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1

DOE LLW classification rationale  

Science Conference Proceedings (OSTI)

This report was about the rationale which the US Department of Energy had with low-level radioactive waste (LLW) classification. It is based on the Nuclear Regulatory Commission's classification system. DOE site operators met to review the qualifications and characteristics of the classification systems. They evaluated performance objectives, developed waste classification tables, and compiled dose limits on the waste. A goal of the LLW classification system was to allow each disposal site the freedom to develop limits to radionuclide inventories and concentrations according to its own site-specific characteristics. This goal was achieved with the adoption of a performance objectives system based on a performance assessment, with site-specific environmental conditions and engineered disposal systems.

Flores, A.Y.

1991-09-16T23:59:59.000Z

2

DOE LLW classification rationale  

Science Conference Proceedings (OSTI)

This report was about the rationale which the US Department of Energy had with low-level radioactive waste (LLW) classification. It is based on the Nuclear Regulatory Commission`s classification system. DOE site operators met to review the qualifications and characteristics of the classification systems. They evaluated performance objectives, developed waste classification tables, and compiled dose limits on the waste. A goal of the LLW classification system was to allow each disposal site the freedom to develop limits to radionuclide inventories and concentrations according to its own site-specific characteristics. This goal was achieved with the adoption of a performance objectives system based on a performance assessment, with site-specific environmental conditions and engineered disposal systems.

Flores, A.Y.

1991-09-16T23:59:59.000Z

3

ANP LLW Management Review  

Science Conference Proceedings (OSTI)

The use of mobile LLW treatment and conditioning systems as a replacement for outdated or worn out permanently installed systems has provided significant flexibility and cost benefit at nuclear power plants over the past decade. The ability to select, install, and operate mobile systems successfully is dependent on advance planning, both in terms of waste management strategy and plant design. This report identifies mobile system technologies that utilities can use at any existing plant or ANP to treat or...

2005-08-11T23:59:59.000Z

4

IRA-WDS: A GIS-based risk analysis tool for water distribution systems  

Science Conference Proceedings (OSTI)

This paper presents the development of a new software tool IRA-WDS. This GIS-based software predicts the risks associated with contaminated water entering water distribution systems from surrounding foul water bodies such as sewers, drains and ditches. ... Keywords: Contaminant intrusion, Developing countries, GIS, Intermittent water supply, Risk assessment, Tight coupling, Water supply

K. Vairavamoorthy; Jimin Yan; Harshal M. Galgale; Sunil D. Gorantiwar

2007-07-01T23:59:59.000Z

5

LLW Notes: Volume 10, Number 8  

SciTech Connect

The Low-Level Radioactive Waste Forum is an association of state and compact representatives, appointed by governors and compact commissions, established to facilitate state and compact implementation of the Low-Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The LLW Forum provides an opportunity for state and compact officials to share information with one another and to exchange views with officials of federal agencies and other interested parties.

Norris, C. [ed.] [Afton Associates, Inc., Washington, DC (United States)

1995-12-06T23:59:59.000Z

6

EPRI Global LLW Profile - Generation, Treatment, Conditioning, and Disposition  

Science Conference Proceedings (OSTI)

In the past several years, the Electric Power Research Institutes (EPRIs) international membership has expanded significantly. As EPRIs membership demographics shift, the absence of a comprehensive global understanding of low level waste (LLW) practices limits our ability to effectively provide technically accurate dialogue and assistance. Understanding LLW waste generation, classification, packaging, treatment, conditioning and disposition profiles is imperative when providing ...

2012-11-29T23:59:59.000Z

7

Managing commercial low-level radioactive waste beyond 1992: Transportation planning for a LLW disposal facility  

Science Conference Proceedings (OSTI)

This technical bulletin presents information on the many activities and issues related to transportation of low-level radioactive waste (LLW) to allow interested States to investigate further those subjects for which proactive preparation will facilitate the development and operation of a LLW disposal facility. The activities related to transportation for a LLW disposal facility are discussed under the following headings: safety; legislation, regulations, and implementation guidance; operations-related transport (LLW and non-LLW traffic); construction traffic; economics; and public involvement.

Quinn, G.J. [Wastren, Inc. (United States)

1992-01-01T23:59:59.000Z

8

Development of New LLW Disposal Options: Phase I Interim Report on the EPRI Industry Strategic Database  

Science Conference Proceedings (OSTI)

Nuclear utilities need a comprehensive industry-wide LLW database to provide intelligence for executive level decision making related to the future of LLW disposal and clearance practices. NEI, the NRC and EPA are requesting this data. The US Government Accounting Office (GAO) also referenced a lack of reliable industry LLW data in its 2004 report on future US LLW disposal options. This report provides initial results from the EPRI initiative filling this data gap.

2005-12-06T23:59:59.000Z

9

Review of Westinghouse AP1000 LLW Management Program  

Science Conference Proceedings (OSTI)

Significant operational cost and waste volume reduction savings opportunities exist, based upon current low level waste (LLW) treatment technology gains, for future operators of the AP1000 reactors. This report is a summary of a review of the AP1000 Radioactive Waste Management Program as defined in the EPRI Utility Requirements Document (URD) and the AP1000 Design Control Document (DCD).

2003-11-19T23:59:59.000Z

10

LLW Forum meeting report, May 7--9, 1997  

Science Conference Proceedings (OSTI)

The Low-Level Radioactive Waste Forum met in Chicago, Illinois, on may 7--9, 1997. Twenty-three Forum Participants, Alternate Forum Participants, and meeting designees representing 20 compacts and states participated. A report on the meeting is given under the following subtitles: New developments in states and compacts; Upgrading an existing disposal facility; Revisions to DOE Order 5820 re DOE waste management; Conference of radiation control program directors: Recent and upcoming activities; National Conference of State Legislatures` (NCSL) low-level radioactive waste working group: Recent and upcoming activities; Executive session; LLW forum business session; Public involvement and risk communication: Success at West Valley, New York; DOE low-level waste management program; impact of the International Atomic Energy Agency`s convention on waste; Panel discussion: The environmental justice concept--Past, present and future; New technologies for processing and disposal of LLRW; High-level and low-level radioactive waste: A dialogue on parallels and intersections; Draft agreement re uniform application of manifesting procedures; Regulatory issues focus; LLW forum October 1997 agenda planning; Resolutions; LLW forum regulatory issues discussion group meets; and Attendance.

Norris, C.; Brown, H. [eds.; Lovinger, T.; Scheele, L.; Shaker, M.A.

1997-12-31T23:59:59.000Z

11

LLW Forum meeting report, October 20--22, 1997  

Science Conference Proceedings (OSTI)

The Low-Level Radioactive Waste Forum met in Annapolis, Maryland, on October 20--22, 1997. Twenty-six Forum Participants, Alternate Forum Participants, and meeting designees representing 22 compacts and states participated. A report on the meeting is given under the following subtitles: New developments in states and compacts; Discussion with NRC Commissioner McGaffigan; Regulatory issues session; Executive session; LLW forum business session; DOE low-level waste management program; Transportation of radioactive waste; Environmental equity: Title VI; Congressional studies on Ward Valley Site; Implementation of DOE`s strategy for waste management; Relicensing Envirocare; Draft agreement for uniform application of manifesting procedures; CRCPD report; Panel: Future of low-level radioactive waste management; Agenda planning: February 1998; Resolutions; and Attendance.

Norris, C.; Brown, H. [eds.; Lovinger, T.; Scheele, L.; Shaker, M.A.

1997-12-31T23:59:59.000Z

12

LLW Forum meeting report, April 25--27, 1994  

SciTech Connect

The Low-Level radioactive Waste Forum is an association of representatives of states and compacts established to facilitate state and compact commission implementation of the Low-Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The Forum provides an opportunity for states and compacts to share information with one another and to exchange views with officials of federal agencies. LLW Forum participants include representatives from regional compacts, designated host states, unaffiliated states, and states with currently-operating low-level radioactive waste facilities. This quarterly meeting was held April 25-27, 1994 and activities during the first quarter of 1994 are detailed..

NONE

1994-12-31T23:59:59.000Z

13

Selection of models to calculate the LLW source term  

Science Conference Proceedings (OSTI)

Performance assessment of a LLW disposal facility begins with an estimation of the rate at which radionuclides migrate out of the facility (i.e., the source term). The focus of this work is to develop a methodology for calculating the source term. In general, the source term is influenced by the radionuclide inventory, the wasteforms and containers used to dispose of the inventory, and the physical processes that lead to release from the facility (fluid flow, container degradation, wasteform leaching, and radionuclide transport). In turn, many of these physical processes are influenced by the design of the disposal facility (e.g., infiltration of water). The complexity of the problem and the absence of appropriate data prevent development of an entirely mechanistic representation of radionuclide release from a disposal facility. Typically, a number of assumptions, based on knowledge of the disposal system, are used to simplify the problem. This document provides a brief overview of disposal practices and reviews existing source term models as background for selecting appropriate models for estimating the source term. The selection rationale and the mathematical details of the models are presented. Finally, guidance is presented for combining the inventory data with appropriate mechanisms describing release from the disposal facility. 44 refs., 6 figs., 1 tab.

Sullivan, T.M. (Brookhaven National Lab., Upton, NY (United States))

1991-10-01T23:59:59.000Z

14

WDS.cdr  

NLE Websites -- All DOE Office Websites (Extended Search)

Waste Data System Waste Data System The U.S. Department of Energy's (DOE) Waste Isolation Pilot Plant, or WIPP, is responsible for the safe disposal of the nation's defense-related transuranic (TRU) waste. Keeping track of thousands of waste containers disposed at WIPP and in temporary storage at sites across the country can be a challenge. To meet this challenge, DOE has developed an information system for keeping all data related to

15

Feasibility studies on the use of TRUPACT-1 for on-site transportation of DOE LLW  

SciTech Connect

In this paper the authors propose using TRUPACT-I, with modifications to its storage system, to facilitate on-site transportation of US Department of Energy (DOE) low-level waste (LLW). TRUPACT-I was designed as a type-B contact-handled transuranic (CH-TRU) waste transportation system for use in Waste Isolation Pilot Plant-related operations and was subjected to the required type-B container accident tests, which it successfully passed. Thus, from a safety standpoint, TRUPACT-1 is provided with double containment, impact limitation, and fire-retardant capabilities. Furthermore, because TRUPACT-1 was developed to transport CH-TRU waste, which is characterized by a higher total activity, larger decay heat, and higher dose rate than LLW, it would be overqualified for the requirements of LLW transportation.

Hills, C.R.; Banjac, V.; Heger, A.S. (Univ. of New Mexico, Albuquerque (United States))

1993-01-01T23:59:59.000Z

16

Greater-than-Class C Low-Level Radioactive Waste (GTCC LLW) | Department of  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Greater-than-Class C Low-Level Radioactive Waste (GTCC LLW) Greater-than-Class C Low-Level Radioactive Waste (GTCC LLW) A transuranic (TRU) waste shipment makes its way to the Waste Isolation Pilot Plant in Carlsbad, N.M. A transuranic (TRU) waste shipment makes its way to the Waste Isolation Pilot Plant in Carlsbad, N.M. On February 17, 2011, DOE issued the Draft Environmental Impact Statement (EIS) for the Disposal of Greater-Than-Class C (GTCC) Low-Level Radioactive Waste (LLRW) and GTCC-Like Waste (Draft EIS, DOE/EIS-0375D) for public review and comment. DOE is inviting public comments on this Draft EIS during a 120-day public comment period, from the date of publication of the EIS's Notice of Availability in the Federal Register. During the comment

17

Test Plan: Phase 1, Hanford LLW melter tests, GTS Duratek, Inc.  

SciTech Connect

This document provides a test plan for the conduct of vitrification testing by a vendor in support of the Hanford Tank Waste Remediation System (TWRS) Low-Level Waste (LLW) Vitrification Program. The vendor providing this test plan and conducting the work detailed within it [one of seven selected for glass melter testing under Purchase Order MMI-SVV-384215] is GTS Duratek, Inc., Columbia, Maryland. The GTS Duratek project manager for this work is J. Ruller. This test plan is for Phase I activities described in the above Purchase Order. Test conduct includes melting of glass with Hanford LLW Double-Shell Slurry Feed waste simulant in a DuraMelter{trademark} vitrification system.

Eaton, W.C.

1995-06-14T23:59:59.000Z

18

Proven concepts for LLW-treatment of large components for free release and recycling  

Science Conference Proceedings (OSTI)

This paper describes Studsvik's technical concept of LLW-treatment of large, retired components from nuclear installations in operation or in decommissioning. Many turbines, heat exchangers and other LLW components have been treated in Studsvik during the last 20 years. This also includes development of techniques and tools, especially our latest experience gained under the pilot project for treatment of one full size PWR steam generator from Ringhals NPP, Sweden. The ambition of this pilot project was to minimize the waste volumes for disposal and to maximize the material recycling. Another objective, respecting ALARA, was the successful minimization of the dose exposure to the personnel. The treatment concept for large, retired components comprises the whole sequence of preparations from road and sea transports and the management of the metallic LLW by segmentation, decontamination and sorting using specially devised tools and shielded treatment cell, to the decision criteria for recycling of the metals, radiological analyses and conditioning of the residual waste into the final packages suitable for customer-related disposal. For e.g. turbine rotors with their huge number of blades the crucial moments are segmentation techniques, thus cold segmentation is a preferred method to keep focus on minimization of volumes for secondary waste. Also a variety of decontamination techniques using blasting cabinet or blasting tumbling machines keeps secondary waste production to a minimum. The technical challenge of the treatment of more complicated components like steam generators also begins with the segmentation. A first step is the separation of the steam dome in order to dock the rest of the steam generator to a specially built treatment cell. Thereafter, the decontamination of the tube bundle is performed using a remotely controlled manipulator. After decontamination is concluded the cutting of the tubes as well as of the shell is performed in the same cell with remotely controlled tools. Some of the sections of steam dome shell or turbine shafts can be cleared directly for unconditional reuse without melting after decontamination and sampling program. Experience shows that the amount of material possible for clearance for unconditional use is between 95 - 97 % for conventional metallic scrap. For components like turbines, heat exchangers or steam generators the recycling ratio can vary to about 80 - 85% of the initial weight. (authors)

Bergstroem, Lena; Lindstrom, Anders; Lindberg, Maria; Wirendal, Bo; Lorenzen, Joachim [Studsvik RadWaste AB, SE-611 82 Nykoeping (Sweden)

2007-07-01T23:59:59.000Z

19

LLW (Low-Level Waste) Notes, special edition, Volume 13, Number 3, April 1998  

SciTech Connect

This special edition of LLW Notes focuses upon the federal government`s attempts to implement environmental justice policies through a variety of mechanisms, including the federal licensing process; the formation of a federal advisory committee; the filing of an amicus curiae brief in a federal court case; and the administrative complaint process under Title VI of the Civil Rights Act. In the absence of clearly defined criteria for implementing the environmental justice concept, an examination of the individual mechanisms being used by the federal government can indicate the eventual scope of federal environmental justice initiatives. Also contained in this issue is a chart depicting the administrative complaints concerning environmental justice that have been filed with the US Environmental Protection Agency under Title VI of the Civil Rights Act. The chart lists information for only those complaints that have been filed with EPA, which is the lead federal agency for environmental justice. EPA has received the vast majority of environmental justice administrative complaints.

NONE

1998-04-01T23:59:59.000Z

20

COMPOSITE ANALYSIS OF LLW DISPOSAL FACILITIES AT THE U.S. DEPARTMENT OF ENERGY'S SAVANNAH RIVER SITE  

Science Conference Proceedings (OSTI)

Composite Analyses (CA's) are required per DOE Order 435.1 [1], in order to provide a reasonable expectation that DOE low-level waste (LLW) disposal, high-level waste tank closure, and transuranic (TRU) waste disposal in combination with Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), Resource Conservation and Recovery Act (RCRA), and deactivation and decommissioning (D&D) actions, will not result in the need for future remedial actions in order to ensure radiological protection of the public and environment. This Order requires that an accounting of all sources of DOE man-made radionuclides and DOE enhanced natural radionuclides that are projected to remain on the site after all DOE site operations have ceased. This CA updates the previous CA that was developed in 1997. As part of this CA, an inventory of expected radionuclide residuals was conducted, exposure pathways were screened and a model was developed such that a dose to the MOP at the selected points of exposure might be evaluated.

Hiergesell, R; Mark Phifer, M; Frank02 Smith, F

2009-01-08T23:59:59.000Z

Note: This page contains sample records for the topic "non-hlw wds llw" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


21

Management of nuclear materials and non-HLW | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

including plutonium, uranium, and nuclear waste in accordance with applicable statutes, DOE Orders and international commitments. Advice encompasses issues related to mixed oxide...

22

LLW Forum meeting report  

SciTech Connect

This document reports the details of the Quarterly Meeting of the Low- Level Radioactive Waste Forum held in San Diego, California during January 23-25, 1991. Topics discussed include: State and Compact Progress Reports; Legal Updates; Update on Technical Assistance; Advanced Notice of Proposed Rulemaking Regarding Surcharge Rebates; Update on TCC Activities; NRC Update; Disposal of Commercial Mixed Waste; Update on EPA Activities; ACNW Working Group on Mixed Waste; National Profile on Mixed Waste; Commercial Perspective on Mixed Waste; Update on DOT Activities; Source Terms; Materials and Waste; Storage: and Waste Acceptance Criteria and Packaging.

NONE

1991-12-31T23:59:59.000Z

23

Control of water infiltration into near surface LLW disposal units. Progress report on field experiments at a humid region site, Beltsville, Maryland: Volume 8  

SciTech Connect

This study`s objective is to assess means for controlling water infiltration through waste disposal unit covers in humid regions. Experimental work is being performed in large-scale lysimeters 21.34 m x 13.72 m x 3.05 m (75 ft x 45 ft x 10 ft) at Beltsville, Maryland. Results of the assessment are applicable to disposal of low-level radioactive waste (LLW), uranium mill tailings, hazardous waste, and sanitary landfills. Three kinds of waste disposal unit covers or barriers to water infiltration are being investigated: (1) resistive layer barrier, (2) conductive layer barrier, and (3) bioengineering management. The resistive layer barrier consists of compacted earthen material (e.g., clay). The conductive layer barrier consists of a conductive layer in conjunction with a capillary break. As long as unsaturated flow conditions are maintained, the conductive layer will wick water around the capillary break. Below-grade layered covers such as (1) and (2) will fail if there is appreciable subsidence of the cover, and remedial action for this kind of failure will be difficult. A surface cover, called bioengineering management, is meant to overcome this problem. The bioengineering management surface barrier is easily repairable if damaged by subsidence; therefore, it could be the system of choice under active subsidence conditions. The bioengineering management procedure also has been shown to be effective in dewatering saturated trenches and could be used for remedial action efforts. After cessation of subsidence, that procedure could be replaced by a resistive layer barrier or, perhaps even better, by a resistive layer barrier/conductive layer barrier system. The latter system would then give long-term effective protection against water entry into waste without institutional care.

Schulz, R.K. [California Univ., Los Angeles, CA (United States); Ridky, R.W. [Maryland Univ., College Park, MD (United States). Dept. of Geology; O`Donnell, E. [Nuclear Regulatory Commission, Washington, DC (United States)

1995-04-01T23:59:59.000Z

24

Emerging LLW Technologies: Dissolvable Clothing  

Science Conference Proceedings (OSTI)

Management of the solid waste associated with radiological protective clothing, and its associated low level liquid laundry waste, has been a burden for the nuclear power industry. A recent technological development utilizing polyvinyl alcohol (PVA) clothing and off site processing represents a sound solution to this challenge. This report represents a technical and economic evaluation of the utility use of PVA clothing.

2002-08-20T23:59:59.000Z

25

Solidification Tests for LLW Sludges  

Science Conference Proceedings (OSTI)

Oak Ridge National laboratory has about 350,000 gallons of remote-handled (RH) sludge in ten liquid low-level waste (LLLW) tanks that must be solidified and stabilized for disposal at the Nevada Test Site. Samples of the waste sludge were collected from four tanks, and a total of 36 small-scale grouting tests were performed. The presence of free water during curing was evaluated, and the cured grouts were analyzed using the Toxicity Characteristic Leaching Procedure (TCLP) to determine if any of the hazardous metals in the sludge (Cd, Cr, Hg, Pb, etc.) would leach above the Resource Conservation and Recovery Act (RCRA) limits/ The grouting formulation used for these tests, with ratios of grout-forming additives weight to waste slurry weight ranging from 0.75:1 to 1.2:1, produced wet grout mixtures that were easy to stir and were self leveling. The grout mixtures cured with no free water visible at any time. The cured grout matrix was very effective at retaining the hazardous metals in the sludge, with TCLP leachate concentrations well below the RCRA limits. The addition of ferrous sulfide (FeS) to some of the sludge samples resulted in, at most, a minimal reduction in the amount of mercury that leached from the grout samples, and had no detectable impact on the other heavy metals present in the sludge (Cd, Cr, and Pb). The TCLP extraction was performed on three samples after 1 day and 7 days of curing, compared to the >28 days for the remaining samples. The metal concentrations for the short cure time samples were similar to the remaining samples, and were all well below the RCRA limits.

Taylor, Paul Allen [ORNL

2009-01-01T23:59:59.000Z

26

LLW Notes, Volume 12, Number 8  

Science Conference Proceedings (OSTI)

Contents include articles entitled: Chem-Nuclear documents new plan for Barnwell; Nebraska releases technical analysis of LLRW facility; Southeast Compact suspends funding for NC facility development; NC governor and Southeast Compact differ on proposed MOU; Midwest Compact to return export fees; State legislators` group revises radioactive waste policy; Internal documents discuss administration`s policy on Ward Valley; BLM issues EA for Ward Valley testing; California DHS, NRC criticize DOI`s testing protocols; Army removes training mines from Ward Valley site; The 1997 gubernatorial elections and a look ahead to 1998; Court throws out case challenging Pennsylvania`s siting law; DOE files notice of appeal in WCS suit; Central Compact moves to dismiss ``Veto`` authority suit; Congress exempts NAS from FACA; Judge sets schedule for Ward Valley case; Court won`t order DOE to accept spent fuel by deadline; NRC chairman expresses concern re CERCLA reauthorization; Senators question EPA`s guidance on remediation; EPA issues guidance, criticizes NRC decommissioning rule; Members of Congress clarify FUSRAP transfer; HLW legislation passes House by wide margin; Takings legislation passes House; Energy and water bill signed into law; and Senate confirms 5 of 6 DOE appointees.

Norris, C.; Brown, H. [eds.; Gedden, R.; Lovinger, T.; Scheele, L.; Shaker, M.A.

1997-12-31T23:59:59.000Z

27

LLW Notes, Volume 12, Number 1  

Science Conference Proceedings (OSTI)

Contents include articles entitled: Suit against Envirocare sparks investigations: Formal petition filed with NRC; Group alleges misconduct by USGS re Beatty study; EPA rescinds NESHAPs subpart 1; Northwest Compact executive director changes jobs; New forum participant for the state of New Jersey; and Director of North Carolina division of radiation control retires.

Norris, C.; Brown, H. [eds.; Colsant, J.; Lovinger, T.; Scheele, L.; Shaker, M.A.

1997-01-01T23:59:59.000Z

28

LLW Notes, Volume 12, Number 7  

SciTech Connect

Contents include articles entitled: House votes 309 to 107 to approve Texas compact; Nebraska governor hosts LLRW meeting; Southeast Compact considers funding proposal; Chem-Nuclear explores options re SC revenue requirements; Legislation sets revenue requirements for Barnwell; TCC meets: Supports CA request for technical assistance; DOE approves part of California`s technical assistance request; State legislators discuss LLRW management for OH, IL, NC; Washington governor re Potential New Hanford Role; Federal court enjoins DOE from excluding WCS on new disposal; Appellate court in favor of DOE in surcharge rebates dispute; Hearing set for October in Ward Valley case; court rejects federal motion to dismiss Ward Valley suit; NE sues commission re veto over export authorizations; US Supreme Court dismisses line-item veto challenge; Department of Interior Inspector General investigation requested; USEC privatization plan approved; DOD finalizes LLRW disposal charter; Clinton nominates six DOE appointees; Congress moves FUSRAP to Army Corps of Engineers; Schaefer named interim director of USGS: Nichols leaves EPA: NRC Commissioner Rogers` term expires; NRC: CA ``Well-Quantified`` to license Ward Valley facility; EPA objects to state permit for Louisiana facility; Petitions submitted to EPA oppose Shintech permits; ECOS draft recommendations re Enviro programs; Legislation introduced to prohibit spent fuel shipments to the Goshutes; and HLW legislation ready for floor action.

Norris, C.; Brown, H. [eds.; Gedden, R.; Lovinger, T.; Scheele, L.; Shaker, M.A.

1997-09-01T23:59:59.000Z

29

LLW Notes, Volume 12, Number 6  

Science Conference Proceedings (OSTI)

Contents include articles entitled: GAO concludes most Ward Valley SEIS issues previously addressed; Midwest compact halts facility development; Texas publishes proposal to issue WCS radioactive materials license; Central Compact issues export authorizations over NE`s objection; Nebraska governor to host LLRW summit; California regulators reassured re US ecology facility in WA; Southeast Compact augments funding for North Carolina; State and compact calendar of events; IAEA Director General to UN: reexamine nuclear power; DOI convenes meetings on Ward Valley Title VI complaint; California BLM: Tribes fully represented and consulted; MW, NE, and SW file amici curiae briefs in Ward Valley suit; Court denies state`s motion for protective order; WCS files suit against Envirocare and others; States attack DOE`s claim re lack of authority to store spent fuel; House committee passes Texas legislation; Ward Valley land transfer bill introduced in Senate; Senate committee holds hearing on Ward Valley legislation and related GAO report; NRDC threatens to sue DOE re Envirocare; NRC chair criticizes Deputy Interior Secretary`s use of Ward Valley fact sheet; Utility consortium submits license application for storage on Goshute land to NRC; Envirocare cited for SNM violation; EPA begins audit; and EPA rejects Title VI claim re Texas site.

Norris, C.; Brown, H. [eds.; Gedden, R.; Lovinger, T.; Scheele, L.; Shaker, M.A.

1997-07-01T23:59:59.000Z

30

LLW Notes, Volume 12, Number 5  

SciTech Connect

Contents include articles entitled: USGS report supports previous conclusions re tritium migration at Beatty; Ohio selects new contractor for screening; Maine Yankee`s future uncertain; Southeast Compact limits funds for North Carolina project; California, Energy, and Interior exchange correspondence on Ward Valley testing; TCC meets in Salt Lake City, Utah; Garner named executive director and forum participant for Northwest Compact; Seventh Circuit upholds Energy Secretary`s determination re distribution of surcharge rebates; US Ecology sues Nebraska re wetlands mitigation; US Supreme Court hears line-item veto challenge; Court rules NAS must provide public access; WCS sues Envirocare of Texas; DOE and Envirocare sign consent agreement; NRC issues performance assessment guidance; NRC to publish final decommissioning rule; House subcommittee passes Texas Consent Act; Environmental justice bill introduced in the House; and International nuclear safety body established.

Norris, C.; Brown, H. [eds.; Gedden, R.; Lovinger, T.; Scheele, L.; Shaker, M.A.

1997-06-01T23:59:59.000Z

31

LLW Notes, Volume 12, Number 2  

SciTech Connect

Contents include the following articles: National Environmental Justice Advisory Council considers Ward Valley resolution; NGA urges Congressional and Presidential support for low-level radioactive waste compacts and transfer of federal land in Ward Valley; RFP issued for SEIS on Ward Valley land transfer; Illinois siting criteria finalized; Consideration of tribal concerns during Ward Valley siting process; State legislators` LLRW working group meets in D.C.; Upcoming state and compact events; Court calendar; Texas compact legislation introduced in Congress; Superfund reform is a priority for 105th Congress; High-level waste bill gets off to an early start; Fort Mojave petition NEJAC for Ward Valley resolution; EPA withdraws cleanup rule from OMB; Board ruling raises doubts about proposed Louisiana enrichment facility; DOE recommends external regulation by NRC; and Supplement--Background on environmental justice.

Norris, C.; Brown, H. [eds.; Colsant, J.; Lovinger, T.; Scheele, L.; Shaker, M.A.

1997-02-01T23:59:59.000Z

32

LLW Notes supplement, Volume 12, Number 6  

SciTech Connect

Contents include articles related to environmental justice concerns and Title VI, entitled as follows: Civil Rights Act of 1964; Exec order on environmental justice; Applicability to states; Philosophical differences -- Environmental justice and Title VI; Ambiguities in existing Title VI guidance; Clarification of existing Title VI guidance; Federal financial assistance; Administrative complaints vs. lawsuits; Effect and disparate impact; Termination, suspension or refusal to grant federal financial assistance; DOJ guidance defines environmental justice; NEJAC meets, adopts far-reaching resolution re siting; Indigenous Peoples Resolution No. 23; and States meet, support environmental justice concept and express concerns about federal approach and composition of NEJAC.

NONE

1997-07-01T23:59:59.000Z

33

Potential GTCC LLW sealed radiation source recycle initiatives  

SciTech Connect

This report suggests 11 actions that have the potential to facilitate the recycling (reuse or radionuclide) of surplus commercial sealed radiation sources that would otherwise be disposed of as greater-than-Class C low-level radioactive waste. The suggestions serve as a basis for further investigation and discussion between the Department of Energy, Nuclear Regulatory Commission, Agreement States, and the commercial sector. Information is also given that describes sealed sources, how they are used, and problems associated with recycling, including legal concerns. To illustrate the nationwide recycling potential, Appendix A gives the estimated quantity and application information for sealed sources that would qualify for disposal in commercial facilities if not recycle. The report recommends that the Department of Energy initiate the organization of a forum to explore the suggested actions and other recycling possibilities.

Fischer, D.

1992-04-01T23:59:59.000Z

34

LLW Forum summary report, volume 2. No. 2. June 1994  

Science Conference Proceedings (OSTI)

Information provided for each compact and its host state includes: governing body, member states, compact establishment date, current waste management, regulatory and program responsibility, siting responsibility, other involvement, disposal technology, siting, licensing, development costs, and operational date.

NONE

1994-06-01T23:59:59.000Z

35

DAW and Mixed LLW Processing and Volume Reduction Technologies  

Science Conference Proceedings (OSTI)

This report serves as a reference handbook of major Dry Active Waste (DAW) and Mixed Waste (MW) treatment technologies commercially available to the commercial nuclear power industry. The report also identifies major DAW and MW treatment facilities available. Brief descriptions are provided for each available technology, and a brief overview addresses the capabilities of each waste treatment facility.

1999-12-07T23:59:59.000Z

36

Performance Evaluation of Advanced LLW Liquid Processing Technology: Boiling Water Reactor Liquid Processing  

Science Conference Proceedings (OSTI)

This report provides condensed information on boiling water reactor (BWR) membrane based liquid radwaste processing systems. The report presents specific details of the technology, including design, configuration, and performance. This information provides nuclear plant personnel with data useful in evaluating the merits of applying advanced processes at their plant.

2001-11-26T23:59:59.000Z

37

Potential GTCC LLW sealed radiation source recycle initiatives. National Low-Level Waste Management Program  

SciTech Connect

This report suggests 11 actions that have the potential to facilitate the recycling (reuse or radionuclide) of surplus commercial sealed radiation sources that would otherwise be disposed of as greater-than-Class C low-level radioactive waste. The suggestions serve as a basis for further investigation and discussion between the Department of Energy, Nuclear Regulatory Commission, Agreement States, and the commercial sector. Information is also given that describes sealed sources, how they are used, and problems associated with recycling, including legal concerns. To illustrate the nationwide recycling potential, Appendix A gives the estimated quantity and application information for sealed sources that would qualify for disposal in commercial facilities if not recycle. The report recommends that the Department of Energy initiate the organization of a forum to explore the suggested actions and other recycling possibilities.

Fischer, D.

1992-04-01T23:59:59.000Z

38

FCRD-USED-2010-000033, LLW Quantity and Inventory, FINAL R...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Cycle Research and Development Cycle Research and Development Used Fuel Disposition Low Level Waste Disposition - Quantity and Inventory Prepared for U.S. Department of Energy Used Nuclear Fuel Robert H. Jones, SRS June 2011 Revision 2 FCRD-USED-2010-000033 FCRD-USED-2010-000033 Fuel Cycle Research and Development June 2011 Used Fuel Disposition Revision 2 Low Level Waste - Quantity and Inventory Page ii of x THIS PAGE INTENTIONALLY LEFT BLANK

39

Utility Position Report on Significant Design Considerations for the Westinghouse AP1000 LLW Management Program  

Science Conference Proceedings (OSTI)

The nuclear power industry has made significant improvements in the performance of radioactive waste operations in the past decade. In order to ensure that utilities are able to take advantage of these cost and performance advances in new plants, EPRI has been leading a team of utility experts in the review of advanced nuclear plant (ANP) radwaste designs. The purpose of this Utility Position Report is to clarify the key recommendations developed by industry experts on the AP1000 design for low-level rad...

2004-12-06T23:59:59.000Z

40

Discovery of New Plutonium Chemistry and Its Potential Effect on LLW Disposal at SRS  

DOE Green Energy (OSTI)

Recently published work on the chemistry of plutonium (IV) dioxide has shown that PuO{sub 2} is not the thermodynamically stable form as was previously thought. In humid environments or the presence of water, some of the plutonium is oxidized to Pu (VI) with the evolution of hydrogen and the formation of PuO2 plus x, where x can range up to 0.27 (i.e. about 27 percent of the Pu has been oxidized to the plus 6 oxidation state). The implication of this discovery is that a more mobile form of plutonium (i.e. Pu (VI)) than that assumed in the performance assessment (i.e. Pu (IV)) could be present in the humid waste disposal environment. If so, then the approved performance assessment might not conservatively bound the effects of plutonium waste disposal.

Wilhite, E.L.

2001-09-11T23:59:59.000Z

Note: This page contains sample records for the topic "non-hlw wds llw" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


41

FCRD-USED-2010-000033, LLW Quantity and Inventory, FINAL R.....  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

and Development Used Fuel Disposition Low Level Waste Disposition - Quantity and Inventory Prepared for U.S. Department of Energy Used Nuclear Fuel Robert H. Jones, SRS June...

42

Development of high integrity, maximum durability concrete structures for LLW disposal facilities  

SciTech Connect

A number of disposal facilities for Low-Level Radioactive Wastes have been planned for the Savannah River Site. Design has been completed for disposal vaults for several waste classifications and construction is nearly complete or well underway on some facilities. Specific design criteria varies somewhat for each waste classification. All disposal units have been designed as below-grade concrete vaults, although the majority will be above ground for many years before being encapsulated with earth at final closure. Some classes of vaults have a minimum required service life of 100 years. All vaults utilize a unique blend of cement, blast furnace slag and pozzolan. The design synthesizes the properties of the concrete mix with carefully planned design details and construction methodologies to (1) eliminate uncontrolled cracking; (2) minimize leakage potential; and (3) maximize durability. The first of these vaults will become operational in 1992. 9 refs.

Taylor, W.P. [Main (Charles T.), Inc., Charlotte, NC (United States)

1992-05-01T23:59:59.000Z

43

Development of high integrity, maximum durability concrete structures for LLW disposal facilities  

SciTech Connect

A number of disposal facilities for Low-Level Radioactive Wastes have been planned for the Savannah River Site. Design has been completed for disposal vaults for several waste classifications and construction is nearly complete or well underway on some facilities. Specific design criteria varies somewhat for each waste classification. All disposal units have been designed as below-grade concrete vaults, although the majority will be above ground for many years before being encapsulated with earth at final closure. Some classes of vaults have a minimum required service life of 100 years. All vaults utilize a unique blend of cement, blast furnace slag and pozzolan. The design synthesizes the properties of the concrete mix with carefully planned design details and construction methodologies to (1) eliminate uncontrolled cracking; (2) minimize leakage potential; and (3) maximize durability. The first of these vaults will become operational in 1992. 9 refs.

Taylor, W.P. (Main (Charles T.), Inc., Charlotte, NC (United States))

1992-01-01T23:59:59.000Z

44

Office of the Assistant General Counsel for Civilian Nuclear...  

NLE Websites -- All DOE Office Websites (Extended Search)

Waste (HLW) and Spent Nuclear Fuel (SNF) Management of Nuclear Materials and Non-HLW Nuclear Fuel Cycle Energy Research and Development Non-Proliferation Nuclear Regulatory...

45

Microsoft PowerPoint - 435 Update - PACof P.ppt  

NLE Websites -- All DOE Office Websites (Extended Search)

1988 * Several attempts to revise 5820.2A * DNFSB Recommendation 94-2 - LLW forecasting and capacity planning inadequate - Characterization of LLW ineffective - LLW with...

46

RH-LLW Disposal Facility Project CD-2/3 to Design/Build Proposal Reconciliation Report  

SciTech Connect

A reconciliation plan was developed and implemented to address potential gaps and responses to gaps between the design/build vendor proposals and the Critical Decision-2/3 approval request package for the Remote-Handled Low Level Waste Disposal Facility Project. The plan and results of the plan implementation included development of a reconciliation team comprised of subject matter experts from Battelle Energy Alliance and the Department of Energy Idaho Operations Office, identification of reconciliation questions, reconciliation by the team, identification of unresolved/remaining issues, and identification of follow-up actions and subsequent approvals of responses. The plan addressed the potential for gaps to exist in the following areas: Department of Energy Order 435.1, Radioactive Waste Management, requirements, including the performance assessment, composite analysis, monitoring plan, performance assessment/composite analysis maintenance plan, and closure plan Environmental assessment supporting the National Environmental Policy Act Nuclear safety Safeguards and security Emplacement operations Requirements for commissioning General project implementation. The reconciliation plan and results of the plan implementation are provided in a business-sensitive project file. This report provides the reconciliation plan and non-business sensitive summary responses to identified gaps.

Annette L. Schafer

2012-06-01T23:59:59.000Z

47

MLW, TRU, LLW, MIXED, HAZARDOUS WASTES AND ENVIRONMENTAL RESTORATION. WASTE MANAGEMENT/ENERGY SECURITY AND A CLEAN ENVIRONMENT. DFR Decommissioning: the Breeder Fuel Processing  

SciTech Connect

The Dounreay site, in North Scotland, was opened in 1955 and a wide range of nuclear facilities have been built and operated there by UKAEA (The United Kingdom Atomic Energy Authority) for the development of atomic energy research. The Dounreay Fast Reactor (DFR) was built between 1955 and 1957, and operated until 1977 for demonstration purposes and for producing electricity. Today, its decommissioning is a key part of the whole Dounreay Site Restoration Plan that integrates the major decommissioning activities such as the fuel treatment and the waste management. The paper presents the contract strategy and provides an overview of the BFR project which consists in the removal of the breeder elements from the reactor and their further treatment. It mainly provides particular details of the Retrieval and Processing Facilities design.

Bonnet, C.; Potier, P.; Ashton, Brian Morris

2003-02-27T23:59:59.000Z

48

LLW Forum summary report: Volume 2, Number 1.1, February 1994: Low-level radioactive waste management activities in the states and compacts  

Science Conference Proceedings (OSTI)

Information presented for compacts and their home states includes: regulatory and program responsibility; siting responsibility, other involvement; siting; licensing; development costs; and disposal facility operation.

Norris, C. [ed.

1994-02-01T23:59:59.000Z

49

Physical, Chemical and Structural Evolution of Zeolite-Containing Waste Forms Produced from Metakaolinite and Calcined Sodium Bearing Waste (HLW and/or LLW)  

SciTech Connect

Zeolites are extremely versatile. They can adsorb liquids and gases and serve as cation exchange media. They occur in nature as well cemented deposits. The ancient Romans used blocks of zeolitized tuff as a building material. Using zeolites for the management of radioactive waste is not a new idea, but a process by which the zeolites can be made to act as a cementing agent is. Zeolitic materials are relatively easy to synthesize from a wide range of both natural and man-made substances. The process under study is derived from a well known method in which metakaolin (an impure thermally dehydroxylated kaolinite heated to {approx}700 C containing traces of quartz and mica) is mixed with sodium hydroxide (NaOH) and reacted in slurry form (for a day or two) at mildly elevated temperatures. The zeolites form as finely divided powders containing micrometer ({micro}m) sized crystals. However, if the process is changed slightly and only just enough concentrated sodium hydroxide solution is added to the metakaolinite to make a thick crumbly paste and then the paste is compacted and cured under mild hydrothermal conditions (60-200 C), the mixture will form a hard ceramic-like material containing distinct crystalline tectosilicate minerals (zeolites and feldspathoids) imbedded in an X-ray amorphous hydrated sodium aluminosilicate matrix. Due to its lack of porosity and vitreous appearance we have chosen to call this composite a ''hydroceramic''.

Grutzeck, Michael W.

2005-06-27T23:59:59.000Z

50

Interim On-Site Storage of Low-Level Waste: Volume 3, Part 2: User's Manual and Lotus Spreadsheet for Estimating LLW Volumes and Act ivities  

Science Conference Proceedings (OSTI)

This volume of the "Interim On-Site Storage" report series supplements Volume 3, Part 1, "Waste Volume Projections and Data Management." Because that volume includes an extensive methodology and a number of worksheets requiring many calculations, users requested a computer program for easily storing, managing, and manipulating applicable data. Volume 3, Part 2 consists of a user's manual and a Lotus spreadsheet macro to meet this utility need.

1993-11-01T23:59:59.000Z

51

EIA - Electricity Data - Energy Information Administration  

U.S. Energy Information Administration (EIA)

Energy Information Administration - EIA - Official Energy Statistics from the U.S. Government ... Piedmont Green Power: GA: 57909: GEN1: 53.50: WDS: ST: 2013: 4: 15394:

52

www.eia.gov  

U.S. Energy Information Administration (EIA)

Buck NC Exelon Power Cromby Generating Station PA Eddystone Generating Station IVEX Packaging Paper LLC IVEX Packaging Lavalley Lumber LLC ME WDS State of Wisconsin

53

www.eia.gov  

U.S. Energy Information Administration (EIA)

Combustion Turbine Internal Combustion Engine Agricultural Byproducts AB ... Wood Waste Liquids* WDL Wood Waste Solids WDS Waste Oil* WO Source: 2, Table 1.11-2 Notes:

54

The role of organic complexants and microparticulates in the facilitated transport of radionuclides  

SciTech Connect

This progress report describes the results of ongoing radiological and geochemical investigations of the mechanisms of radionuclide transport in groundwater at two low-level waste (LLW) disposal sites within the waste management area of the Chalk River Laboratories (CRL), Ontario, Canada. These sites, the Chemical Pit liquid disposal facility and the Waste Management Area C solid LLW disposal site, have provided valuable 30- to 40-year-old field locations for characterizing the migration of radionuclides and evaluating a number of recent site performance objectives for LLW disposal facilities. This information will aid the NRC and other federal, state, and local regulators, as well as LLW disposal site developers and waste generators, in maximizing the effectiveness of existing or projected LLW disposal facilities for isolating radionuclides from the general public and thereby improving the health and safety aspects of LLW disposal.

Schilk, A.J.; Robertson, D.E.; Abel, K.H.; Thomas, C.W. [and others

1996-12-01T23:59:59.000Z

55

Interim Storage of Low and Intermediate Level Wastes: Guidelines for Extended Storage  

Science Conference Proceedings (OSTI)

Domestic utilities are responding to impending changes in low-level waste (LLW) disposal site facility availability by extending their capabilities for interim on-site storage of LLW. International utilities likewise face challenges in implementing complete low and intermediate waste disposal options. Therefore, our members asked EPRI to revise and update our series of documents devoted to on-site interim LLW storage. This report represents the key guidelines document for the series.

2002-10-30T23:59:59.000Z

56

Review of private sector and Department of Energy treatment, storage, and disposal capabilities for low-level and mixed low-level waste  

SciTech Connect

Private sector capacity for treatment, storage, and disposal (TSD) of various categories of radioactive waste has been researched and reviewed for the Idaho National Engineering Laboratory (INEL) by Lockheed Idaho Technologies Company, the primary contractor for the INEL. The purpose of this document is to provide assistance to the INEL and other US Department of Energy (DOE) sites in determining if private sector capabilities exist for those waste streams that currently cannot be handled either on site or within the DOE complex. The survey of private sector vendors was limited to vendors currently capable of, or expected within the next five years to be able to perform one or more of the following services: low-level waste (LLW) volume reduction, storage, or disposal; mixed LLW treatment, storage, or disposal; alpha-contaminated mixed LLW treatment; LLW decontamination for recycling, reclamation, or reuse; laundering of radioactively-contaminated laundry and/or respirators; mixed LLW treatability studies; mixed LLW treatment technology development. Section 2.0 of this report will identify the approach used to modify vendor information from previous revisions of this report. It will also illustrate the methodology used to identify any additional companies. Section 3.0 will identify, by service, specific vendor capabilities and capacities. Because this document will be used to identify private sector vendors that may be able to handle DOE LLW and mixed LLW streams, it was decided that current DOE capabilities should also be identified. This would encourage cooperation between DOE sites and the various states and, in some instances, may result in a more cost-effective alternative to privatization. The DOE complex has approximately 35 sites that generate the majority of both LLW and mixed LLW. Section 4.0 will identify these sites by Operations Office, and their associated LLW and mixed LLW TSD units.

Willson, R.A.; Ball, L.W.; Mousseau, J.D.; Piper, R.B.

1996-03-01T23:59:59.000Z

57

Guide for Operating an Interim On-Site Low Level Radioactive Waste Storage Facility  

Science Conference Proceedings (OSTI)

As a result of increasing low-level waste (LLW) disposal site uncertainty, the industry expects that utilities will have to rely on their own on-site storage LLW storage programs in the near future. This report captures essential information related to the operation of an on-site LLW storage program. The report is a comprehensive reference to which utilities can routinely refer throughout the development and implementation of the storage program and operation of the storage facility.

2004-11-16T23:59:59.000Z

58

Waste Containers for Extended Storage of Class A, B and C Wastes, Rev. 1  

Science Conference Proceedings (OSTI)

In response to the potential loss of low-level waste (LLW) disposal capacity for Class B and C Wastes in 2008, EPRI is updating its guidance documents on the interim storage of LLW wastes. This volume provides a comprehensive review of LLW containers and container technologies to help utilities evaluate their options and make selections for extended on-site storage. This revision updates the listings of commercially available containers, adds international containers, and provides minor technical changes...

2003-08-26T23:59:59.000Z

59

LFRG Charter  

Energy.gov (U.S. Department of Energy (DOE))

The Low - Level Waste (LLW) Disposal Facility Federal Review Group (LFRG) Cliarter identifies the purpose, objectives, andmembershiprequirements of the group.

60

Final DUF6 PEIS: Volume 2, Appendix G; Long-Term Storage  

NLE Websites -- All DOE Office Websites (Extended Search)

LLNL Lawrence Livermore National Laboratory LLMW low-level mixed waste LLW low-level radioactive waste MEI maximally exposed individual NEPA National Environmental Policy Act...

Note: This page contains sample records for the topic "non-hlw wds llw" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


61

DOE/ID-Number  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

This includes the storage, transportation, and disposal of low level waste (LLW), used nuclear fuel (UNF), and high level waste (HLW). The Office of Fuel Cycle Technologies...

62

Environmental Impacts of Options for Disposal of Depleted Uranium...  

NLE Websites -- All DOE Office Websites (Extended Search)

study by Oak Ridge National Laboratory evaluated the acceptability of several depleted uranium conversion products at potential LLW disposal sites to provide a basis for DOE...

63

A Characteristics-Based Approach to Radioactive Waste Classification in Advanced Nuclear Fuel Cycles  

E-Print Network (OSTI)

LLW-?GTCC GTCC in NRC criteria. Vitrified glass; Matheson, Jim. Letter to NRC Chairman Dale E California Press, NRC 2008 Nuclear Regulatory

Djokic, Denia

2013-01-01T23:59:59.000Z

64

Remote-Handled Low-Level Waste (RHLLW) Disposal Project Code of Record  

Science Conference Proceedings (OSTI)

The Remote-Handled Low-Level Waste Disposal Project addresses an anticipated shortfall in remote-handled LLW disposal capability following cessation of operations at the existing facility, which will continue until it is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of fiscal year 2015). Development of a new onsite disposal facility, the highest ranked alternative, will provide necessary remote handled LLW disposal capability and will ensure continuity of operations that generate remote-handled LLW. This report documents the Code of Record for design of a new LLW disposal capability.

S.L. Austad, P.E.; L.E. Guillen, P.E.; C. W. McKnight, P.E.; D. S. Ferguson, P.E.

2010-10-01T23:59:59.000Z

65

Microsoft PowerPoint - 7-04 Langton CBP overview Tech Exchange...  

NLE Websites -- All DOE Office Websites (Extended Search)

LLW Disposal Grouted in Vault LAW Disposal in Vaults Presented by Martin J. Letourneau, DOE-EM Performance Assessment Community of Practice Print Close 3 Cementitious Engineered...

66

Microsoft Word - m460.2-1aFinal6-4-08.doc  

Office of Legacy Management (LM)

transuranic (TRU) waste, low level waste (LLW), etc.. For some topics, such as emergency notification, a common approach can be applied to all modes and material types so...

67

www.eia.gov  

U.S. Energy Information Administration (EIA)

Wood Waste Liquids WDL Source: 1 (including footnote 16 within source) Wood Waste Solids WDS Waste Oil WO Source: 2, Table 1.11-2 ... Internal Combustion Engine Notes:

68

Application Programming Interface Documentation - Qb - U.S. Energy ...  

U.S. Energy Information Administration (EIA)

SERIES NAME: MMBTU per Unit : International Paper Courtland Mill : Wood/Wood Waste Solids : All Primemovers : Quarterly SERIES ID: ELEC.PLANT.AVG_HEAT.50245-WDS-ALL.Q

69

Proceedings: 1997 EPRI International Low-Level Waste Conference  

Science Conference Proceedings (OSTI)

Due to the changing business environment, U.S. utilities are evaluating methods to improve operations while minimizing costs. EPRI's sixth annual International Low-Level Waste (LLW) Conference featured 55 papers on a variety of topics. The majority of papers presented new or optimized technology and plant enhancements to reduce cost and improve LLW management.

1999-05-27T23:59:59.000Z

70

Proceedings: 1995 EPRI International Low-Level Waste Conference  

Science Conference Proceedings (OSTI)

EPRI's fourth annual International Low-Level Waste (LLW) Conference featured 72 papers on a variety of topics. Some of the subjects included were interim storage experiences; liquid, wet, and DAW improved processing and technology; mixed waste; decontamination; and building public trust. In addition, a nuclear industry and EPRI LLW projects update was presented.

1995-12-05T23:59:59.000Z

71

Comparison of low-level waste disposal programs of DOE and selected international countries  

SciTech Connect

The purpose of this report is to examine and compare the approaches and practices of selected countries for disposal of low-level radioactive waste (LLW) with those of the US Department of Energy (DOE). The report addresses the programs for disposing of wastes into engineered LLW disposal facilities and is not intended to address in-situ options and practices associated with environmental restoration activities or the management of mill tailings and mixed LLW. The countries chosen for comparison are France, Sweden, Canada, and the United Kingdom. The countries were selected as typical examples of the LLW programs which have evolved under differing technical constraints, regulatory requirements, and political/social systems. France was the first country to demonstrate use of engineered structure-type disposal facilities. The UK has been actively disposing of LLW since 1959. Sweden has been disposing of LLW since 1983 in an intermediate-depth disposal facility rather than a near-surface disposal facility. To date, Canada has been storing its LLW but will soon begin operation of Canada`s first demonstration LLW disposal facility.

Meagher, B.G. [Lockheed Idaho Technologies Co., Idaho Falls, ID (United States); Cole, L.T. [Cole and Associates (United States)

1996-06-01T23:59:59.000Z

72

Proceedings: 2004 EPRI International Low-Level Waste Conference and Exhibit Show  

Science Conference Proceedings (OSTI)

Nuclear utilities are continually evaluating methods to improve operations and minimize cost. EPRI's thirteenth annual International Low Level Waste (LLW) Conference -- coupled with the 25th annual ASME/EPRI Radwaste Workshop -- offered valuable insights into this effort by presenting papers covering new or improved technology developed worldwide for LLW management, processing, shipment, disposal, and regulation.

2005-06-14T23:59:59.000Z

73

Nevada Test Site Waste Acceptance Criteria (NTSWAC)  

SciTech Connect

This document establishes the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, Nevada Test Site Waste Acceptance Criteria (NTSWAC). The NTSWAC provides the requirements, terms, and conditions under which the Nevada Test Site will accept low-level radioactive (LLW) and LLW Mixed Waste (MW) for disposal.

NNSA /NSO Waste Management Project

2008-06-01T23:59:59.000Z

74

Amended Record of Decision for the Department of Energy's Final Programmatic Environmental Impact Statement for Accomplishing Expanded Civilian Nuclear Energy Research and Development and Isotope Production Missions in the U.S. (DOE/EIS-0310) (08/13/04)  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

0 0 Federal Register / Vol. 69, No. 156 / Friday, August 13, 2004 / Notices (LLW), mixed low-level waste (MLLW), Transuranic (TRU) waste, and immobilized low activity waste to support clean up at Hanford and to assist other DOE sites in completing their cleanup programs. DOE decided in the ROD to (1) limit the volumes of LLW and MLLW received at Hanford from other sites for disposal; (2) dispose of LLW in lined disposal facilities, a practice already used for MLLW; (3) construct and operate a lined, combined-use disposal facility (previously referenced in this Notice of Intent as the ''Integrated Disposal Facility'') in Hanford's 200 East Area for disposal of LLW and MLLW, and further limit offsite waste receipts until the IDF is constructed; (4) treat LLW and MLLW

75

Disposal of low-level and mixed low-level radioactive waste during 1990  

Science Conference Proceedings (OSTI)

Isotopic inventories and other data are presented for low-level radioactive waste (LLW) and mixed LLW disposed (and occasionally stored) during calendar year 1990 at commercial disposal facilities and Department of Energy (DOE) sites. Detailed isotopic information is presented for the three commercial disposal facilities located near Barnwell, SC, Richland, WA, and Beatty, NV. Less information is presented for the Envirocare disposal facility located near Clive, UT, and for LLW stored during 1990 at the West Valley site. DOE disposal information is included for the Savannah River Site (including the saltstone facility), Nevada Test Site, Los Alamos National Laboratory, Idaho National Engineering Laboratory, Hanford Site, Y-12 Site, and Oak Ridge National Laboratory. Summary information is presented about stored DOE LLW. Suggestions are made about improving LLW disposal data.

Not Available

1993-08-01T23:59:59.000Z

76

Supplemental information related to risk assessment for the off-site transportation of low-level waste for the U.S. Department of Energy waste management programmatic environmental impact statement  

Science Conference Proceedings (OSTI)

This report presents supplemental information to support the human health risk assessment conducted for the transportation of low-level waste (LLW) in support of the US Department of Energy Waste Management Programmatic Environmental Impact Statement (WM PEIS). Detailed descriptions of the transportation health risk assessment method and results of the assessment are presented in Appendix E of the WM PEIS and are not repeated in this report. This report presents additional information that is not presented in Appendix E but that was needed to conduct the transportation risk assessment for Waste Management (WM) LLW. Included are definition of the LLW alternatives considered in the WM PEIS, data related to the inventory and to the physical and radiological characteristics of WM LLW, an overview of the risk assessment method, and detailed results of the assessment for each WM LLW alternative considered.

Monette, F.A.; Biwer, B.M.; LePoire, D.J.; Chen, S.Y. [Argonne National Lab., IL (United States). Environmental Assessment Div.

1996-12-01T23:59:59.000Z

77

Remote-Handled Low-Level Waste Disposal Project Code of Record  

Science Conference Proceedings (OSTI)

The Remote-Handled Low-Level Waste (LLW) Disposal Project addresses an anticipated shortfall in remote-handled LLW disposal capability following cessation of operations at the existing facility, which will continue until it is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). Development of a new onsite disposal facility, the highest ranked alternative, will provide necessary remote-handled LLW disposal capability and will ensure continuity of operations that generate remote-handled LLW. This report documents the Code of Record for design of a new LLW disposal capability. The report is owned by the Design Authority, who can authorize revisions and exceptions. This report will be retained for the lifetime of the facility.

S.L. Austad, P.E.; L.E. Guillen, P.E.; C. W. McKnight, P.E.; D. S. Ferguson, P.E.

2011-04-01T23:59:59.000Z

78

Remote-Handled Low-Level Waste Disposal Project Code of Record  

Science Conference Proceedings (OSTI)

The Remote-Handled Low-Level Waste (LLW) Disposal Project addresses an anticipated shortfall in remote-handled LLW disposal capability following cessation of operations at the existing facility, which will continue until it is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). Development of a new onsite disposal facility will provide necessary remote-handled LLW disposal capability and will ensure continuity of operations that generate remote-handled LLW. This report documents the Code of Record for design of a new LLW disposal capability. The report is owned by the Design Authority, who can authorize revisions and exceptions. This report will be retained for the lifetime of the facility.

S.L. Austad, P.E.; L.E. Guillen, P.E.; C. W. McKnight, P.E.; D. S. Ferguson, P.E.

2012-06-01T23:59:59.000Z

79

Remote-Handled Low-Level Waste Disposal Project Code of Record  

Science Conference Proceedings (OSTI)

The Remote-Handled Low-Level Waste (LLW) Disposal Project addresses an anticipated shortfall in remote-handled LLW disposal capability following cessation of operations at the existing facility, which will continue until it is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). Development of a new onsite disposal facility, the highest ranked alternative, will provide necessary remote-handled LLW disposal capability and will ensure continuity of operations that generate remote-handled LLW. This report documents the Code of Record for design of a new LLW disposal capability. The report is owned by the Design Authority, who can authorize revisions and exceptions. This report will be retained for the lifetime of the facility.

S.L. Austad, P.E.; L.E. Guillen, P.E.; C. W. McKnight, P.E.; D. S. Ferguson, P.E.

2011-01-01T23:59:59.000Z

80

Remote-Handled Low-Level Waste Disposal Project Code of Record  

Science Conference Proceedings (OSTI)

The Remote-Handled Low-Level Waste (LLW) Disposal Project addresses an anticipated shortfall in remote-handled LLW disposal capability following cessation of operations at the existing facility, which will continue until it is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). Development of a new onsite disposal facility will provide necessary remote-handled LLW disposal capability and will ensure continuity of operations that generate remote-handled LLW. This report documents the Code of Record for design of a new LLW disposal capability. The report is owned by the Design Authority, who can authorize revisions and exceptions. This report will be retained for the lifetime of the facility.

S.L. Austad, P.E.; L.E. Guillen, P.E.; C. W. McKnight, P.E.; D. S. Ferguson, P.E.

2012-04-01T23:59:59.000Z

Note: This page contains sample records for the topic "non-hlw wds llw" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


81

Seagate Crystal Reports - RADCM  

Office of Environmental Management (EM)

Jersey Jersey SITE: Princeton PROGRAM: SC WASTE TYPE: Low Level Waste OPERATIONS OFFICE: Chicago Operations Office % of Stream Princeton - Low Level Waste - Compactable LLW WASTE STREAM CODE: 00492 STREAM NAME:Com pactable LLW MPC NAME:Solids TOTAL CURIES: Approved Volume : Future Volume Avg: Future Volume Lower Limit: Future Volume Upper Limit: 100.000 Compactable LLW Isotopes Cobalt-60 Avg Concentration: Low Limit Concent:5.0000E-003 Ci/m3 Upper Limit Concent:5.0000E-003 Ci/m3 Hydrogen-3 Avg Concentration: Low Limit Concent:5.0040E-003 Ci/m3 Upper Limit Concent:1.0000E+001 Ci/m3 % of Stream Princeton - Low Level Waste - Non-Compactable LLW WASTE STREAM CODE: 00493 STREAM NAME:Non-Compactable LLW MPC NAME:Solids TOTAL CURIES: Approved Volume : Future Volume Avg: Future Volume Lower Limit:

82

Life-Cycle Cost and Risk Analysis of Alternative Configurations for Shipping Low-Level Radioactive Waste to the Nevada Test Site  

SciTech Connect

The Nevada Test Site (NTS) is a major receiver of low-level radioactive waste (LLW) for disposal. Currently, all LLW received at NTS is shipped by truck. The trucks use highway routes to NTS that pass through the Las Vegas Valley and over Hoover Dam, which is a concern of local stakeholder groups in the State of Nevada. Rail service offers the opportunity to reduce transportation risks and costs, according to the Waste Management Programmatic Environmental Impact Statement (WM-PEIS). However, NTS and some DOE LLW generator sites are not served with direct rail service so intermodal transport is under consideration. Intermodal transport involves transport via two modes, in this case truck and rail, from the generator sites to NTS. LLW shipping containers would be transferred between trucks and railcars at intermodal transfer points near the LLW generator sites, NTS, or both. An Environmental Assessment (EA)for Intermodal Transportation of Low-Level Radioactive Waste to the Nevada Test Site (referred to as the NTSIntermodal -M) has been prepared to determine whether there are environmental impacts to alterations to the current truck routing or use of intermodal facilities within the State of Nevada. However, an analysis of the potential impacts outside the State of Nevada are not addressed in the NTS Intermodal EA. This study examines the rest of the transportation network between LLW generator sites and the NTS and evaluates the costs, risks, and feasibility of integrating intermodal shipments into the LLW transportation system. This study evaluates alternative transportation system configurations for NTS approved and potential generators based on complex-wide LLW load information. Technical judgments relative to the availability of DOE LLW generators to ship from their sites by rail were developed. Public and worker risk and life-cycle cost components are quantified. The study identifies and evaluates alternative scenarios that increase the use of rail (intermodal where needed) to transport LLW from generator sites to NTS.

PM Daling; SB Ross; BM Biwer

1999-12-17T23:59:59.000Z

83

Methods for verifying compliance with low-level radioactive waste acceptance criteria  

Science Conference Proceedings (OSTI)

This report summarizes the methods that are currently employed and those that can be used to verify compliance with low-level radioactive waste (LLW) disposal facility waste acceptance criteria (WAC). This report presents the applicable regulations representing the Federal, State, and site-specific criteria for accepting LLW. Typical LLW generators are summarized, along with descriptions of their waste streams and final waste forms. General procedures and methods used by the LLW generators to verify compliance with the disposal facility WAC are presented. The report was written to provide an understanding of how a regulator could verify compliance with a LLW disposal facility`s WAC. A comprehensive study of the methodology used to verify waste generator compliance with the disposal facility WAC is presented in this report. The study involved compiling the relevant regulations to define the WAC, reviewing regulatory agency inspection programs, and summarizing waste verification technology and equipment. The results of the study indicate that waste generators conduct verification programs that include packaging, classification, characterization, and stabilization elements. The current LLW disposal facilities perform waste verification steps on incoming shipments. A model inspection and verification program, which includes an emphasis on the generator`s waste application documentation of their waste verification program, is recommended. The disposal facility verification procedures primarily involve the use of portable radiological survey instrumentation. The actual verification of generator compliance to the LLW disposal facility WAC is performed through a combination of incoming shipment checks and generator site audits.

NONE

1993-09-01T23:59:59.000Z

84

Preliminary Hazard Analysis for the Remote-Handled Low-Level Waste Disposal Project  

Science Conference Proceedings (OSTI)

The need for remote handled low level waste (LLW) disposal capability has been identified. A new onsite, remote-handled LLW disposal facility has been identified as the highest ranked alternative for providing continued, uninterrupted remote-handled LLW disposal capability for remote-handled LLW that is generated as part of the nuclear mission of the Idaho National Laboratory and from spent nuclear fuel processing activities at the Naval Reactors Facility. Historically, this type of waste has been disposed of at the Radioactive Waste Management Complex. Disposal of remote-handled LLW in concrete disposal vaults at the Radioactive Waste Management Complex will continue until the facility is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). This document supports the conceptual design for the proposed remote-handled LLW disposal facility by providing an initial nuclear facility hazard categorization and by identifying potential hazards for processes associated with onsite handling and disposal of remote-handled LLW.

Lisa Harvego; Mike Lehto

2010-10-01T23:59:59.000Z

85

Preliminary Hazard Analysis for the Remote-Handled Low-Level Waste Disposal Facility  

Science Conference Proceedings (OSTI)

The need for remote handled low level waste (LLW) disposal capability has been identified. A new onsite, remote-handled LLW disposal facility has been identified as the highest ranked alternative for providing continued, uninterrupted remote-handled LLW disposal capability for remote-handled LLW that is generated as part of the nuclear mission of the Idaho National Laboratory and from spent nuclear fuel processing activities at the Naval Reactors Facility. Historically, this type of waste has been disposed of at the Radioactive Waste Management Complex. Disposal of remote-handled LLW in concrete disposal vaults at the Radioactive Waste Management Complex will continue until the facility is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). This document supports the conceptual design for the proposed remote-handled LLW disposal facility by providing an initial nuclear facility hazard categorization and by identifying potential hazards for processes associated with onsite handling and disposal of remote-handled LLW.

Lisa Harvego; Mike Lehto

2010-05-01T23:59:59.000Z

86

Preliminary Hazard Analysis for the Remote-Handled Low-Level Waste Disposal Facility  

Science Conference Proceedings (OSTI)

The need for remote handled low level waste (LLW) disposal capability has been identified. A new onsite, remote-handled LLW disposal facility has been identified as the highest ranked alternative for providing continued, uninterrupted remote-handled LLW disposal capability for remote-handled LLW that is generated as part of the nuclear mission of the Idaho National Laboratory and from spent nuclear fuel processing activities at the Naval Reactors Facility. Historically, this type of waste has been disposed of at the Radioactive Waste Management Complex. Disposal of remote-handled LLW in concrete disposal vaults at the Radioactive Waste Management Complex will continue until the facility is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). This document supports the conceptual design for the proposed remote-handled LLW disposal facility by providing an initial nuclear facility hazard categorization and by identifying potential hazards for processes associated with onsite handling and disposal of remote-handled LLW.

Lisa Harvego; Mike Lehto

2010-02-01T23:59:59.000Z

87

ORBITAL EVOLUTION OF COMPACT WHITE DWARF BINARIES  

SciTech Connect

The newfound prevalence of extremely low mass (ELM, M{sub He} < 0.2 M{sub Sun }) helium white dwarfs (WDs) in tight binaries with more massive WDs has raised our interest in understanding the nature of their mass transfer. Possessing small (M{sub env} {approx} 10{sup -3} M{sub Sun }) but thick hydrogen envelopes, these objects have larger radii than cold WDs and so initiate mass transfer of H-rich material at orbital periods of 6-10 minutes. Building on the original work of D'Antona et al., we confirm the 10{sup 6} yr period of continued inspiral with mass transfer of H-rich matter and highlight the fact that the inspiraling direct-impact double WD binary HM Cancri likely has an ELM WD donor. The ELM WDs have less of a radius expansion under mass loss, thus enabling a larger range of donor masses that can stably transfer matter and become a He mass transferring AM CVn binary. Even once in the long-lived AM CVn mass transferring stage, these He WDs have larger radii due to their higher entropy from the prolonged H-burning stage.

Kaplan, David L. [Physics Department, University of Wisconsin-Milwaukee, Milwaukee, WI 53211 (United States); Bildsten, Lars [Kavli Institute for Theoretical Physics and Department of Physics, Kohn Hall, University of California, Santa Barbara, CA 93106 (United States); Steinfadt, Justin D. R., E-mail: kaplan@uwm.edu, E-mail: bildsten@kitp.ucsb.edu, E-mail: jdrsteinfadt@gmail.com [Department of Physics, Broida Hall, University of California, Santa Barbara, CA 93106 (United States)

2012-10-10T23:59:59.000Z

88

Melter system technology testing for Hanford Site low-level tankwaste vitrification  

Science Conference Proceedings (OSTI)

Following revisions to the Tri-Party Agreement for Hanford Site cleanup, which specified vitrification for Complete melter feasibility and system operability immobilization of the low-level waste (LLW) tests, select reference melter(s), and establish reference derived from retrieval and pretreatment of the radioactive LLW glass formulation that meets complete systems defense wastes stored in 177 underground tanks, commercial requirements (June 1996). Available melter technologies were tested during 1994 to 1995 as part of a multiphase program to select reference Submit conceptual design and initiate definitive design technologies for the new LLW vitrification mission.

Wilson, C.N.

1996-05-03T23:59:59.000Z

89

Guidance document for multi-facility recycle/reuse/free release of metals from radiological control areas  

SciTech Connect

Approximately 15% of the Low Level Waste (LLW) produced at Los Alamos consists of scrap metal equipment and materials. The majority of this material is produced by decommissioning and modification of existing facilities. To address this waste stream, Los Alamos has developed a scrap metal recycling program that is operated by the Environmental Stewardship Office to minimize the amount of LLW metal sent for LLW landfill disposal. Past practice has supported treating all waste metals generated within RCA`s as contaminated. Through the metal recycling project, ESO is encouraging the use of alternatives to LLW disposal. Diverting RSM from waste landfill, disposal protects the environment, reduces the cost of operation, and reduces the cost of maintenance and operation at landfill sites. Waste minimization efforts also results in a twofold economic reward: The RSM has a market value and decontamination reduces the volume and therefore the amount of the radioactive waste to be buried within landfills.

Gogol, S.; Starke, T.

1997-08-15T23:59:59.000Z

90

EIS-0243: Record of Decision | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

of Energy's Waste Management Program: Treatment and Disposal of Low-Level Waste and Mixed Low-Level Waste For the management of low- level waste (LLW) analyzed in the Final...

91

Microsoft PowerPoint - DOE-PA-Wrkshp_Richland_WA Apr_2010-ASR...  

NLE Websites -- All DOE Office Websites (Extended Search)

of waste in unlined trenches in 1952 * Received TRU mixed hazardous waste from Rocky Flats * LLW-only disposal began in 1984 in pits 17-20 and disposal of remote handled...

92

Summary report. Low-level radioactive waste management activities in the states and compacts. Volume 4, No. 2  

Science Conference Proceedings (OSTI)

`Low-Level Radioactive Waste Management Activities in the States and Compacts` is a supplement to `LLW Notes` and is distributed periodically by Afton Associates, Inc. to state, compact and federal officials that receive `LLW Notes`. The Low-Level Radioactive Waste Forum (LLW Forum) is an association of state and compact representatives, appointed by governors and compact commissions, established to facilitate state and compact implementation of the Low- Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The LLW Forum provides an opportunity for state and compact officials to share information with one another and to exchange views with officials of federal agencies and other interested parties.

NONE

1996-08-01T23:59:59.000Z

93

Summary report, low-level radioactive waste management activities in the states and compacts. Vol. 4. No. 1  

Science Conference Proceedings (OSTI)

`Low-Level Radioactive Waste Management Activities in the States and Compacts` is a supplement to `LLW Notes` and is distributed periodically by Afton Associates, Inc. to state, compact and federal officials that receive `LLW Notes`. The Low-Level Radioactive Waste Forum (LLW Forum) is an association of state and compact representatives, appointed by governors and compact commissions, established to facilitate state and compact implementation of the Low- Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The LLW Forum provides an opportunity for state and compact officials to share information with one another and to exchange views with officials of federal agencies and other interested parties.

NONE

1996-01-01T23:59:59.000Z

94

Potential co-disposal of greater-than-class C low-level radioactive waste with Department of Energy special case waste - greater-than-class C low-level waste management program  

Science Conference Proceedings (OSTI)

This document evaluates the feasibility of co-disposing of greater-than-Class C low-level radioactive waste (GTCC LLW) with U.S. Department of Energy (DOE) special case waste (SCW). This document: (1) Discusses and evaluates key issues concerning co-disposal of GTCC LLW with SCW. This includes examining these issues in terms of regulatory concerns, technical feasibility, and economics; (2) Examines advantages and disadvantages of such co-disposal; and (3) Makes recommendations. Research and analysis of the issues presented in this report indicate that it would be technically and economically feasible to co-dispose of GTCC LLW with DOE SCW. However, a dilemma will likely arise in the current division of regulatory responsibilities between the U.S. Nuclear Regulatory Commission and DOE (i.e., current requirement for disposal of GTCC LLW in a facility licensed by the Nuclear Regulatory Commission). DOE SCW is currently not subject to this licensing requirement.

Allred, W.E.

1994-09-01T23:59:59.000Z

95

Microsoft Word - EM SSAB Chairs Meeting Oct 2012 Minutes_2_14...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

section 435.1enables EM to classify some equipment and wastes used or produced in HLW treatment programs as LLW or transuranic waste-based on its actual characteristics, not...

96

Carbon - 14 In Low-Level Waste  

Science Conference Proceedings (OSTI)

This report describes EPRI's collective efforts to understand and model the behavior of long-lived radionuclide Carbon-14 ((14)C) in low-level waste (LLW) disposal facilities.

1999-09-22T23:59:59.000Z

97

Portsmouth DUF6 Conversion Final EIS - Appendix F: Assessment...  

NLE Websites -- All DOE Office Websites (Extended Search)

6 Conversion EIS a Material Origin Destination Depleted U 3 O 8 Portsmouth Envirocare, NTS LLW, empty cylinders Portsmouth Envirocare, NTS CaF 2 Portsmouth Envirocare, NTS HF...

98

Issue briefs on low-level radioactive wastes  

Science Conference Proceedings (OSTI)

This report contains 4 Issue Briefs on low-level radioactive wastes. They are entitled: Handling, Packaging, and Transportation, Economics of LLW Management, Public Participation and Siting, and Low Level Waste Management.

Not Available

1981-01-01T23:59:59.000Z

99

Southern California Edison's Evaluation of California Energy Commission  

E-Print Network (OSTI)

of Evacuation Plan for the Public...................................18 b) Overview of Evacuation Plan for Non-Essential. Overview of Plan for Plant Access for Essential Plant Workers...............................................................30 3. Transportation of LLW to Licensed Disposal Facilities.............................32 4

100

FAQ 39-What are the potential environmental impacts from conversion...  

NLE Websites -- All DOE Office Websites (Extended Search)

nonhazardous solid waste, or whether disposal as LLW would be required. The low level of uranium contamination expected for CaF2 (i.e., less than 1 ppm) suggests that sale or...

Note: This page contains sample records for the topic "non-hlw wds llw" from the National Library of EnergyBeta (NLEBeta).
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they are not comprehensive nor are they the most current set.
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to obtain the most current and comprehensive results.


101

Breakout Session EM 3  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Level Radioactive Waste Level Radioactive Waste Disposition Activities Update Transportation External Coordination Working Group Douglas Tonkay Office of Disposal Operations February 7, 2008 Discussion Topics * DOE Low-Level/Mixed Low-Level Waste Corporate Board (LLW Corporate Board) * Greater-than-class C low-level radioactive waste (GTCC LLW) Disposition * DOE radioactive waste and materials disposition data - Waste Information Management System (WIMS) DOE LLW Corporate Board * Uses a commercial business model to more effectively manage DOE LLW and MLLW activities - Based on Transuranic Waste Corporate Board - Promotes efficient and cost-effective treatment and disposal alternatives and use of DOE regional disposal facilities - Identifies and addresses complex-wide issues, coordinate operations

102

Page not found | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

River Site (SRS) has placed an operational stormwater runoff cover over the 625,000-square-foot area comprising E-Area Low-Level Waste (LLW) Facility Slit Trench Disposal...

103

SPITZER 24 {mu}m SURVEY FOR DUST DISKS AROUND HOT WHITE DWARFS  

Science Conference Proceedings (OSTI)

Two types of dust disks around white dwarfs (WDs) have been reported: small dust disks around cool metal-rich WDs consisting of tidally disrupted asteroids and a large dust disk around the hot central WD of the Helix planetary nebula (PN) possibly produced by collisions among Kuiper-Belt-like objects. To search for more dust disks of the latter type, we have conducted a Spitzer MIPS 24 {mu}m survey of 71 hot WDs or pre-WDs, among which 35 are central stars of PNe (CSPNs). Nine of these evolved stars are detected and their 24 {mu}m flux densities are at least two orders of magnitude higher than their expected photospheric emission. Considering the bias against the detection of distant objects, the 24 {mu}m detection rate for the sample is {approx}>15%. It is striking that seven, or {approx}20%, of the WD and pre-WDs in known PNe exhibit 24 {mu}m excesses, while two, or 5%-6%, of the WDs not in PNe show 24 {mu}m excesses and they have the lowest 24 {mu}m flux densities. We have obtained follow-up Spitzer Infrared Spectrograph spectra for five objects. Four show clear continuum emission at 24 {mu}m, and one is overwhelmed by a bright neighboring star but still shows a hint of continuum emission. In the cases of WD 0950+139 and CSPN K 1-22, a late-type companion is present, making it difficult to determine whether the excess 24 {mu}m emission is associated with the WD or its red companion. High-resolution images in the mid-infrared are needed to establish unambiguously the stars responsible for the 24 {mu}m excesses.

Chu, You-Hua; Bilikova, Jana; Gruendl, Robert A. [Department of Astronomy, University of Illinois at Urbana-Champaign, Urbana, IL 61801 (United States); Su, Kate Y. L. [Stewart Observatory, University of Arizona, Tucson, AZ 85721 (United States); De Marco, Orsola [Department of Physics and Astronomy, Macquarie University, Sydney, NSW 2109 (Australia); Guerrero, Martin A. [Instituto de Astrofisica de Andalucia, CSIC, E-18008 Granada (Spain); Updike, Adria C. [CRESST and the Observational Cosmology Laboratory, NASA/GSFC, Greenbelt, MD 20771 (United States); Volk, Kevin [Space Telescope Science Institute, Baltimore, MD 21218 (United States); Rauch, Thomas, E-mail: yhchu@illinois.edu [Institut fuer Astronomie und Astrophysik Tuebingen (IAAT), Abteilung Astronomie, D-72076 Tuebingen (Germany)

2011-09-15T23:59:59.000Z

104

Waste Logic: FT 2.0: Waste Logic: FastTrack Version 2.0 with Data Link  

Science Conference Proceedings (OSTI)

Tracking and trending liquid processing performance data is critical for utility low-level waste (LLW) managers to sufficiently recognize good performance of their liquid processing systems and identify areas for improvement. In response to this challenge, EPRI's LLW group developed FastTrack. EPRI's Waste Logic: FastTrack Version 2.0 with Data Link software for Microsoft Windows-based PC computers is a custom database software application that provides storage, retrieval, analysis, graphing, repo...

2004-10-25T23:59:59.000Z

105

Proceedings: 1996 EPRI International Low Level Waste Conference  

Science Conference Proceedings (OSTI)

Due to the changing business environment, U.S. utilities are evaluating methods to improve operations while minimizing costs. EPRI's fifth annual International Low Level Waste (LLW) Conference featured 65 papers on a variety of topics. More than a third of the papers emphasized liquid-wet waste processing enhancements, new or improved technologies, and LLW program cost reduction. Other subjects included dry active waste processing cost reduction, the new DOT/NRC transport regulations, mixed waste, vitrif...

1996-12-06T23:59:59.000Z

106

Idaho Chemical Processing Plant low-level waste grout stabilization development program FY-96 status report  

Science Conference Proceedings (OSTI)

The general purpose of the Grout Stabilization Development Program is to solidify and stabilize the liquid low-level wastes (LLW) generated at the Idaho Chemical Processing Plant (ICPP). It is anticipated that LLW will be produced from the following: (1) chemical separation of the tank farm high-activity sodium-bearing waste; (2) retrieval, dissolution, and chemical separation of the aluminum, zirconium, and sodium calcines; (3) facility decontamination processes; and (4) process equipment waste. The main tasks completed this fiscal year as part of the program were chromium stabilization study for sodium-bearing waste and stabilization and solidification of LLW from aluminum and zirconium calcines. The projected LLW will be highly acidic and contain high amounts of nitrates. Both of these are detrimental to Portland cement chemistry; thus, methods to precondition the LLW and to cure the grout were explored. A thermal calcination process, called denitration, was developed to solidify the waste and destroy the nitrates. A three-way blend of Portland cement, blast furnace slag, and fly ash was successfully tested. Grout cubes were prepared at various waste loadings to maximize loading while meeting compressive strength and leach resistance requirements. For the sodium LLW, a 25% waste loading achieves a volume reduction of 3.5 and a compressive strength of 2,500 pounds per square inch while meeting leach, mix, and flow requirements. It was found that the sulfur in the slag reduces the chromium leach rate below regulatory limits. For the aluminum LLW, a 15% waste loading achieves a volume reduction of 8.5 and a compressive strength of 4,350 pounds per square inch while meeting leach requirements. Likewise for zirconium LLW, a 30% waste loading achieves a volume reduction of 8.3 and a compressive strength of 3,570 pounds per square inch.

Herbst, A.K.

1996-09-01T23:59:59.000Z

107

Disposal Cost Savings Considerations in Curie Reduction Programs  

Science Conference Proceedings (OSTI)

In 1996, the Low Level Radioactive Waste (LLW) Disposal Facility in Barnwell, South Carolina, announced a new fee structure for the disposal of radioactive wastes based on waste density, dose rate, and activity (curies). This report provides a detailed discussion of the current Barnwell Disposal Fee Structure along with its cost impact on various types of wastes generated. The report also evaluates various curie reduction options, their practical application, and their cost savings potential to help LLW ...

1998-03-30T23:59:59.000Z

108

Proceedings: 2006 EPRI International Low Level Waste Conference and Exhibit Show  

Science Conference Proceedings (OSTI)

Nuclear utilities are continually evaluating methods to improve operations and minimize cost. EPRI's 15th Annual International Low Level Waste (LLW) Conferencecoupled with the 27th Annual ASME/EPRI Radwaste Workshopoffered valuable insight into this effort by presenting papers covering new or improved technology developed worldwide for LLW management, processing, shipment, disposal and regulation. Attendees from several foreign countries, including Korea, the United Kingdom, Canada and Sweden, presented ...

2007-05-15T23:59:59.000Z

109

Guidelines for Operating an Interim On Site Low Level Radioactive Waste Storage Facility - Revision 1  

Science Conference Proceedings (OSTI)

The majority of commercial USA nuclear stations have constructed on-site LLW storage facilities, and most of these same utilities are experiencing or have experienced at least one period of interim on-site storage. These Guidelines focus on operational considerations and incorporate many of the lessons learned while operating various types of LLW storage facilities. This document was reviewed by the USNRC. Subsequently, the USNRC issued RIS 2008-32, Interim LLRW Storage at NPPs, which recognizes the meth...

2009-02-23T23:59:59.000Z

110

Interim On-Site Storage of Low-Level Waste: Volume 4, Part 3: Waste Container Closures, Seals, and Gas Vents  

Science Conference Proceedings (OSTI)

This volume of the Interim On-Site Storage report series supplements Volume 4, Part 1, which includes an extensive methodology and detailed information on the types and availability of low-level waste (LLW) containers and container coatings for extended storage. Part 2, soon to be published, addresses monitoring and inspection requirements for stored LLW containers. Part 3 continues the series by providing detailed guidance on container closures, seals, and gas vents, including performance goals and key ...

1993-11-11T23:59:59.000Z

111

Evaluation of Exothermic Reactions from Bulk-Vitrification Melter Feeds Containing Cellulose  

SciTech Connect

PNNL has demonstrated that cellulose effectively reduces the amount of molten ionic salt during Bulk Vitrification of simulated Hanford Low Level Waste (LLW). To address concerns about the potential reactivity of cellulose-LLW, PNNL used thermogravimetric analysis, differential thermal analysis, and accelerating rate calorimetry to determine in these preliminary studies that these mixtures will support a self-sustaining reaction if heated to 110C at adiabatic conditions. Additional testing is recommended.

Scheele, Randall D.; McNamara, Bruce K.; Bagaasen, Larry M.; Bos, Stanley J.; Kozelisky, Anne E.; Berry, Pam

2007-06-25T23:59:59.000Z

112

Proceedings: 2008 EPRI International Low-Level Waste Conference and Exhibit Show  

Science Conference Proceedings (OSTI)

Nuclear utilities are continually evaluating methods to improve operations, minimize cost and find alternatives for disposal of NRC Class A, B & C waste. EPRI's 17th Annual International Low Level Waste (LLW) Conference - coupled with the 31st Annual ASME/EPRI Radwaste Workshop - offered valuable insights into this effort by presenting papers covering new or improved technology developed worldwide for LLW management, processing, shipment, disposal and regulation. Attendees from several foreign countries ...

2008-11-18T23:59:59.000Z

113

Review and Demonstration of Korea Hydro & Nuclear Power (KHNP) Vitrification Technology for Low Level Waste Treatment  

Science Conference Proceedings (OSTI)

Vitrification is the process of stabilizing nuclides in a glass matrix in order to enhance disposal options. A mature technology, vitrification has been applied to high level radioactive waste (HLW) for more than 40 years. As disposal costs and public concern for the environment increase, vitrification is considered to be a promising technology for low level waste (LLW) stabilization. This report covers the characteristics of LLW generated from nuclear power plants, current melter technologies ...

2013-08-14T23:59:59.000Z

114

Conceptual Safety Design Report for the Remote Handled Low-Level Waste Disposal Facility  

SciTech Connect

A new onsite, remote-handled LLW disposal facility has been identified as the highest ranked alternative for providing continued, uninterrupted remote-handled LLW disposal for remote-handled LLW from the Idaho National Laboratory and for spent nuclear fuel processing activities at the Naval Reactors Facility. Historically, this type of waste has been disposed of at the Radioactive Waste Management Complex. Disposal of remote-handled LLW in concrete disposal vaults at the Radioactive Waste Management Complex will continue until the facility is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). This conceptual safety design report supports the design of a proposed onsite remote-handled LLW disposal facility by providing an initial nuclear facility hazard categorization, by identifying potential hazards for processes associated with onsite handling and disposal of remote-handled LLW, by evaluating consequences of postulated accidents, and by discussing the need for safety features that will become part of the facility design.

Boyd D. Christensen

2010-05-01T23:59:59.000Z

115

Conceptual Safety Design Report for the Remote Handled Low-Level Waste Disposal Facility  

Science Conference Proceedings (OSTI)

A new onsite, remote-handled LLW disposal facility has been identified as the highest ranked alternative for providing continued, uninterrupted remote-handled LLW disposal for remote-handled LLW from the Idaho National Laboratory and for spent nuclear fuel processing activities at the Naval Reactors Facility. Historically, this type of waste has been disposed of at the Radioactive Waste Management Complex. Disposal of remote-handled LLW in concrete disposal vaults at the Radioactive Waste Management Complex will continue until the facility is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). This conceptual safety design report supports the design of a proposed onsite remote-handled LLW disposal facility by providing an initial nuclear facility hazard categorization, by identifying potential hazards for processes associated with onsite handling and disposal of remote-handled LLW, by evaluating consequences of postulated accidents, and by discussing the need for safety features that will become part of the facility design.

Boyd D. Christensen

2010-02-01T23:59:59.000Z

116

Automatic generation of water distribution systems based on GIS data  

Science Conference Proceedings (OSTI)

In the field of water distribution system (WDS) analysis, case study research is needed for testing or benchmarking optimisation strategies and newly developed software. However, data availability for the investigation of real cases is limited due to ... Keywords: Algorithmic network generation, GIS-data, Hydraulic simulation, Modular design system, Water distribution system

Robert Sitzenfrei, Michael MDerl, Wolfgang Rauch

2013-09-01T23:59:59.000Z

117

BWR Fuel Deposit Characterization  

Science Conference Proceedings (OSTI)

Because of the possible role of crud in accelerated cladding corrosion in BWRs, there is increased interest in the morphology and elemental distribution of crud on irradiated rods. This report describes the results of scanning electron spectroscopy with wavelength dispersive spectrometry (SEM/WDS) examinations of the crud morphology and elemental composition of three rods irradiated in LaSalle Unit 2.

2005-11-28T23:59:59.000Z

118

PULSATIONS IN HYDROGEN BURNING LOW-MASS HELIUM WHITE DWARFS  

SciTech Connect

Helium core white dwarfs (WDs) with mass M {approx}< 0.20 M {sub sun} undergo several Gyr of stable hydrogen burning as they evolve. We show that in a certain range of WD and hydrogen envelope masses, these WDs may exhibit g-mode pulsations similar to their passively cooling, more massive carbon/oxygen core counterparts, the ZZ Cetis. Our models with stably burning hydrogen envelopes on helium cores yield g-mode periods and period spacings longer than the canonical ZZ Cetis by nearly a factor of 2. We show that core composition and structure can be probed using seismology since the g-mode eigenfunctions predominantly reside in the helium core. Though we have not carried out a fully nonadiabatic stability analysis, the scaling of the thermal time in the convective zone with surface gravity highlights several low-mass helium WDs that should be observed in search of pulsations: NLTT 11748, SDSS J0822+2753, and the companion to PSR J1012+5307. Seismological studies of these He core WDs may prove especially fruitful, as their luminosity is related (via stable hydrogen burning) to the hydrogen envelope mass, which eliminates one model parameter.

Steinfadt, Justin D. R. [Department of Physics, Broida Hall, University of California, Santa Barbara, CA 93106 (United States); Bildsten, Lars [Kavli Institute for Theoretical Physics and Department of Physics, Kohn Hall, University of California, Santa Barbara, CA 93106 (United States); Arras, Phil, E-mail: jdrs@physics.ucsb.ed, E-mail: bildsten@kitp.ucsb.ed, E-mail: arras@virginia.ed [Department of Astronomy, University of Virginia, P.O. Box 400325, Charlottesville, VA 22904 (United States)

2010-07-20T23:59:59.000Z

119

Design and operational considerations of United States commercial near-surface low-level radioactive waste disposal facilities  

Science Conference Proceedings (OSTI)

In accordance with the Low-Level Radioactive Waste Policy Amendments Act of 1985, states are responsible for providing for disposal of commercially generated low-level radioactive waste (LLW) within their borders. LLW in the US is defined as all radioactive waste that is not classified as spent nuclear fuel, high-level radioactive waste, transuranic waste, or by-product material resulting from the extraction of uranium from ore. Commercial waste includes LLW generated by hospitals, universities, industry, pharmaceutical companies, and power utilities. LLW generated by the country`s defense operations is the responsibility of the Federal government and its agency, the Department of Energy. The commercial LLRW disposal sites discussed in this report are located near: Sheffield, Illinois (closed); Maxey Flats, Kentucky (closed); Beatty, Nevada (closed); West Valley, New York (closed); Barnwell, South Carolina (operating); Richland, Washington (operating); Ward Valley, California, (proposed); Sierra Blanca, Texas (proposed); Wake County, North Carolina (proposed); and Boyd County, Nebraska (proposed). While some comparisons between the sites described in this report are appropriate, this must be done with caution. In addition to differences in climate and geology between sites, LLW facilities in the past were not designed and operated to today`s standards. This report summarizes each site`s design and operational considerations for near-surface disposal of low-level radioactive waste. The report includes: a description of waste characteristics; design and operational features; post closure measures and plans; cost and duration of site characterization, construction, and operation; recent related R and D activities for LLW treatment and disposal; and the status of the LLW system in the US.

Birk, S.M.

1997-10-01T23:59:59.000Z

120

THE WIRED SURVEY. II. INFRARED EXCESSES IN THE SDSS DR7 WHITE DWARF CATALOG  

SciTech Connect

With the launch of the Wide-field Infrared Survey Explorer (WISE), a new era of detecting planetary debris and brown dwarfs (BDs) around white dwarfs (WDs) has begun with the WISE InfraRed Excesses around Degenerates (WIRED) Survey. The WIRED Survey is sensitive to substellar objects and dusty debris around WDs out to distances exceeding 100 pc, well beyond the completeness level of local WDs. In this paper, we present a cross-correlation of the preliminary Sloan Digital Sky Survey (SDSS) Data Release 7 (DR7) WD catalog between the WISE, Two-Micron All Sky Survey (2MASS), UKIRT Infrared Deep Sky Survey (UKIDSS), and SDSS DR7 photometric catalogs. From {approx}18,000 input targets, there are WISE detections comprising 344 'naked' WDs (detection of the WD photosphere only), 1020 candidate WD+M dwarf binaries, 42 candidate WD+BD systems, 52 candidate WD+dust disk systems, and 69 targets with indeterminate infrared excess. We classified all of the detected targets through spectral energy distribution model fitting of the merged optical, near-IR, and WISE photometry. Some of these detections could be the result of contaminating sources within the large ( Almost-Equal-To 6'') WISE point-spread function; we make a preliminary estimate for the rates of contamination for our WD+BD and WD+disk candidates and provide notes for each target of interest. Each candidate presented here should be confirmed with higher angular resolution infrared imaging or infrared spectroscopy. We also present an overview of the observational characteristics of the detected WDs in the WISE photometric bands, including the relative frequencies of candidate WD+M, WD+BD, and WD+disk systems.

Debes, John H.; Leisawitz, David T. [Goddard Space Flight Center, Greenbelt, MD 20771 (United States); Hoard, D. W. [Spitzer Science Center, California Institute of Technology, Pasadena, CA 91125 (United States); Wachter, Stefanie [Infrared Processing and Analysis Center, California Institute of Technology, Pasadena, CA 91125 (United States); Cohen, Martin [Monterey Institute for Research in Astronomy, Marina, CA 93933 (United States)

2011-12-01T23:59:59.000Z

Note: This page contains sample records for the topic "non-hlw wds llw" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


121

Microbial degradation of low-level radioactive waste. Volume 1, Annual report for FY 1993  

SciTech Connect

The Nuclear Regulatory Commission stipulates that disposed low-level radioactive waste (LLW) be stabilized. Because of apparent ease of use and normal structural integrity, cement has been widely used as a binder to solidify LLW. However, the resulting waste forms are sometimes susceptible to failure due to the actions of waste constituents, stress, and environment. This report reviews laboratory efforts that are being developed to address the effects of microbiologically influenced chemical attack on cement-solidified LLW. Groups of microorganisms are being employed that are capable of metabolically converting organic and inorganic substrates into organic and mineral acids. Such acids aggressively react with cement and can ultimately lead to structural failure. Results on the application of mechanisms inherent in microbially influenced degradation of cement-based material are the focus of this report. Sufficient data-validated evidence of the potential for microbially influenced deterioration of cement-solidified LLW has been developed during the course of this study. These data support the continued development of appropriate tests necessary to determine the resistance of cement-solidified LLW to microbially induced degradation that could impact the stability of the waste form. They also justify the continued effort of enumeration of the conditions necessary to support the microbiological growth and population expansion.

Rogers, R.D.; Hamilton, M.A.; Veeh, R.H.; McConnell, J.W. Jr.

1994-04-01T23:59:59.000Z

122

Metal recycling experience at Los Alamos National Laboratory. Reuse, release, and recycle of metals from radiological control areas``  

Science Conference Proceedings (OSTI)

Approximately 15% of the Low-Level Waste (LLW) produced at Los Alamos consists of scrap metal equipment and materials. The majority of this material is produced by decommissioning and the modification of existing facilities. To reduce this waste stream, Department of Energy Headquarters, EM-77 Office, sponsored the Reuse, Recycle, and Release of Metals from Radiological Control Areas High Return on Investment (ROI) Project to implement recycle, reuse, and release of scrap metal at the laboratory. The goal of this project was to develop cost effective alternatives to LLW disposal of scrap metal and to avoid the disposal of 2,400 m{sup 3} of scrap metal. The ROI for this project was estimated at 948%. The ROI project was funded in March 1996 and is scheduled for completion by October 1997. At completion, a total of 2,400 m{sup 3} of LLW avoidance will have been accomplished and a facility to continue recycling activities will be operational. This paper will present the approach used to develop effective alternatives for scrap metal at Los Alamos and then discuss the tasks identified in the approach in detail. Current scrap metal inventory, waste projections, alternatives to LLW disposal, regulatory guidance, and efforts to institutionalize the alternatives to LLW disposal will be discussed in detail.

Gogol, S.

1997-11-01T23:59:59.000Z

123

Gas generation from low-level radioactive waste: Concerns for disposal  

DOE Green Energy (OSTI)

The Advisory Committee on Nuclear Waste (ACNW) has urged the Nuclear Regulatory Commission (NRC) to reexamine the topic of hydrogen gas generation from low-level radioactive waste (LLW) in closed spaces to ensure that the slow buildup of hydrogen from water-bearing wastes in sealed containers does not become a problem for long-term safe disposal. Brookhaven National Laboratory (BNL) has prepared a report, summarized in this paper, for the NRC to respond to these concerns. The paper discusses the range of values for G(H{sub 2}) reported for materials of relevance to LLW disposal; most of these values are in the range of 0.1 to 0.6. Most studies of radiolytic hydrogen generation indicate a leveling off of pressurization, probably because of chemical kinetics involving, in many cases, the radiolysis of water within the waste. Even if no leveling off occurs, realistic gas leakage rates (indicating poor closure by gaskets on drums and liners) will result in adequate relief of pressure for radiolytic gas generation from the majority of commercial sector LLW packages. Biodegradative gas generation, however, could pose a pressurization hazard even at realistic gas leakage rates. Recommendations include passive vents on LLW containers (as already specified for high integrity containers) and upper limits to the G values and/or the specific activity of the LLW.

Siskind, B.

1992-01-01T23:59:59.000Z

124

Gas generation from low-level radioactive waste: Concerns for disposal  

DOE Green Energy (OSTI)

The Advisory Committee on Nuclear Waste (ACNW) has urged the Nuclear Regulatory Commission (NRC) to reexamine the topic of hydrogen gas generation from low-level radioactive waste (LLW) in closed spaces to ensure that the slow buildup of hydrogen from water-bearing wastes in sealed containers does not become a problem for long-term safe disposal. Brookhaven National Laboratory (BNL) has prepared a report, summarized in this paper, for the NRC to respond to these concerns. The paper discusses the range of values for G(H{sub 2}) reported for materials of relevance to LLW disposal; most of these values are in the range of 0.1 to 0.6. Most studies of radiolytic hydrogen generation indicate a leveling off of pressurization, probably because of chemical kinetics involving, in many cases, the radiolysis of water within the waste. Even if no leveling off occurs, realistic gas leakage rates (indicating poor closure by gaskets on drums and liners) will result in adequate relief of pressure for radiolytic gas generation from the majority of commercial sector LLW packages. Biodegradative gas generation, however, could pose a pressurization hazard even at realistic gas leakage rates. Recommendations include passive vents on LLW containers (as already specified for high integrity containers) and upper limits to the G values and/or the specific activity of the LLW.

Siskind, B.

1992-04-01T23:59:59.000Z

125

Radioactive waste management complex low-level waste radiological composite analysis  

Science Conference Proceedings (OSTI)

The composite analysis estimates the projected cumulative impacts to future members of the public from the disposal of low-level radioactive waste (LLW) at the Idaho National Engineering and Environmental Laboratory (INEEL) Radioactive Waste Management Complex (RWMC) and all other sources of radioactive contamination at the INEEL that could interact with the LLW disposal facility to affect the radiological dose. Based upon the composite analysis evaluation, waste buried in the Subsurface Disposal Area (SDA) at the RWMC is the only source at the INEEL that will significantly interact with the LLW facility. The source term used in the composite analysis consists of all historical SDA subsurface disposals of radionuclides as well as the authorized LLW subsurface disposal inventory and projected LLW subsurface disposal inventory. Exposure scenarios evaluated in the composite analysis include all the all-pathways and groundwater protection scenarios. The projected dose of 58 mrem/yr exceeds the composite analysis guidance dose constraint of 30 mrem/yr; therefore, an options analysis was conducted to determine the feasibility of reducing the projected annual dose. Three options for creating such a reduction were considered: (1) lowering infiltration of precipitation through the waste by providing a better cover, (2) maintaining control over the RWMC and portions of the INEEL indefinitely, and (3) extending the period of institutional control beyond the 100 years assumed in the composite analysis. Of the three options investigated, maintaining control over the RWMC and a small part of the present INEEL appears to be feasible and cost effective.

McCarthy, J.M.; Becker, B.H.; Magnuson, S.O.; Keck, K.N.; Honeycutt, T.K.

1998-05-01T23:59:59.000Z

126

Corrective Action Plan for INEL low-level waste management ES&H vulnerabilities  

SciTech Connect

Low-level waste (LLW) activities at INEL include numerous waste generators, storage facilities, three treatment facilities, and one disposal facility. The Working Group Assessment Team (WGAT) conducted an assessment of the LLW management program in response to the Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 94-2 (Conformance with Safety Standards at Department of Energy Low-Level Nuclear Waste and Disposal Facilities). Assessment included review of waste generators, liquid effluent treatment, storage facilities and practices, and a disposal facility with vaults and a shallow subsurface burial site. WGAT reviewed relevant documents and conducted tours concerning these LLW operations. The vulnerabilities identified by WGAT were similar to those self-identified by INEL (storage and disposal of LLW). This assessment resulted in the documentation of 8 vulnerabilities and 3 conditions. WGAT assessed the overall LLW/mixed low-level waste (MLLW) management program at INEL as being generally effective. As recommended by DNFSB, a site-specific Corrective Action Plan has been prepared and constitutes the initial site improvement activities.

1996-07-01T23:59:59.000Z

127

Waste Determination and Section 3116 of the 2005 National Defense Authorization Act - HQ Perspective  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Level Waste Corporate Board Level Waste Corporate Board Section 3116 A H d t P ti A Headquarters Perspective Martin J. Letourneau Chair, Low-Level Waste Disposal Facility Federal Review Group , p y p March 5, 2008 safety performance cleanup closure M E Environmental Management Environmental Management Section 3116 vs. DOE Order 435.1 * From a technical perspective, the criteria are essentially identical y * Both paths provide a methodology to treat and manage waste incidental to reprocessing as non-HLW * Section 3116 can only be applied in the states of South Carolina and Idaho * For consistency all future WIR Evaluations will be * For consistency, all future WIR Evaluations will be modeled after the Section 3116 process * One key difference is the regulatory responsibility of One key difference is the regulatory responsibility of

128

Environmental assessment for the construction, operation, and decommissioning of the Waste Segregation Facility at the Savannah River Site  

Science Conference Proceedings (OSTI)

This Environmental Assessment (EA) has been prepared by the Department of Energy (DOE) to assess the potential environmental impacts associated with the construction, operation and decontamination and decommissioning (D&D) of the Waste Segregation Facility (WSF) for the sorting, shredding, and compaction of low-level radioactive waste (LLW) at the Savannah River Site (SRS) located near Aiken, South Carolina. The LLW to be processed consists of two waste streams: legacy waste which is currently stored in E-Area Vaults of SRS and new waste generated from continuing operations. The proposed action is to construct, operate, and D&D a facility to process low-activity job-control and equipment waste for volume reduction. The LLW would be processed to make more efficient use of low-level waste disposal capacity (E-Area Vaults) or to meet the waste acceptance criteria for treatment at the Consolidated Incineration Facility (CIF) at SRS.

NONE

1998-01-01T23:59:59.000Z

129

Presentation Title  

NLE Websites -- All DOE Office Websites (Extended Search)

LLW Processing Update LLW Processing Update Aaron Staub Senior Engineer Waste Solidification Engineering Denver Technical Exchange May 19, 2009 LWO-WSE-2009-00135 Saltstone LLW Processing Update 2 Saltstone Facility: Background Commissioned in 1990 for waste treatment of site evaporator bottoms effluents and decontaminated salt solution from In-Tank Precipitation (ITP) processing. Original design allowed for significant contact maintenance, waste expected to have minimal radioactive source term. During 1990s and early 2000s, delays in salt processing eliminated much of the feed planned for Saltstone. Intermittent operations only to support evaporator effluents. By mid-2000s, Tank Farm space requirements create need to dispose of small volume of waste with higher Cs-137 levels than originally forecast.

130

NNSS Waste Disposal Proves Vital Resource for DOE Complex | Department of  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

NNSS Waste Disposal Proves Vital Resource for DOE Complex NNSS Waste Disposal Proves Vital Resource for DOE Complex NNSS Waste Disposal Proves Vital Resource for DOE Complex March 20, 2013 - 12:00pm Addthis The Area 5 Radioactive Waste Management Site The Area 5 Radioactive Waste Management Site Like most LLW, RTGs disposed of at the NNSS were handled without any special equipment or clothing because of the relatively low dose rate levels. Like most LLW, RTGs disposed of at the NNSS were handled without any special equipment or clothing because of the relatively low dose rate levels. An irradiator from Sandia National Laboratory was disposed of at the RWMS in September 2012. An irradiator from Sandia National Laboratory was disposed of at the RWMS in September 2012. The Area 5 Radioactive Waste Management Site Like most LLW, RTGs disposed of at the NNSS were handled without any special equipment or clothing because of the relatively low dose rate levels.

131

Manifest requirements. RCRA Information Brief  

Science Conference Proceedings (OSTI)

Specific pretransport regulatory requirements must be met by DOE prior to shipment of hazardous waste, low-level wastes (LLW), and radioactive mixed wastes (RMW). The pretransport requirements are intended to help reduce the risk of loss or leakage of, or exposure to, hazardous wastes, LLW, and RMW during shipment; and to communicate information on potential hazards to shippers, carriers, or receivers of waste shipments, and emergency response personnel in the event of an accident, spill, or leak. These goals are accomplished through tracking of shipments, correct packaging and labeling, and communication of potential hazards. Specific requirements include manifesting, packaging, marking and labeling of waste packages, placarding of vehicles, and selecting appropriate waste transporters and shipment destinations. This Information Brief focuses on the manifesting requirements associated with domestic transport of hazardous wastes, LLW, and RMW.

Not Available

1994-04-01T23:59:59.000Z

132

Thermal denitration and mineralization of waste constituents  

SciTech Connect

In order to produce a quality grout from LLW using hydraulic cements, proper conditioning of the waste is essential for complete cement curing. Several technologies were investigated as options for conditions. Since the LLW is dilute, removal of all, or most, of the water will significantly reduce the final waste volume. Neutralization of the LLW is also desirable since acidic liquids to not allow cement to cure properly. The nitrate compounds are very soluble and easily leached from solid waste forms; therefore, denitration is desirable. Thermal and chemical denitration technologies have the advantages of water removal, neutralization, and denitration. The inclusion of additives during thermal treatment were investigated as a method of forming insoluable waste conditions.

Nenni, J.A.; Boardman, R.D.

1997-08-01T23:59:59.000Z

133

Criticality safety considerations for low-level-waste facilities  

SciTech Connect

The nuclear criticality safety for handling and burial of certain special nuclear materials (SNM) at low-level-waste (LLW) facilities is licensed by the US Nuclear Regulatory Commission (NRC). Recently, Oak Ridge National Laboratory (ORNL) staff assisted the NRC Office of Nuclear Material Safety and Safeguards, Low-Level-Waste and Decommissioning Projects Branch, in developing technical specifications for the nuclear criticality safety of {sup 235}U and {sup 235}Pu in LLW facilities. This assistance resulted in a set of nuclear criticality safety criteria that can be uniformly applied to the review of LLW package burial facility license applications. These criteria were developed through the coupling of the historic surface-density criterion with current computational technique to establish safety criteria considering SNM material form and reflector influences. This paper presents a summary of the approach used to establish and to apply the criteria to the licensing review process.

Hopper, C.M.

1995-04-01T23:59:59.000Z

134

Exploratory study of complexant concentrate waste processing  

SciTech Connect

The purpose of this exploratory study, conducted by Pacific Northwest Laboratory for Westinghouse Hanford Company, was to determine the effect of applying advanced chemical separations technologies to the processing and disposal of high-level wastes (HLW) stored in underground tanks. The major goals of this study were to determine (1) if the wastes can be partitioned into a small volume of HLW plus a large volume of low-level waste (LLW), and (2) if the activity in the LLW can be lowered enough to meet NRC Class LLW criteria. This report presents the results obtained in a brief scouting study of various processes for separating radionuclides from Hanford complexant concentrate (CC) waste.

Lumetta, G.J.; Bray, L.A.; Kurath, D.E.; Morrey, J.R.; Swanson, J.L.; Wester, D.W.

1993-02-01T23:59:59.000Z

135

Evaluation of solid-based separation materials for the pretreatment of radioactive wastes  

SciTech Connect

Separation science will play an important role in pretreating nuclear wastes stored at various US Department of Energy Sites. The application of separation processes offers potential economic and environmental benefits with regards to remediating these sites. For example, at the Hanford Site, the sizeable volume of radioactive wastes stored in underground tanks could be partitioned into a small volume of high-level waste (HLW) and a relatively large volume of low-level waste (LLW). After waste separation, only the smaller volume of HLW would require costly vitrification and geologic disposal. Furthermore, the quality of the remaining LLW form (e.g., grout) would be improved due to the lower inventory of radionuclides present in the LLW stream. This report investigates extraction chromatography as a possible separation process for Hanford wastes.

Lumetta, G.J.; Wagner, M.J.; Wester, D.W.; Morrey, J.R.

1993-05-01T23:59:59.000Z

136

Department of Energy treatment capabilities for greater-than-Class C low-level radioactive waste  

SciTech Connect

This report provides brief profiles for 26 low-level and high-level waste treatment capabilities available at the Idaho National Engineering Laboratory (INEL), Lawrence Livermore National Laboratory (LLNL), Los Alamos National Laboratory (LANL), Oak Ridge National Laboratory (ORNL), Pacific Northwest Laboratory (PNL), Rocky Flats Plant (RFP), Savannah River Site (SRS), and West Valley Demonstration Plant (WVDP). Six of the treatments have potential use for greater-than-Class C low-level waste (GTCC LLW). They include: (a) the glass ceramic process and (b) the Waste Experimental Reduction Facility incinerator at INEL; (c) the Super Compaction and Repackaging Facility and (d) microwave melting solidification at RFP; (e) the vitrification plant at SRS; and (f) the vitrification plant at WVDP. No individual treatment has the capability to treat all GTCC LLW streams. It is recommended that complete physical and chemical characterizations be performed for each GTCC waste stream, to permit using multiple treatments for GTCC LLW.

Morrell, D.K.; Fischer, D.K.

1995-01-01T23:59:59.000Z

137

Radioactive waste disposal characteristics of candidate tokamak demonstration reactors  

SciTech Connect

Results from the current physics, materials and blanket R and D programs are combined with physics and engineering design constraints to characterize candidate tokamak demonstration plant (DEMO) designs. Blanket designs based on the principal structural materials, breeding materials and coolants being developed for the DEMO were adapted from the literature. Neutron flux and activation calculations were performed, and several radioactive waste disposal indices were evaluated, for each design. Of the primary low-activation structural materials under development in the US, it appears that vanadium and ferritic steel alloys, and possibly silicon carbide, could lead to DEMO designs which could satisfy realistic low-level waste (LLW) criteria, provided that impurities can be controlled within plausible limits. Allowable LLW concentrations are established for the limiting alloying and impurity elements. All breeding materials and neutron multipliers considered meet the LLW criterion.

Hoffman, E.A.; Stacey, W.M.; Hertel, N.E.

1998-08-01T23:59:59.000Z

138

DOE Railcar Fleet Asset Planning & Lessons Learned  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Railcar Railcar Fleet DOE Railcar Fleet Asset Planning & Lessons Learned Dave Lojek - US DOE Lessons Learned Dave Lojek US DOE Environmental Management Consolidated Business Center (EMCBC) Support: Office of Packaging & Transportation (EM-45) Di i O i Discussion Overview *Completed Rail Campaigns - LLW -Fernald, Mound, Savannah River *In Progress - LLW -Savannah River, Brookhaven, Moab *ForeCast - LLW -Portsmouth, Paducah, D&D, DUF6 2 *Lessons Learned F ld Cl P j t Fernald Closure Project First Rail Shipment: April 26, 1999 First Rail Shipment: Final Rail Shipment: April 26, 1999 October 11, 2006 Unit Trains Shipped: 201 Railcars Shipped: 12,000 3 Tons Shipped: 1,200,000 F ld R il E i t Fernald Rail Equipment * 3 - Locomotives * 250 Total Railcars In Service 190 New Purchase Gov't Gondolas 60 Leased Gondola Railcars

139

Seagate Crystal Reports - RADCM  

Office of Environmental Management (EM)

Mexico Mexico SITE: LosAlamos PROGRAM: DP WASTE TYPE: Low Level Waste OPERATIONS OFFICE: Albuquerque Operations Office % of Stream LosAlamos - Low Level Waste - LLW-PCB WASTE STREAM CODE: 02015 STREAM NAME:LLW-PCB MPC NAME:Soil/Debris TOTAL CURIES: Approved Volume : Future Volume Avg: Future Volume Lower Limit: Future Volume Upper Limit: 100.000 LLW -PCB Isotopes Plutonium-239 Avg Concentration: Low Limit Concent: Upper Limit Concent:1.0000E+002 nCi/g Americium-241 Avg Concentration: Low Limit Concent: Upper Limit Concent:1.0000E+002 nCi/g Cesium-137 Avg Concentration: Low Limit Concent: Upper Limit Concent:8.6400E+002 nCi/g Uranium-238 Avg Concentration: Low Limit Concent: Upper Limit Concent:4.8900E+002 nCi/g Plutonium-238 Avg Concentration: Low Limit Concent: Upper Limit Concent:1.0000E+002 nCi/g

140

P  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

5: s m r \o \o P s CA DISCLAIMER r r M c M LLW Drum Staging BuiMing Environmental Assessment August 3, 1994 DISCLAIMER Portions of t f G s document may be illegible in electronic image products. images are produced from the best avaiIable original document. LLW Drum Staging Building Environmental Assessment EXECUTIVE SUMMARY The proposed action is to place a 3 meter (m) by 4.5 m (10 ft x 15 ft) prefabricated storage building (uansportainer) adjacent to the existing Weapons Engineering Tritium Facility (PlrETF) at Technical Area (TA-) 16, Los Alamos National Laboratory (LANL), and to use the building as a staging site for sealed 55-gallon drums of noncompactible waste contaminated with low levels of z3ium (LLW). Up to eight drums of waste would be

Note: This page contains sample records for the topic "non-hlw wds llw" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


141

Volume 5: Waste Forms for Interim Storage, Revision 1  

Science Conference Proceedings (OSTI)

In the 1990s, the Electric Power Research Institute (EPRI) published a series of guidance reports on Interim On-Site Storage of Low Level Waste due to concern that loss of access to disposal pathways might one day lead to the need for interim on-site storage of low level waste (LLW). With the closure of the Barnwell Disposal Site to out-of-compact waste in 2008, 85% of the industry has, in fact, been faced with the loss of a disposal pathway for their Class B and C LLW, resulting in the reality of on-sit...

2011-09-14T23:59:59.000Z

142

Greater-than-Class C low-level radioactive waste characterization. Appendix A-1: Nuclear utility data outputs from the GNUPS database  

SciTech Connect

The Greater-Than-Class C Nuclear Utility Projections System (GNUPS) was developed as a database for the GTCC LLW Program to estimate future volumes and radionuclide activities of nuclear utility GTCC LLW. Detailed printouts from the GNUPS database are presented in this appendix. The GNUPS projects nuclear utility volumes and activities for three cases: low, base, and high. In addition, the projections can be adjusted to account for the effects of packaging, concentration averaging, and plant operating lifetime. A brief description of how the GNUPS performs calculations of volumes and activities is given.

1994-09-01T23:59:59.000Z

143

Recommended Changes to Guidelines for Operating an Interim On-Site Low Level Radioactive Waste Storage Facility - For NRC Review  

Science Conference Proceedings (OSTI)

The majority of commercial U.S. nuclear stations have constructed on-site low-level waste (LLW) storage facilities, and most of these same utilities are experiencing or have experienced at least one period of interim on-site storage. EPRI has issued two revisions of Guidelines for Operating an Interim On-Site Low Level Radioactive Waste Storage Facility. Revision 1 of these Guidelines focused on operational considerations and incorporated many of the lessons learned while operating various types of LLW s...

2011-12-19T23:59:59.000Z

144

Low-level waste certification plan for the Lawrence Berkeley Laboratory Hazardous Waste Handling Facility. Revision 1  

SciTech Connect

The purpose of this plan is to describe the organization and methodology for the certification of low-level radioactive waste (LLW) handled in the Hazardous Waste Handling Facility (HWHF) at Lawrence Berkeley Laboratory (LBL). This plan is composed to meet the requirements found in the Westinghouse Hanford Company (WHC) Solid Waste Acceptance Criteria (WAC) and follows the suggested outline provided by WHC in the letter of April 26, 1990, to Dr. R.H. Thomas, Occupational Health Division, LBL. LLW is to be transferred to the WHC Hanford Site Central Waste Complex and Burial Grounds in Hanford, Washington.

1995-01-10T23:59:59.000Z

145

Chloride removal from vitrification offgas  

Science Conference Proceedings (OSTI)

This study identified and investigated techniques of selectively purging chlorides from the low-level waste (LLW) vitrification process with the purge stream acceptable for burial on the Hanford Site. Chlorides will be present in high concentration in several individual feeds to the LLW Vitrification Plant. The chlorides are highly volatile in combustion type melters and are readily absorbed by wet scrubbing of the melter offgas. The Tank Waste Remediation System (TWRS) process flow sheets show that the resulting chloride rich scrub solution is recycled back to the melter. The chlorides must be purged from the recycle loop to prevent the buildup of excessively high chloride concentrations.

Slaathaug, E.J. [Westinghouse Hanford Co., Richland, WA (United States)

1995-06-01T23:59:59.000Z

146

Evaluation of Waste Forms for Immobilization of (14)C and (129)I: Development of Novel Management Scheme for (14)C and (129)I  

Science Conference Proceedings (OSTI)

(14)C and (129)I radionuclides can pose waste disposal challenges, since they are readily incorporated into bio-organic molecules and have half-lives that are substantially longer than most other radionuclides present in nuclear power plant low level waste (LLW). This study evaluated several techniques for separating (14)C and (129)I from LLW as well as a number of waste forms for immobilizing them. While the study did not result in any viable approaches for separating the waste, it did identify a number...

1998-09-04T23:59:59.000Z

147

Proceedings: 2003 EPRI International Low Level Waste Conference  

SciTech Connect

Nuclear utilities are continually evaluating methods to improve operations and minimize cost. EPRI's Twelfth Annual International Low Level Waste (LLW) Conference--coupled with the 24th Annual ASME/EPRI Radwaste Workshop--offered valuable insights into this effort by presenting papers covering new or improved technology developed worldwide for LLW management, processing, shipment, disposal, and regulation. EPRI accomplished the conference planning in collaboration with the International Atomic Energy Agency (IAEA). In addition to the United States, international representatives from the IAEA, Korea, Hungary, Canada, the United Kingdom, Japan, and Germany presented papers.

None

2004-04-01T23:59:59.000Z

148

THE FREQUENCY OF DEBRIS DISKS AT WHITE DWARFS  

SciTech Connect

We present near- and mid-infrared photometry and spectroscopy from PAIRITEL, IRTF, and Spitzer of a metallicity-unbiased sample of 117 cool, hydrogen-atmosphere white dwarfs (WDs) from the Palomar-Green survey and find five with excess radiation in the infrared, translating to a 4.3{sup +2.7} {sub -1.2}% frequency of debris disks. This is slightly higher than, but consistent with the results of previous surveys. Using an initial-final mass relation, we apply this result to the progenitor stars of our sample and conclude that 1-7 M {sub Sun} stars have at least a 4.3% chance of hosting planets; an indirect probe of the intermediate-mass regime eluding conventional exoplanetary detection methods. Alternatively, we interpret this result as a limit on accretion timescales as a fraction of WD cooling ages; WDs accrete debris from several generations of disks for {approx}10 Myr. The average total mass accreted by these stars ranges from that of 200 km asteroids to Ceres-sized objects, indicating that WDs accrete moons and dwarf planets as well as solar system asteroid analogs.

Barber, Sara D.; Patterson, Adam J.; Kilic, Mukremin [Homer L. Dodge Department of Physics and Astronomy, University of Oklahoma, 440 W. Brooks St., Norman, OK 73019 (United States); Leggett, S. K. [Gemini Observatory, 670 N. A'ohoku Place, Hilo, HI 96720 (United States); Dufour, P. [Departement de Physique, Universite de Montreal, C.P. 6128, Succursale Centre-Ville, Montreal, Quebec H3C 3J7 (Canada); Bloom, J. S.; Starr, D. L., E-mail: barber@nhn.ou.edu [Department of Astronomy, University of California, Berkeley, CA 94720 (United States)

2012-11-20T23:59:59.000Z

149

Low level waste management: a compilation of models and monitoring techniques. Volume 1  

SciTech Connect

In support of the National Low-Level Waste (LLW) Management Research and Development Program being carried out at Oak Ridge National Laboratory, Science Applications, Inc., conducted a survey of models and monitoring techniques associated with the transport of radionuclides and other chemical species from LLW burial sites. As a result of this survey, approximately 350 models were identified. For each model the purpose and a brief description are presented. To the extent possible, a point of contact and reference material are identified. The models are organized into six technical categories: atmospheric transport, dosimetry, food chain, groundwater transport, soil transport, and surface water transport. About 4% of the models identified covered other aspects of LLW management and are placed in a miscellaneous category. A preliminary assessment of all these models was performed to determine their ability to analyze the transport of other chemical species. The models that appeared to be applicable are identified. A brief survey of the state-of-the-art techniques employed to monitor LLW burial sites is also presented, along with a very brief discussion of up-to-date burial techniques.

Mosier, J.E.; Fowler, J.R.; Barton, C.J. (comps.)

1980-04-01T23:59:59.000Z

150

Siting Study for the Remote-Handled Low-Level Waste Disposal Project  

Science Conference Proceedings (OSTI)

The U.S. Department of Energy has identified a mission need for continued disposal capacity for remote-handled low-level waste (LLW) generated at the Idaho National Laboratory (INL). An alternatives analysis that was conducted to evaluate strategies to achieve this mission need identified two broad options for disposal of INL generated remote-handled LLW: (1) offsite disposal and (2) onsite disposal. The purpose of this study is to identify candidate sites or locations within INL boundaries for the alternative of an onsite remote handled LLW disposal facility and recommend the highest-ranked locations for consideration in the National Environmental Policy Act process. The study implements an evaluation based on consideration of five key elements: (1) regulations, (2) key assumptions, (3) conceptual design, (4) facility performance, and (5) previous INL siting study criteria, and uses a five-step process to identify, screen, evaluate, score, and rank 34 separate sites located across INL. The result of the evaluation is identification of two recommended alternative locations for siting an onsite remote-handled LLW disposal facility. The two alternative locations that best meet the evaluation criteria are (1) near the Advanced Test Reactor Complex and (2) west of the Idaho Comprehensive Environmental Response, Compensation, and Liability Act Disposal Facility.

Lisa Harvego; Joan Connolly; Lance Peterson; Brennon Orr; Bob Starr

2010-10-01T23:59:59.000Z

151

National Environmental Policy Act Compliance Strategy for the Remote-Handled Low-level Waste Disposal Facility  

Science Conference Proceedings (OSTI)

The U.S. Department of Energy (DOE) needs to have disposal capability for remote-handled low level waste (LLW) generated at the Idaho National Laboratory (INL) at the time the existing disposal facility is full or must be closed in preparation for final remediation of the INL Subsurface Disposal Area in approximately the year 2017.

Peggy Hinman

2010-10-01T23:59:59.000Z

152

Greater-than-Class C low-level radioactive waste transportation regulations and requirements study. National Low-Level Waste Management Program  

SciTech Connect

The purpose of this report is to identify the regulations and requirements for transporting greater-than-Class C (GTCC) low-level radioactive waste (LLW) and to identify planning activities that need to be accomplished in preparation for transporting GTCC LLW. The regulations and requirements for transporting hazardous materials, of which GTCC LLW is included, are complex and include several Federal agencies, state and local governments, and Indian tribes. This report is divided into five sections and three appendices. Section 1 introduces the report. Section 2 identifies and discusses the transportation regulations and requirements. The regulations and requirements are divided into Federal, state, local government, and Indian tribes subsections. This report does not identify the regulations or requirements of specific state, local government, and Indian tribes, since the storage, treatment, and disposal facility locations and transportation routes have not been specifically identified. Section 3 identifies the planning needed to ensure that all transportation activities are in compliance with the regulations and requirements. It is divided into (a) transportation packaging; (b) transportation operations; (c) system safety and risk analysis, (d) route selection; (e) emergency preparedness and response; and (f) safeguards and security. This section does not provide actual planning since the details of the Department of Energy (DOE) GTCC LLW Program have not been finalized, e.g., waste characterization and quantity, storage, treatment and disposal facility locations, and acceptance criteria. Sections 4 and 5 provide conclusions and referenced documents, respectively.

Tyacke, M.; Schmitt, R.

1993-07-01T23:59:59.000Z

153

Low-level radioactive waste management: transitioning to off-site disposal at Los Alamos National Laboratory  

SciTech Connect

Facing the closure of nearly all on-site management and disposal capability for low-level radioactive waste (LLW), Los Alamos National Laboratory (LANL) is making ready to ship the majority of LLW off-site. In order to ship off-site, waste must meet the Treatment, Storage, and Disposal Facility's (TSDF) Waste Acceptance Criteria (WAC). In preparation, LANL's waste management organization must ensure LANL waste generators characterize and package waste compliantly and waste characterization documentation is complete and accurate. Key challenges that must be addressed to successfully make the shift to off-site disposal of LLW include improving the detail, accuracy, and quality of process knowledge (PK) and acceptable knowledge (AK) documentation, training waste generators and waste management staff on the higher standard of data quality and expectations, improved WAC compliance for off-site facilities, and enhanced quality assurance throughout the process. Certification of LANL generators will allow direct off-site shipping of LLW from their facilities.

Dorries, Alison M [Los Alamos National Laboratory

2010-11-09T23:59:59.000Z

154

Nondestructive Evaluation of Low-Level Radioactive Waste Canisters for Free-Water Content  

Science Conference Proceedings (OSTI)

Federal regulations set limits on free-standing liquid in radioactive waste containers. This report identifies four nondestructive evaluation methods that may provide nuclear power plant operators with reliable and accurate determinations of the existence and amount of free-standing liquids in low-level radioactive waste (LLW) containers.

1991-06-17T23:59:59.000Z

155

Caustic leaching of high-level radioactive tank sludge: A critical literature review  

Science Conference Proceedings (OSTI)

The Department of Energy (DOE) must treat and safely dispose of its radioactive tank contents, which can be separated into high-level waste (HLW) and low-level waste (LLW) fractions. Since the unit costs of treatment and disposal are much higher for HLW than for LLW, technologies to reduce the amount of HLW are being developed. A key process currently being studied to reduce the volume of HLW sludges is called enhanced sludge washing (ESW). This process removes, by water washes, soluble constituents such as sodium salts, and the washed sludge is then leached with 2--3 M NaOH at 60--100 C to remove nonradioactive metals such as aluminum. The remaining solids are considered to be HLW while the solutions are LLW after radionuclides such as {sup 137}Cs have been removed. Results of bench-scale tests have shown that the ESW will probably remove the required amounts of inert constituents. While both experimental and theoretical results have shown that leaching efficiency increases as the time and temperature of the leach are increased, increases in the caustic concentration above 2--3 M will only marginally improve the leach factors. However, these tests were not designed to validate the assumption that the caustic used in the ESW process will generate only a small increase (10 Mkg) in the amount of LLW; instead the test conditions were selected to maximize leaching in a short period and used more water and caustic than is planned during full-scale operations. Even though calculations indicate that the estimate for the amount of LLW generated by the ESW process appears to be reasonable, a detailed study of the amount of LLW from the ESW process is still required. If the LLW analysis indicates that sodium management is critical, then a more comprehensive evaluation of the clean salt process or caustic recycle would be needed. Finally, experimental and theoretical studies have clearly demonstrated the need for the control of solids formation during and after leaching.

McGinnis, C.P.; Welch, T.D.; Hunt, R.D.

1998-08-01T23:59:59.000Z

156

Clean option: An alternative strategy for Hanford Tank Waste Remediation. Volume 2, Detailed description of first example flowsheet  

SciTech Connect

Disposal of high-level tank wastes at the Hanford Site is currently envisioned to divide the waste between two principal waste forms: glass for the high-level waste (HLW) and grout for the low-level waste (LLW). The draft flow diagram shown in Figure 1.1 was developed as part of the current planning process for the Tank Waste Remediation System (TWRS), which is evaluating options for tank cleanup. The TWRS has been established by the US Department of Energy (DOE) to safely manage the Hanford tank wastes. It includes tank safety and waste disposal issues, as well as the waste pretreatment and waste minimization issues that are involved in the ``clean option`` discussed in this report. This report describes the results of a study led by Pacific Northwest Laboratory to determine if a more aggressive separations scheme could be devised which could mitigate concerns over the quantity of the HLW and the toxicity of the LLW produced by the reference system. This aggressive scheme, which would meet NRC Class A restrictions (10 CFR 61), would fit within the overall concept depicted in Figure 1.1; it would perform additional and/or modified operations in the areas identified as interim storage, pretreatment, and LLW concentration. Additional benefits of this scheme might result from using HLW and LLW disposal forms other than glass and grout, but such departures from the reference case are not included at this time. The evaluation of this aggressive separations scheme addressed institutional issues such as: radioactivity remaining in the Hanford Site LLW grout, volume of HLW glass that must be shipped offsite, and disposition of appropriate waste constituents to nonwaste forms.

Swanson, J.L.

1993-09-01T23:59:59.000Z

157

WasteStreamForecast2010.xls  

Office of Environmental Management (EM)

Reporting Reporting Site Disposition Facility Field Stream ID Actual Dispos 2009 Starting Inventory 2010 2010 2011 2012 2013 2014 2015 to 2019 2020 to 2024 2025 to 2029 2030 to 2034 2035 to 2039 2040-50 1 Ames Energy Solutions-Clive (formerly Envirocare) 8020-01 0.00 0.00 0.00 0.00 0.00 20.00 0.00 0.00 20.00 20.00 20.00 0.00 60.00 2 Argonne Area 5 LLW Disposal Unit (NTS) AEL105DOEa 55.12 50.45 72.36 29.22 29.22 29.22 29.22 29.22 0.00 0.00 0.00 0.00 0.00 3 Argonne Area 5 LLW Disposal Unit (NTS) AEL106DOEa 0.38 0.07 0.09 0.21 0.21 0.21 0.21 0.21 0.00 0.00 0.00 0.00 0.00 4 Argonne Area 5 LLW Disposal Unit (NTS) AE-L104DOE 0.19 10.85 11.19 0.42 0.42 0.42 0.42 0.42 0.00 0.00 0.00 0.00 0.00 5 Argonne Area 5 LLW Disposal Unit (NTS) AEL103DOE 74.13 87.37 110.16 30.39 30.39 30.39 30.39 30.39 0.00 0.00 0.00 0.00 0.00 6 Argonne Area 5 LLW Disposal Unit (NTS)

158

Assessing Potential Exposure from Truck Transport of Low-level Radioactive Waste to the Nevada Test Site  

Science Conference Proceedings (OSTI)

Since 1980, over 651,558 m{sup 3} (23,000,000 ft{sup 3}) of low-level radioactive waste (LLW) have been disposed of at the Nevada Test Site (NTS) by shallow land burial. Since 1988, the majority of this waste has been generated at other United States (U.S.) Department of Energy (DOE) and Department of Defense (DoD) sites and facilities in the U.S. Between fiscal year (FY) 2002 and the publication date, the volumes of LLW being shipped by truck to the NTS increased sharply with the accelerated closure of DOE Environmental Management (EM) Program sites (DOE, 2002). The NTS is located 105 km (65 mi) northwest of Las Vegas, Nevada, in the U.S. There continue to be public concerns over the safety of LLW shipments to the NTS. They can be broadly divided into two categories: (1) the risk of accidents involving trucks traveling on public highways; and (2) whether residents along transportation routes receive cumulative exposure from individual LLW shipments that pose a long-term health risk. The DOE and U.S. Department of Transportation (DOT) regulations ensure that radiation exposure from truck shipments to members of the public is negligible. Nevertheless, particularly in rural communities along transportation routes in Utah and Nevada, there is a perceived risk from members of the public about cumulative exposure, particularly when ''Main Street'' and the routes being used by LLW trucks are one in the same. To provide an objective assessment of gamma radiation exposure to members of the public from LLW transport by truck, the Desert Research Institute (DRI) and the DOE, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) established a stationary and automated array of four pressurized ion chambers (PICs) in a vehicle pullout for LLW trucks to pass through just outside the entrance to the NTS. The PICs were positioned at a distance of 1.0 m (3.3 ft) from the sides of the truck trailer and at a height of 1.5 m (5.0 ft) to simulate conditions that a member of the public (Turner, 1995) might experience if a truck were to pass while the person was on the side of the road, or if a truck were to come to a stop at a stoplight in one of the smaller towns along the transportation routes. The 1.0-m (3.3-ft) distance also allowed for comparison with gamma readings of trucks taken with portable, hand-held instruments at the two LLW disposal sites at the NTS: the Area 5 Radioactive Waste Management Complex (RWMC) and the Area 3 Radioactive Waste Management Site (RWMS). The purpose in automating the system was to provide the most objective and consistent measurement and calculation of radiation exposure from the trucks possible. The array was set up in November 2002 and equipment was tested and calibrated over the next two months. Data collection on trucks began on February 13, 2003, and continued to the end of December 2003. In all, external gamma readings were collected from 1,012 of the 2,260 trucks that delivered LLW to the NTS during this period. Because DOE could not contractually require waste generators to participate in the study, the database is biased toward voluntary participants; however, data were collected from the 10 generators that represented 92 percent of the LLW shipments to the NTS during the study period, with another eight generators accounting for the balance of the shipments. Because of the voluntary nature of the participation, the identity of the waste generators is not used in the report. Previous studies on potential exposure to the public from transporting LLW to the NTS either relied on calculated exposures (Davis et al., 2002) or was based on a small population of trucks (e.g., 88) where a relatively high-background value of 50 microRoentgens per hour (R/h) (background value measured at the LLW disposal sites) were subtracted from the gross reading of the truck trailer as measured by portable, handheld instruments (Gertz, 2001). The dataset that resulted from the DRI study is the largest collection of measurements of LLW trucks in transit of which the authors are aware.

J. Miller; D. Shafer; K. Gray; B. Church; S. Campbell; B. Holz

2005-08-01T23:59:59.000Z

159

Assessing Potential Exposure from Truck Transport of Low-level Radioactive Waste to the Nevada Test Site  

Science Conference Proceedings (OSTI)

Since 1980, over 651,558 m{sup 3} (23,000,000 ft{sup 3}) of low-level radioactive waste (LLW) have been disposed of at the Nevada Test Site (NTS) by shallow land burial. Since 1988, the majority of this waste has been generated at other United States (U.S.) Department of Energy (DOE) and Department of Defense (DoD) sites and facilities in the U.S. Between fiscal year (FY) 2002 and the publication date, the volumes of LLW being shipped by truck to the NTS increased sharply with the accelerated closure of DOE Environmental Management (EM) Program sites (DOE, 2002). The NTS is located 105 km (65 mi) northwest of Las Vegas, Nevada, in the U.S. There continue to be public concerns over the safety of LLW shipments to the NTS. They can be broadly divided into two categories: (1) the risk of accidents involving trucks traveling on public highways; and (2) whether residents along transportation routes receive cumulative exposure from individual LLW shipments that pose a long-term health risk. The DOE and U.S. Department of Transportation (DOT) regulations ensure that radiation exposure from truck shipments to members of the public is negligible. Nevertheless, particularly in rural communities along transportation routes in Utah and Nevada, there is a perceived risk from members of the public about cumulative exposure, particularly when ''Main Street'' and the routes being used by LLW trucks are one in the same. To provide an objective assessment of gamma radiation exposure to members of the public from LLW transport by truck, the Desert Research Institute (DRI) and the DOE, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) established a stationary and automated array of four pressurized ion chambers (PICs) in a vehicle pullout for LLW trucks to pass through just outside the entrance to the NTS. The PICs were positioned at a distance of 1.0 m (3.3 ft) from the sides of the truck trailer and at a height of 1.5 m (5.0 ft) to simulate conditions that a member of the public (Turner, 1995) might experience if a truck were to pass while the person was on the side of the road, or if a truck were to come to a stop at a stoplight in one of the smaller towns along the transportation routes. The 1.0-m (3.3-ft) distance also allowed for comparison with gamma readings of trucks taken with portable, hand-held instruments at the two LLW disposal sites at the NTS: the Area 5 Radioactive Waste Management Complex (RWMC) and the Area 3 Radioactive Waste Management Site (RWMS). The purpose in automating the system was to provide the most objective and consistent measurement and calculation of radiation exposure from the trucks possible. The array was set up in November 2002 and equipment was tested and calibrated over the next two months. Data collection on trucks began on February 13, 2003, and continued to the end of December 2003. In all, external gamma readings were collected from 1,012 of the 2,260 trucks that delivered LLW to the NTS during this period. Because DOE could not contractually require waste generators to participate in the study, the database is biased toward voluntary participants; however, data were collected from the 10 generators that represented 92 percent of the LLW shipments to the NTS during the study period, with another eight generators accounting for the balance of the shipments. Because of the voluntary nature of the participation, the identity of the waste generators is not used in the report. Previous studies on potential exposure to the public from transporting LLW to the NTS either relied on calculated exposures (Davis et al., 2002) or was based on a small population of trucks (e.g., 88) where a relatively high-background value of 50 microRoentgens per hour ({micro}R/h) (background value measured at the LLW disposal sites) were subtracted from the gross reading of the truck trailer as measured by portable, handheld instruments (Gertz, 2001). The dataset that resulted from the DRI study is the largest collection of measurements of LLW trucks in transit of which the authors are aware.

Miller, J; Shafer, D; Gray, K; Church, B; Campbell, S; Holtz, B.

2005-08-15T23:59:59.000Z

160

EIS-0200: Record of Decision | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

00: Record of Decision 00: Record of Decision EIS-0200: Record of Decision Treatment and Disposal of Low-Level Waste and Mixed Low-Level Waste; Amendment of the Record of Decision for the Nevada Test Site For the management of low- level waste (LLW) analyzed in the Final Waste Management Programmatic Environmental Impact Statement (WM PEIS), the Department of Energy (DOE) has decided to perform minimum treatment at all sites and continue, to the extent practicable, disposal of on- site LLW at the Idaho National Engineering and Environmental Laboratory (INEEL), the Los Alamos National Laboratory (LANL) in New Mexico, the Oak Ridge Reservation (ORR) in Tennessee, and the Savannah River Site (SRS) in South Carolina. In addition, the Department has decided to make the Hanford Site

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161

EIS-0337-SA-01: Supplement Analysis | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

7-SA-01: Supplement Analysis 7-SA-01: Supplement Analysis EIS-0337-SA-01: Supplement Analysis West Valley Demonstration Project Waste Management The Department of Energy's (DOE) West Valley Demonstration Project (WVDP) prepared a final waste management environmental impact statement (WVDP WM ElS) that examined the potential environmental impacts associated with the proposed shipment of radioactive wastes that were either in storage or would be generated over a 10-year period (DOE 2003). Since the EIS was issued, new information has become available regarding the volume and type of low level radioactive waste (LLW), and DOE now proposes to use additional disposal locations for LLW waste for which the transportation impacts were not analyzed in the WVDP WM EIS. West Valley Demonstration Project Waste Management Environmental Impact

162

Page not found | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

51 - 560 of 29,416 results. 51 - 560 of 29,416 results. Download EA-1900: Notice of Availability of a Final Environmental Assessment and Finding of No Significant Impact Radiological Work and Storage Building at the Knolls Atomic Power Laboratory Kesselring Site, West Milton, New York http://energy.gov/nepa/downloads/ea-1900-notice-availability-final-environmental-assessment-and-finding-no-significant Page EIS-0243: Nevada Test Site and Off-Site Locations in the State of Nevada This EIS evaluates the potential environmental impacts of the management of low-level waste (LLW) at all sites and continue, to the extent practicable, disposal of on- site LLW at the Idaho... http://energy.gov/nepa/eis-0243-nevada-test-site-and-site-locations-state-nevada Page EA-1061: The Off-site Volume Reduction of Low-level Radioactive Waste

163

Microsoft Word - DOE-ID-INL-10-021.doc  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

21 21 SECTION A. Project Title: Geotechnical Investigation for INL Remote-Handled Low-Level Waste Disposal SECTION B. Project Description: The proposed action would conduct geotechnical investigations at two 4-6 acre candidate sites for a Remote-Handled Low-Level Waste (RH LLW) Facility at the Idaho National Laboratory (INL). One site is located southwest of the Advanced Test Reactor (ATR)-Complex and the other site is located west of and across Lincoln Blvd. from the Idaho Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Disposal Facility (ICDF). The RH LLW Facility is one alternative being analyzed to address an anticipated shortfall of disposal capability following cessation of RHLLW disposal operations at the

164

Overview of Nevada Test Site Radioactive and Mixed Waste Disposal Operations  

SciTech Connect

The U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office Environmental Management Program is responsible for carrying out the disposal of on-site and off-site generated low-level radioactive waste (LLW) and low-level radioactive mixed waste (MW) at the Nevada Test Site (NTS). Core elements of this mission are ensuring safe and cost-effective disposal while protecting workers, the public, and the environment. This paper focuses on the impacts of new policies, processes, and opportunities at the NTS related to LLW and MW. Covered topics include: the first year of direct funding for NTS waste disposal operations; zero tolerance policy for non-compliant packages; the suspension of mixed waste disposal; waste acceptance changes; DOE Consolidated Audit Program (DOECAP) auditing; the 92-Acre Area closure plan; new eligibility requirements for generators; and operational successes with unusual waste streams.

J.T. Carilli; S.K. Krenzien; R.G. Geisinger; S.J. Gordon; B. Quinn

2009-03-01T23:59:59.000Z

165

DOE to Weigh Alternatives for Greater Than Class C Low-Level Waste Disposal  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

to Weigh Alternatives for Greater Than Class C Low-Level Waste to Weigh Alternatives for Greater Than Class C Low-Level Waste Disposal DOE to Weigh Alternatives for Greater Than Class C Low-Level Waste Disposal July 20, 2007 - 2:55pm Addthis WASHINGTON, DC - The U.S. Department of Energy (DOE) today announced that it will evaluate disposal options for Greater Than Class C (GTCC) low-level radioactive waste (LLW) generated from the decommissioning of nuclear power plants, medical activities and nuclear research. DOE delivered to the Federal Register this week a Notice of Intent (NOI) to prepare an Environmental Impact Statement (EIS), which will evaluate how and where to safely dispose of GTCC LLW that is currently stored at commercial nuclear power plants and other generator sites across the country. The Energy Policy Act of 2005 requires DOE to report to Congress on its evaluation of

166

EIS-0243: Nevada Test Site and Off-Site Locations in the State of Nevada |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

3: Nevada Test Site and Off-Site Locations in the State of 3: Nevada Test Site and Off-Site Locations in the State of Nevada EIS-0243: Nevada Test Site and Off-Site Locations in the State of Nevada Summary This EIS evaluates the potential environmental impacts of the management of low-level waste (LLW) at all sites and continue, to the extent practicable, disposal of on- site LLW at the Idaho National Engineering and Environmental Laboratory (INEEL), the Los Alamos National Laboratory (LANL) in New Mexico, the Oak Ridge Reservation (ORR) in Tennessee, and the Savannah River Site (SRS) in South Carolina. Public Comment Opportunities None available at this time. Documents Available for Download November 3, 2003 EIS-0243-SA-02: Supplement Analysis Nevada Test Site and Off-Site Locations in the State of Nevada to Address

167

DOE Selects Two Contractors for Multiple-Award Waste Disposal Contract |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Two Contractors for Multiple-Award Waste Disposal Two Contractors for Multiple-Award Waste Disposal Contract DOE Selects Two Contractors for Multiple-Award Waste Disposal Contract April 12, 2013 - 12:00pm Addthis Media Contact Bill Taylor, 803-952-8564 Bill.Taylor@srs.gov Cincinnati - The U.S. Department of Energy (DOE) awarded two fixed price unit rate Indefinite Delivery/Indefinite Quantity (ID/IQ) multiple-award contracts for the permanent disposal of Low-Level Waste (LLW) and Mixed-Low Level Waste (MLLW) today to EnergySolutions, LLC and Waste Control Specialists, LLC. The goal of these contracts is to establish a vehicle that allows DOE sites to place timely, competitive and cost-effective task orders for the permanent disposal of: Class A, B, and C LLW and MLLW 11e(2) byproduct material Technology Enhanced Naturally Occurring Radioactive Material

168

Record of Decision for the Department of Energy's Waste Management Program: Treatment and Disposal of Low-Level Waste and Mixed Low-Level Waste; Amendment of the Record of Decision for the Nevada Test Site (DOE/EIS-0200) (DOE/EIS-0243) (2/25/00)_  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

061 061 Federal Register / Vol. 65, No. 38 / Friday, February 25, 2000 / Notices 1 After the Final WM PEIS was issued in May 1997, DOE issued ''Accelerating Cleanup: Paths to Closure.'' In that document, DOE provided estimates of waste volumes that would result from the planned operations and accelerated cleanup processes at DOE sites. Because some of the estimates differed from those provided in the WM PEIS, DOE examined the LLW and MLLW volumes to determine if the updated volume estimates constitute significant new information relevant to environmental concerns that would warrant preparation of a supplemental EIS or a new PEIS. This examination extended only to LLW and MLLW volumes, because the transuranic, hazardous and high-level waste volume estimates did not change

169

Low Level Waste Disposition - Quantity and Inventory | Department of  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Low Level Waste Disposition - Quantity and Inventory Low Level Waste Disposition - Quantity and Inventory Low Level Waste Disposition - Quantity and Inventory This study has been prepared by the Used Fuel Disposition (UFD) campaign of the Fuel Cycle Research and Development (FCR&D) program. The purpose of this study is to provide an estimate of the volume of low level waste resulting from a variety of commercial fuel cycle alternatives in order to support subsequent system-level evaluations of disposal system performance. This study provides an estimate of Class A/B/C low level waste (LLW), greater than Class C (GTCC) waste, mixed LLW and mixed GTCC waste generated from the following initial set of fuel cycles and recycling processes: 1. Operations at a geologic repository based upon a once through light

170

Low Level Waste Disposition - Quantity and Inventory | Department of  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Low Level Waste Disposition - Quantity and Inventory Low Level Waste Disposition - Quantity and Inventory Low Level Waste Disposition - Quantity and Inventory This study has been prepared by the Used Fuel Disposition (UFD) campaign of the Fuel Cycle Research and Development (FCR&D) program. The purpose of this study is to provide an estimate of the volume of low level waste resulting from a variety of commercial fuel cycle alternatives in order to support subsequent system-level evaluations of disposal system performance. This study provides an estimate of Class A/B/C low level waste (LLW), greater than Class C (GTCC) waste, mixed LLW and mixed GTCC waste generated from the following initial set of fuel cycles and recycling processes: 1. Operations at a geologic repository based upon a once through light

171

Microsoft PowerPoint - News Flash_Idaho AMWTP_110509  

NLE Websites -- All DOE Office Websites (Extended Search)

Date Date U.S. Department of Energy For more information on EM Recovery Act, visit: www.em.doe.gov/emrecovery Environmental Management Recovery Act Keeping You in the Know November 5, 2009 Idaho's Advanced Mixed Waste Treatment Project Completes Recovery Act Goals U.S. Department of Energy For more information on EM Recovery Act, visit: www.em.doe.gov/emrecovery With funds provided by the American Recovery and Reinvestment Act (Recovery Act) the U.S. Department of Energy's Idaho Site is shipping radioactive waste years ahead of schedule. The site committed to shipping 1,300 cubic meters of low level waste (LLW) and mixed low level waste (MLLW) out of Idaho and retrieving 1,200 cubic meters of stored transuranic (TRU) waste. Ship a total of 1,303 cubic meters of LLW and MLLW off site.

172

Replacement Capability for Disposal of Remote-Handled Low-Level Waste Generated at the Department of Energys Idaho Site  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Environmental Assessment Environmental Assessment for the Replacement Capability for Disposal of Remote-Handled Low-Level Radioactive Waste Generated at the Department of Energy's Idaho Site August 2011 DOE/EA-1793 Draft Environmental Assessment for the Replacement Capability for Disposal of Remote-Handled Low-Level Radioactive Waste Generated at the Department of Energy's Idaho Site August 2011 v EXECUTIVE SUMMARY The U.S. Department of Energy (DOE) proposes to provide replacement capability for disposal of remote-handled low-level radioactive waste (LLW) generated at the Idaho National Laboratory (INL) site beginning in October 2017. Historically, INL has disposed of this LLW onsite. However, the existing disposal area located within the INL Radioactive Waste Management Complex will undergo

173

Implementation plan for the Waste Experimental Reduction Facility Restart Operational Readiness Review  

SciTech Connect

The primary technical objective for the WERF Restart Project is to assess, upgrade where necessary, and implement management, documentation, safety, and operation control systems that enable the resumption and continued operation of waste treatment and storage operations in a manner that is compliant with all environment, safety, and quality requirements of the US Department of Energy and Federal and State regulatory agencies. Specific processes that will be resumed at WERF include compaction of low-level compatible waste; size reduction of LLW, metallic and wood waste; incineration of combustible LLW and MLLW; and solidification of low-level and mixed low-level incinerator bottom ash, baghouse fly ash, and compatible sludges and debris. WERF will also provide for the operation of the WWSB which includes storage of MLLW in accordance with Resource Conservation and Recovery Act requirements.

Not Available

1993-03-01T23:59:59.000Z

174

Assessment of Preferred Depleted Uranium Disposal Forms  

SciTech Connect

The Department of Energy (DOE) is in the process of converting about 700,000 metric tons (MT) of depleted uranium hexafluoride (DUF6) containing 475,000 MT of depleted uranium (DU) to a stable form more suitable for long-term storage or disposal. Potential conversion forms include the tetrafluoride (DUF4), oxide (DUO2 or DU3O8), or metal. If worthwhile beneficial uses cannot be found for the DU product form, it will be sent to an appropriate site for disposal. The DU products are considered to be low-level waste (LLW) under both DOE orders and Nuclear Regulatory Commission (NRC) regulations. The objective of this study was to assess the acceptability of the potential DU conversion products at potential LLW disposal sites to provide a basis for DOE decisions on the preferred DU product form and a path forward that will ensure reliable and efficient disposal.

Croff, A.G.; Hightower, J.R.; Lee, D.W.; Michaels, G.E.; Ranek, N.L.; Trabalka, J.R.

2000-06-01T23:59:59.000Z

175

Waste minimization handbook, Volume 1  

Science Conference Proceedings (OSTI)

This technical guide presents various methods used by industry to minimize low-level radioactive waste (LLW) generated during decommissioning and decontamination (D and D) activities. Such activities generate significant amounts of LLW during their operations. Waste minimization refers to any measure, procedure, or technique that reduces the amount of waste generated during a specific operation or project. Preventive waste minimization techniques implemented when a project is initiated can significantly reduce waste. Techniques implemented during decontamination activities reduce the cost of decommissioning. The application of waste minimization techniques is not limited to D and D activities; it is also useful during any phase of a facility`s life cycle. This compendium will be supplemented with a second volume of abstracts of hundreds of papers related to minimizing low-level nuclear waste. This second volume is expected to be released in late 1996.

Boing, L.E.; Coffey, M.J.

1995-12-01T23:59:59.000Z

176

Potential for and consequences of criticality resulting from hydrogeochemically concentrated fissile uranium blended with soil in low-level waste disposal facilities  

SciTech Connect

Evaluations were done to determine conditions that could permit nuclear criticality with fissile uranium in low-level-waste (LLW) facilities and to estimate potential radiation exposures to personnel if there were such an accident. Simultaneous hydrogeochemical and nuclear criticality studies were done (1) to identify some realistic scenarios for uranium migration and concentration increase at LLW disposal facilities, (2) to model groundwater transport and subsequent concentration via sorption or precipitation of uranium, (3) to evaluate the potential for nuclear criticality resulting from potential increases in uranium concentration over disposal limits, and (4) to estimate potential radiation exposures to personnel resulting from criticality consequences. The scope of the referenced work was restricted to uranium at an assumed 100 wt% {sup 235}U enrichment. Three outcomes of uranium concentration are possible: uranium concentration is increased to levels that do pose a criticality safety concern; uranium concentration is increased, but levels do not pose a criticality safety concern; or uranium concentration does not increase.

Hopper, C.M.; Parks, C.V.

1997-08-01T23:59:59.000Z

177

Potential for Subsidence at the Low-Level Radioactive Waste Disposal Area  

Science Conference Proceedings (OSTI)

U.S. Department of Energy (DOE) Order 435.1, Radioactive Waste Management requires that DOE low-level radioactive waste (LLW) disposal facilities receive a Disposal Authorization Statement (DAS) from DOE-Headquarters. The DAS for the LLW disposal facility at the Radioactive Waste Management Complex (RWMC) at the Idaho National Engineering and Environmental Laboratory (INEEL) was granted in April 2000 and included a number of conditions that must be addressed. A maintenance plan (Schuman 2000) was prepared that identifies the tasks to be completed to address the conditions in the DAS as well as a schedule for their completion. The need for a subsidence analysis was one of the conditions identified for the DAS, and thus, a task to prepare a subsidence analysis was included in the maintenance plan. This document provides the information necessary to satisfy that requirement.

Keck, K.A.; Seitz, R.R.

2002-09-26T23:59:59.000Z

178

Potential for Subsidence at the Low-level Waste Disposal Area  

Science Conference Proceedings (OSTI)

U.S. Department of Energy (DOE) Order 435.1, Radioactive Waste Management requires that DOE low-level radioactive waste (LLW) disposal facilities receive a Disposal Authorization Statement (DAS) from DOE-Headquarters. The DAS for the LLW disposal facility at the Radioactive Waste Management Complex (RWMC) at the Idaho National Engineering and Environmental Laboratory (INEEL) was granted in April 2000 and included a number of conditions that must be addressed. A maintenance plan (Schuman 2000) was prepared that identifies the tasks to be completed to address the conditions in the DAS as well as a schedule for their completion. The need for a subsidence analysis was one of the conditions identified for the DAS, and thus, a task to prepare a subsidence analysis was included in the maintenance plan. This document provides the information necessary to satisfy that requirement.

Keck, Karen Nina; Seitz, Roger Ray

2002-09-01T23:59:59.000Z

179

Selection of a computer code for Hanford low-level waste engineered-system performance assessment  

Science Conference Proceedings (OSTI)

Planned performance assessments for the proposed disposal of low-level waste (LLW) glass produced from remediation of wastes stored in underground tanks at Hanford, Washington will require calculations of radionuclide release rates from the subsurface disposal facility. These calculations will be done with the aid of computer codes. Currently available computer codes were ranked in terms of the feature sets implemented in the code that match a set of physical, chemical, numerical, and functional capabilities needed to assess release rates from the engineered system. The needed capabilities were identified from an analysis of the important physical and chemical process expected to affect LLW glass corrosion and the mobility of radionuclides. The highest ranked computer code was found to be the ARES-CT code developed at PNL for the US Department of Energy for evaluation of and land disposal sites.

McGrail, B.P.; Mahoney, L.A.

1995-10-01T23:59:59.000Z

180

Identification of Non-Pertechnetate Species in Hanford Tank Waste, Their Synthesis, Characterization, and Fundamental Chemistry  

Science Conference Proceedings (OSTI)

Technetium, as pertechnetate (TcO4 -), is a mobile species in the environment. This characteristic, along with its long half-life, (99Tc, t1/2 = 213,000 a) makes technetium a major contributor to the long-term hazard associated with low level waste (LLW) disposal. Technetium partitioning from the nuclear waste at DOE sites may be required so that the LLW forms meet DOE performance assessment criteria. Technetium separations assume that technetium exists as TcO4 - in the waste. However, years of thermal, chemical, and radiolytic digestion in the presence of organic material, has transformed much of the TcO4 - into unidentified, stable, reduced, technetium complexes. To successfully partition technetium from tank wastes, it will be necessary to either remove these technetium species with a new process, or reoxidize them to TcO4 - so that conventional pertechnetate separation schemes will be successful.

Schroeder, Norman C.; Ashley, Kenneth R.; Olivares, Jose A.

2004-06-15T23:59:59.000Z

Note: This page contains sample records for the topic "non-hlw wds llw" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
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181

Evaluation of Department of Energy-Held Potential Greater-Than-Class C Low-Level Radioactive Waste. Revision 1  

Science Conference Proceedings (OSTI)

A number of commercial facilities have generated potential greater-than-Class C low-level radioactive waste (GTCC LLW), and, through contractual arrangements with the US Department of Energy (DOE) or for health and safety reasons, DOE is storing the waste. This report presents the results of an assessment conducted by the GTCC LLW Management Program to consider specific circumstances under which DOE accepted the waste, and to determine whether disposal in a facility licensed by the US Nuclear Regulatory Commission, or by DOE in a nonlicensed facility, is appropriate. Input from EG&G Idaho, Inc., and DOE Idaho Operations Office legal departments concerning the disposal requirements of this waste were the basis for the decision process used in this report.

NONE

1994-09-01T23:59:59.000Z

182

Mixed waste characterization, treatment & disposal focus area  

Science Conference Proceedings (OSTI)

The mission of the Mixed Waste Characterization, Treatment, and Disposal Focus Area (referred to as the Mixed Waste Focus Area or MWFA) is to provide treatment systems capable of treating DOE`s mixed waste in partnership with users, and with continual participation of stakeholders, tribal governments, and regulators. The MWFA deals with the problem of eliminating mixed waste from current and future storage in the DOE complex. Mixed waste is waste that contains both hazardous chemical components, subject to the requirements of the Resource Conservation and Recovery Act (RCRA), and radioactive components, subject to the requirements of the Atomic Energy Act. The radioactive components include transuranic (TRU) and low-level waste (LLW). TRU waste primarily comes from the reprocessing of spent fuel and the use of plutonium in the fabrication of nuclear weapons. LLW includes radioactive waste other than uranium mill tailings, TRU, and high-level waste, including spent fuel.

NONE

1996-08-01T23:59:59.000Z

183

Test plan for evaluation of plasma melter technology for vitrification of high-sodium content low-level radioactive liquid wastes  

SciTech Connect

This document provides a test plan for the conduct of plasma arc vitrification testing by a vendor in support of the Hanford Tank Waste Remediation System (TWRS) Low-Level Waste (LLW) Vitrification Program. The vendor providing this test plan and conducting the work detailed within it [one of seven selected for glass melter testing under Purchase Order MMI-SVV-384212] is the Westinghouse Science and Technology Center (WSTC) in Pittsburgh, PA. WSTC authors of the test plan are D. F. McLaughlin, E. J. Lahoda, W. R. Gass, and N. D`Amico. The WSTC Program Manager for this test is D. F. McLaughlin. This test plan is for Phase I activities described in the above Purchase Order. Test conduct includes melting of glass frit with Hanford LLW Double-Shell Slurry Feed waste simulant in a plasma arc fired furnace.

McLaughlin, D.F.; Lahoda, E.J.; Gass, W.R.; D`Amico, N. [ed.

1994-10-20T23:59:59.000Z

184

Seagate Crystal Reports - RADCM  

Office of Environmental Management (EM)

Idaho Idaho SITE: Argonne-W PROGRAM: EM WASTE TYPE: Low Level Waste OPERATIONS OFFICE: Chicago Operations Office % of Stream Argonne-W - Low Level Waste - Phyto-Remediation Residuals WASTE STREAM CODE: 01181 STREAM NAME:Phyto-Remediation Residuals MPC NAME:Debris W aste TOTAL CURIES: Approved Volume : 1.800 Future Volume Avg: 0.000 Future Volume Lower Limit: Future Volume Upper Limit: % of Stream Argonne-W - Low Level Waste - LLW Contaminated Rubble/Debris WASTE STREAM CODE: 04081 STREAM NAME:LLW Contaminated Rubble/Debris MPC NAME:Debris W aste TOTAL CURIES: Approved Volume : 0.000 Future Volume Avg: 40.000 Future Volume Lower Limit: Future Volume Upper Limit: STATE: Idaho SITE: Argonne-W PROGRAM: EM WASTE TYPE: Mixed Low Level Waste OPERATIONS OFFICE: Chicago Operations Office

185

Seagate Crystal Reports - RADCM  

Office of Environmental Management (EM)

Illinois Illinois SITE: Argonne-E PROGRAM: EM WASTE TYPE: Low Level Waste OPERATIONS OFFICE: Chicago Operations Office % of Stream Argonne-E - Low Level Waste - LLW-Contaminated Rubble/Debris WASTE STREAM CODE: 01133 STREAM NAME:LLW-Contaminated Rubble/Debris MPC NAME:Asphalt Debris TOTAL CURIES: Approved Volume : 400.000 Future Volume Avg: 50.000 Future Volume Lower Limit: Future Volume Upper Limit: STATE: Illinois SITE: Argonne-E PROGRAM: EM WASTE TYPE: Mixed Low Level Waste OPERATIONS OFFICE: Chicago Operations Office % of Stream Argonne-E - Mixed Low Level Waste - MLLW-Contaminated D&D Rubble/Debris (Metals) WASTE STREAM CODE: 01134 STREAM NAME:MLLW-Contaminated D&D Rubble/Debris (Metals) MPC NAME:Elemental Hazardous Metals TOTAL CURIES: Approved Volume : 49.110 Future Volume Avg: 64.900

186

Seagate Crystal Reports - Cm102  

Office of Environmental Management (EM)

Contaminated Media Contaminated Media Contaminated Media: In-Situ Contaminated Media (CM-10) STATE: Alaska SITE: Amchitka PROGRAM: EM WASTE TYPE: LLW OPERATIONS OFFICE: Nevada Operations Office Amchitka - LLW - RAD/Ground Water Stream Code: 01015 Generating Program: EM MPC Name: Ground/Surface Waters Total Curies: Approved Volume: 0 Cubic meters Future Volume Avg: 0 Cubic meters Future Volume Lower Limit: Future Volume Upper Limit: Source Site: AINP Destination Site: AINP Activity: Primary TSD System: Estimated Volume Avg: 0 Cubic meters Lower Limit Volume: Upper Limit Volume: Activity: Comb of Acc/Inst Con TSD System: STATE: Colorado SITE: GrJuncOff PROGRAM: EM WASTE TYPE: 11e2 OPERATIONS OFFICE: Idaho Operations Office Page 1 of 65 Tuesday, June 3, 2008 Data Set ID: EM Corporate - FY 2001 Update

187

EA-1793: Draft Environmental Assessment | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

3: Draft Environmental Assessment 3: Draft Environmental Assessment EA-1793: Draft Environmental Assessment Replacement Capability for Disposal of Remote-Handled Low-Level Radioactive Waste Generated at the Department of Energy's Idaho Site The U.S. Department of Energy (DOE) proposes to provide replacement capability for disposal of remote-handled low-level radioactive waste (LLW) generated at the Idaho National Laboratory (INL) site beginning in October 2017. Historically, INL has disposed of this LLW onsite. However, the existing disposal area located within the INL Radioactive Waste Management Complex will undergo closure as part of ongoing cleanup of INL and will not be available after 2017. The proposed project to establish replacement capability is not a DOE Environmental Management Idaho Cleanup Project

188

EA-0843: Idaho National Engineering Laboratory Low-Level and Mixed Waste  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

43: Idaho National Engineering Laboratory Low-Level and Mixed 43: Idaho National Engineering Laboratory Low-Level and Mixed Waste Processing, Idaho Falls, Idaho EA-0843: Idaho National Engineering Laboratory Low-Level and Mixed Waste Processing, Idaho Falls, Idaho SUMMARY This EA evaluates the environmental impacts of a proposal to (1) reduce the volume of the U.S. Department of Energy's Idaho National Engineering Laboratory's (INEL) generated low-level waste (LLW) through sizing, compaction, and stabilization at Waste Experimental Reduction Facility (WERF); and (2) use commercial offsite facilities for supplemental LLW volume reduction (incineration). PUBLIC COMMENT OPPORTUNITIES None available at this time. DOCUMENTS AVAILABLE FOR DOWNLOAD June 3, 1994 EA-0843: Finding of No Significant Impact Idaho National Engineering Laboratory Low-Level and Mixed Waste Processing

189

Technical area status report for waste destruction and stabilization  

SciTech Connect

The Office of Environmental Restoration and Waste Management (EM) was established by the Department of Energy (DOE) to direct and coordinate waste management and site remediation programs/activities throughout the DOE complex. In order to successfully achieve the goal of properly managing waste and the cleanup of the DOE sites, the EM was divided into five organizations: the Office of Planning and Resource Management (EM-10); the Office of Environmental Quality Assurance and Resource Management (EM-20); the Office of Waste Operations (EM-30); the Office of Environmental Restoration (EM-40); and the Office of Technology and Development (EM-50). The mission of the Office of Technology Development (OTD) is to develop treatment technologies for DOE`s operational and environmental restoration wastes where current treatment technologies are inadequate or not available. The Mixed Waste Integrated Program (MWIP) was created by OTD to assist in the development of treatment technologies for the DOE mixed low-level wastes (MLLW). The MWIP has established five Technical Support Groups (TSGs) whose purpose is to identify, evaluate, and develop treatment technologies within five general technical areas representing waste treatment functions from initial waste handling through generation of final waste forms. These TSGs are: (1) Front-End Waste Handling, (2) Physical/Chemical Treatment, (3) Waste Destruction and Stabilization, (4) Second-Stage Destruction and Offgas Treatment, and (5) Final Waste Forms. This report describes the functions of the Waste Destruction and Stabilization (WDS) group. Specifically, the following items are discussed: DOE waste stream identification; summary of previous efforts; summary of WDS treatment technologies; currently funded WDS activities; and recommendations for future activities.

Dalton, J.D.; Harris, T.L.; DeWitt, L.M. [Science Applications International Corp., Idaho Falls, ID (United States)

1993-08-01T23:59:59.000Z

190

Proceedings: 2010 EPRI International Low Level Waste Conference  

Science Conference Proceedings (OSTI)

Nuclear utilities are continually evaluating methods to improve operations, minimize costs, and find alternatives for disposal of Nuclear Regulatory Commission (NRC) Class A, B, and C waste. The Electric Power Research Institutes (EPRIs) 19th annual International Low Level Waste (LLW) Conferencecoupled with the 33rd annual American Society of Mechanical Engineers (ASME)/EPRI Radwaste Workshopoffered valuable insights into this effort by presenting papers covering new or improved technology developed worl...

2011-06-07T23:59:59.000Z

191

Chemistry of application of calcination/dissolution to the Hanford tank waste inventory  

SciTech Connect

Approximately 330,000 metric tons of sodium-rich radioactive waste originating from separation of plutonium from irradiated uranium fuel are stored in underground tanks at the Hanford Site in Washington State. Fractionation of the waste into low-level waste (LLW) and high-level waste (HLW) streams is envisioned via partial water dissolution and limited radionuclide extraction operations. Under optimum conditions, LLW would contain most of the chemical bulk while HLW would contain virtually all of the transuranic and fission product activity. Calcination at around 850 C, followed by water dissolution, has been proposed as an alternative initial treatment of Hanford Site waste to improve waste dissolution and the envisioned LLW/HLW split. Results of literature and laboratory studies are reported on the application of calcination/dissolution (C/D) to the fractionation of the Hanford Site tank waste inventory. Both simulated and genuine Hanford Site waste materials were used in the lab tests. To evaluation confirmed that C/D processing reduced the amount of several components from the waste. The C/D dissolutions of aluminum and chromium allow redistribution of these waste components from the HLW to the LLW fraction. Comparisons of simple water-washing with C/D processing of genuine Hanford Site waste are also reported based on material (radionuclide and chemical) distributions to solution and solid residue phases. The lab results show that C/D processing yielded superior dissolution of aluminum and chromium sludges compared to simple water dissolution. 57 refs., 26 figs., 18 tabs.

Delegard, C.H.; Elcan, T.D.; Hey, B.E.

1994-05-01T23:59:59.000Z

192

Estimating decommissioning costs: The 1994 YNPS decommissioning cost study  

Science Conference Proceedings (OSTI)

Early this year, Yankee Atomic Electric Company began developing a revised decommissioning cost estimate for the Yankee Nuclear Power Station (YNPS) to provide a basis for detailed decommissioning planning and to reflect slow progress in siting low-level waste (LLW) and spent-nuclear-fuel disposal facilities. The revision also reflects the need to change from a cost estimate that focuses on overall costs to a cost estimate that is sufficiently detailed to implement decommissioning and identify the final cost of decommissioning.

Szymczak, W.J.

1994-12-31T23:59:59.000Z

193

Proceedings: 2011 EPRI International Low Level Waste Conference and Exhibit Show  

Science Conference Proceedings (OSTI)

Nuclear utilities are continually evaluating methods to improve operations, minimize costs, and find alternatives for disposal of Nuclear Regulatory Commission (NRC) Class A, B, and C waste. The Electric Power Research Institute's (EPRI's) 20th Annual International Low Level Waste (LLW) Conferencecoupled with the 34th Annual American Society of Mechanical Engineers (ASME)/EPRI Radwaste Workshopoffered valuable insights into this effort by presenting papers covering new or improved technology developed wo...

2012-03-21T23:59:59.000Z

194

Acquisition Strategy for the Idaho National Laboratory Remote-Handled Low-Level Waste Disposition Project  

Science Conference Proceedings (OSTI)

This document describes the design-build acquisition strategy that will be applied to the Remote Handled LLW Disposal Project. The design-build delivery method will be tailored, as appropriate, to integrate the requirements of Department of Energy (DOE) Order 413.3B, 'Program and Project Management for the Acquisition of Capital Assets,' with the DOE budget formulation process and the safety requirements of DOE-STD-1189, 'Integration of Safety into the Design Process.'

David Duncan

2011-05-01T23:59:59.000Z

195

Low Level Waste On Site Storage Operating Guidelines -- Supplemental Information Manual  

Science Conference Proceedings (OSTI)

This Supplemental Information Manual captures essential information related to the implementation of an on-site low level waste (LLW) storage program. It summarizes the guidance and experience provided in the Interim On-Site Storage series of reports and should be used in concert with EPRI report 1018644, "Guidelines for Operating an Interim On Site Low Level Radioactive Waste Storage FacilityRevision 1," 2009.

2009-02-26T23:59:59.000Z

196

Decommissioning Low Level Waste Management and Reduction Guide  

Science Conference Proceedings (OSTI)

Nuclear plants undertaking decommissioning projects find that costs of low-level waste (LLW) management are a substantial portion of the total cost. To assist the industry in planning and optimizing their decommissioning radwaste management practices, EPRI developed a guide with more than 75 areas of guidance and an extensive lessons learned section. Using this report will aid utilities in successfully planning, executing, and disposing of low-level wastes during a decommissioning project.

1999-09-17T23:59:59.000Z

197

Intruder scenarios for site-specific low-level radioactive waste classification  

Science Conference Proceedings (OSTI)

The US Department of Energy (DOE) has revised its low-level radioactive waste (LLW) management requirements and guidelines for waste generated at its facilities supporting defense missions. Specifically, draft DOE Order 5820.2A, Chapter 3 describes the purpose, policy, and requirements necessary for the management of defense LLW. The draft DOE policy calls for LLW operations to be managed to protect the health and safety of the public, preserve the environment, and ensure that no remedial action will be necessary after termination of operations. The basic approach used by DOE is to establish overall performance objectives, in terms of groundwater protection and public radiation dose limits, and to require site-specific performance assessments to determine compliance. As a result of these performance assessments, each site will develop waste acceptance criteria that define the allowable quantities and concentrations of specific radioisotopes. Additional limitations on waste disposal design, waste form, and waste treatment will also be developed on a site-specific basis. As a key step in the site-specific performance assessments, an evaluation must be conducted of potential radiation doses to intruders who may inadvertently move onto a closed DOE LLW disposal site after loss of institutional controls. This report (1) describes the types of intruder scenarios that should be considered when performing this step of the site-specific performance assessment, (2) provides the results of generic calculations performed using unit concentrations of various radionuclides as a comparison of the magnitude of importance of the various intruder scenarios, and (3) shows the relationship between the generic doses and waste classification limits for defense wastes.

Kennedy, W.E. Jr.; Peloquin, R.A.

1988-09-01T23:59:59.000Z

198

LLWnotes - Volume 11, Number 4  

SciTech Connect

This document is the May 1996 issue of LLWnotes. It contains articles and news items on the following topics: news items related to states and compacts; Low-Level Radioactive Waste (LLW) Forum activities; court rulings and calendars; US DOE testing at Ward Valley; US BLM contract with Lawrence Livermore National Laboratory; Mixed Waste Pilot Project Schedule; extension of US EPA`s mixed waste enforcement moratorium; EPA Advisory Committee on research program operation; and decommissioning.

1996-05-01T23:59:59.000Z

199

Improved Cobalt Removal: Field Testing Phase: Effects of Normally Encountered Plant Impurities on Removal Performance  

Science Conference Proceedings (OSTI)

This study examined the effects of plant impurities on cobalt removal from liquid radioactive waste. Improved process knowledge is critical to utilities that are continually working to increase the performance of their low-level waste (LLW) treatment systems. This report provides predictive chemistry information for improved cobalt removal obtained from test work at Catawba Nuclear Station. It also provides test methodologies for performing similar evaluations at other member plants.

2001-11-26T23:59:59.000Z

200

Proceedings: 2012 EPRI International Low Level Waste Conference and Exhibit Show  

Science Conference Proceedings (OSTI)

Nuclear utilities are continually evaluating methods to improve operations, minimize costs, and find alternatives for disposal of Nuclear Regulatory Commission (NRC) Class A, B, and C waste. The Electric Power Research Institutes (EPRIs) 21st annual International Low Level Waste (LLW) Conferencecoupled with the 35th annual American Society of Mechanical Engineers (ASME)/EPRI Radwaste Workshopoffered valuable insights into this effort by presenting papers covering new or ...

2013-05-31T23:59:59.000Z

Note: This page contains sample records for the topic "non-hlw wds llw" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


201

Justification Of The Use Of Boreholes For Disposal Of Sealed Radiological Sources  

Science Conference Proceedings (OSTI)

Soon there will be only 14 states in two compacts that are able to dispose of Low Level Waste (LLW): the Northwest and Rocky Mountain compact with disposal options in Richland, Washington, and the Atlantic compact with disposal options in Barnwell, South Carolina. How do states not in one of the two compacts dispose of their LLW? The Off-Site Source Recovery Project can take possession and dispose of some of the unwanted transuranic sources at the Waste Isolation Pilot Plant (WIPP). However, there will be no path forward for states outside of the two compacts for disposal of their non-transuranic LLW. A solution that has been much discussed, debated and researched, but has not been put into wide scale practice, is the borehole disposal concept. It is the author's position that companies that drill and explore for oil have been disposing of sources in borehole-like structures for years. It should be noted that these companies are not purposely disposing of these sources, but the sources are irretrievable and must be abandoned. Additionally, there are Nuclear Regulatory Commission (NRC) regulations that must be followed to seal the well that contains the lost and abandoned source. According to the NRC Event Notification Reports database, there were a minimum of 29 reports of lost and abandoned sources in oil wells between December 1999 and October 2006. The sources were lost at depths between 2,018-18,887 feet, or 600-5,750 meters. The companies that are performing explorations with the aid of sealed radiological sources must follow regulation 10 CFR Part 39. Subsection 15 outlines the procedures that must be followed if sources are determined to be irretrievable and abandoned in place. If the NRC allows and has regulations in place for oil companies, why can't states and/or companies be allowed to dispose of LLW in a similar fashion?

Zarling, John [Los Alamos National Laboratory; Johnson, Peter [Los Alamos National Laboratory

2008-01-01T23:59:59.000Z

202

Waste Receiving and Processing Facility Module 1 Data Management System Software Requirements Specification  

Science Conference Proceedings (OSTI)

This document provides the software requirements for Waste Receiving and Processing (WRAP) Module 1 Data Management System (DMS). The DMS is one of the plant computer systems for the new WRAP 1 facility (Project W-026). The DMS will collect, store and report data required to certify the low level waste (LLW) and transuranic (TRU) waste items processed at WRAP 1 as acceptable for shipment, storage, or disposal.

Brann, E.C. II

1994-09-09T23:59:59.000Z

203

Estimation of natural ground water recharge for the performance assessment of a low-level waste disposal facility at the Hanford Site  

SciTech Connect

In 1994, the Pacific Northwest Laboratory (PNL) initiated the Recharge Task, under the PNL Vitrification Technology Development (PVTD) project, to assist Westinghouse Hanford Company (WHC) in designing and assessing the performance of a low-level waste (LLW) disposal facility for the US Department of Energy (DOE). The Recharge Task was established to address the issue of ground water recharge in and around the LLW facility and throughout the Hanford Site as it affects the unconfined aquifer under the facility. The objectives of this report are to summarize the current knowledge of natural ground water recharge at the Hanford Site and to outline the work that must be completed in order to provide defensible estimates of recharge for use in the performance assessment of this LLW disposal facility. Recharge studies at the Hanford Site indicate that recharge rates are highly variable, ranging from nearly zero to greater than 100 mm/yr depending on precipitation, vegetative cover, and soil types. Coarse-textured soils without plants yielded the greatest recharge. Finer-textured soils, with or without plants, yielded the least. Lysimeters provided accurate, short-term measurements of recharge as well as water-balance data for the soil-atmosphere interface and root zone. Tracers provided estimates of longer-term average recharge rates in undisturbed settings. Numerical models demonstrated the sensitivity of recharge rates to different processes and forecast recharge rates for different conditions. All of these tools (lysimetry, tracers, and numerical models) are considered vital to the development of defensible estimates of natural ground water recharge rates for the performance assessment of a LLW disposal facility at the Hanford Site.

Rockhold, M.L.; Fayer, M.J.; Kincaid, C.T.; Gee, G.W.

1995-03-01T23:59:59.000Z

204

Transportation Rule Technical Support  

Science Conference Proceedings (OSTI)

EPRI initiated this project as part of an industry effort to seek regulatory relief for two low-level waste (LLW) transportation container rules that the industry perceived as overly conservative. This report presents the technical arguments for regulatory change developed by the EPRI project team. EPRI, through the cooperation of the Nuclear Energy Institute (NEI), is in the process of bringing these two technical arguments forward to the various regulatory agencies.

2002-10-02T23:59:59.000Z

205

ESMAP-Indonesia-Low Carbon Development Options Study | Open Energy  

Open Energy Info (EERE)

Low Carbon Development Options Study Low Carbon Development Options Study Jump to: navigation, search Name Indonesia-ESMAP Low Carbon Country Studies Program Agency/Company /Organization Energy Sector Management Assistance Program of the World Bank Partner United Kingdom Department for International Development Sector Energy, Land Focus Area Energy Efficiency, Forestry Topics Background analysis, GHG inventory, Low emission development planning, Market analysis, Policies/deployment programs Website http://www-wds.worldbank.org/e Country Indonesia South-Eastern Asia References World Bank, ESMAP - Low Carbon Growth Country Studies - Getting Started[1] Overview "The Indonesia's study aimed to evaluate and develop strategic options to mitigate climate change without compromising the country's development

206

METAL ACCRETION ONTO WHITE DWARFS CAUSED BY POYNTING-ROBERTSON DRAG ON THEIR DEBRIS DISKS  

Science Conference Proceedings (OSTI)

Recent discoveries of compact (sizes {approx}rate M-dot{sub PR}{approx}10{sup 8} g s{sup -1} and higher, scaling quadratically with WD effective temperature. We compare our results with observations and show that, as expected, no WD hosting a particulate debris disk shows evidence of metal accretion rate below that produced by the PR drag. Existence of WDs accreting metals at rates significantly higher than M-dot{sub PR} suggests that another mechanism in addition to the PR drag drives accretion of high-Z elements in these systems.

Rafikov, Roman R., E-mail: rrr@astro.princeton.edu [Department of Astrophysical Sciences, Princeton University, Ivy Lane, Princeton, NJ 08540 (United States)

2011-05-01T23:59:59.000Z

207

Selected radionuclides important to low-level radioactive waste management  

Science Conference Proceedings (OSTI)

The purpose of this document is to provide information to state representatives and developers of low level radioactive waste (LLW) management facilities about the radiological, chemical, and physical characteristics of selected radionuclides and their behavior in the environment. Extensive surveys of available literature provided information for this report. Certain radionuclides may contribute significantly to the dose estimated during a radiological performance assessment analysis of an LLW disposal facility. Among these are the radionuclides listed in Title 10 of the Code of Federal Regulations Part 61.55, Tables 1 and 2 (including alpha emitting transuranics with half-lives greater than 5 years). This report discusses these radionuclides and other radionuclides that may be significant during a radiological performance assessment analysis of an LLW disposal facility. This report not only includes essential information on each radionuclide, but also incorporates waste and disposal information on the radionuclide, and behavior of the radionuclide in the environment and in the human body. Radionuclides addressed in this document include technetium-99, carbon-14, iodine-129, tritium, cesium-137, strontium-90, nickel-59, plutonium-241, nickel-63, niobium-94, cobalt-60, curium -42, americium-241, uranium-238, and neptunium-237.

NONE

1996-11-01T23:59:59.000Z

208

Implementation plan for WRAP Module 1 operational readiness review  

Science Conference Proceedings (OSTI)

The Waste Receiving and Processing Module 1 (WRAP 1) will be used to receive, sample, treat, and ship contact-handled (CH) transuranic (TRU), low-level waste (LLW), and low-level mixed waste (LLMW) to storage and disposal sites both on the Hanford site and off-site. The primary mission of WRAP 1 is to characterize and certify CH waste in 55-gallon and 85-gallon drums; and its secondary function is to certify CH waste standard waste boxes (SWB) and boxes of similar size for disposal. The WRAP 1 will provide the capability for examination (including x-ray, visual, and contents sampling), limited treatment, repackaging, and certification of CH suspect-TRU waste in 55-gallon drums retrieved from storage, as well as newly generated CH LLW and CH TRU waste drums. The WRAP 1 will also provide examination (X-ray and visual only) and certification of CH LLW and CH TRU waste in small boxes. The decision to perform an Operational Readiness Review (ORR) was made in accordance with WHC-CM-5-34, Solid Waste Disposal Operations Administration, Section 1.4, Operational Readiness Activities. The ORR will ensure plant and equipment readiness, management and personnel readiness, and management programs readiness for the initial startup of the facility. This implementation plan is provided for defining the conduct of the WHC ORR.

Irons, L.G.

1994-11-04T23:59:59.000Z

209

Waste Form Development for the Solidification of PDCF/MOX Liquid Waste Streams  

SciTech Connect

At the Savannah River Site, part of the Department of Energy's nuclear materials complex located in South Carolina, cementation has been selected as the solidification method for high-alpha and low-activity waste streams generated in the planned plutonium disposition facilities. A Waste Solidification Building (WSB) that will be used to treat and solidify three radioactive liquid waste streams generated by the Pit Disassembly and Conversion Facility) and the Mixed Oxide Fuel Fabrication Facility is in the preliminary design stage. The WSB is expected to treat a transuranic (TRU) waste stream composed primarily of americium and two low-level waste (LLW) streams. The acidic wastes will be concentrated in the WSB evaporator and neutralized in a cement head tank prior to solidification. A series of TRU mixes were prepared to produce waste forms exhibiting a range of processing and cured properties. The LLW mixes were prepared using the premix from the preferred TRU waste form. All of the waste forms tested passed the Toxicity Characteristic Leaching Procedure. After processing in the WSB, current plans are to dispose of the solidified TRU waste at the Waste Isolation Pilot Plant in New Mexico and the solidified LLW waste at an approved low-level waste disposal facility.

COZZI, ALEX

2004-02-18T23:59:59.000Z

210

Waste Form Development for the Solidification of PDCF/MOX Liquid Waste Streams  

SciTech Connect

At the Savannah River Site, part of the Department of Energy's nuclear materials complex located in South Carolina, cementation has been selected as the solidification method for high-alpha and low-activity waste streams generated in the planned plutonium disposition facilities. A Waste Solidification Building (WSB) that will be used to treat and solidify three radioactive liquid waste streams generated by the Pit Disassembly and Conversion Facility) and the Mixed Oxide Fuel Fabrication Facility is in the preliminary design stage. The WSB is expected to treat a transuranic (TRU) waste stream composed primarily of americium and two low-level waste (LLW) streams. The acidic wastes will be concentrated in the WSB evaporator and neutralized in a cement head tank prior to solidification. A series of TRU mixes were prepared to produce waste forms exhibiting a range of processing and cured properties. The LLW mixes were prepared using the premix from the preferred TRU waste form. All of the waste forms tested passed the Toxicity Characteristic Leaching Procedure. After processing in the WSB, current plans are to dispose of the solidified TRU waste at the Waste Isolation Pilot Plant in New Mexico and the solidified LLW waste at an approved low-level waste disposal facility.

COZZI, ALEX

2004-02-18T23:59:59.000Z

211

Equity of commercial low-level radioactive waste disposal fees. Report to Congress  

SciTech Connect

In the Report accompanying the Fiscal Year 1997 Senate Energy and Water Development Appropriations Bill, the Senate Appropriations Committee directed the Department of Energy (DOE) to prepare a study of the costs of operating a low-level radioactive waste (LLW) disposal facility such as the one at Barnwell, South Carolina, and to determine whether LLW generators are paying equitable disposal fees. The disposal costs of four facilities are reviewed in this report, two operating facilities and two planned facilities. The operating facilities are located at Barnwell, South Carolina, and Richland, Washington. They are operated by Chem-Nuclear, LLC, (Chem-Nuclear), and US Ecology, Inc., (US Ecology), respectively. The planned facilities are expected to be built at Ward Valley, California, and Sierra Blanca, Texas. They will be operated by US Ecology and the State of Texas, respectively. This report found that disposal fees vary significantly among facilities for a variety of reasons. However, the information suggests that at each disposal facility, LLW generators pay equitable disposal fees.

1998-02-01T23:59:59.000Z

212

Underground storage tank integrated demonstration: Evaluation of pretreatment options for Hanford tank wastes  

SciTech Connect

Separation science plays a central role inn the pretreatment and disposal of nuclear wastes. The potential benefits of applying chemical separations in the pretreatment of the radioactive wastes stored at the various US Department of Energy sites cover both economic and environmental incentives. This is especially true at the Hanford Site, where the huge volume (>60 Mgal) of radioactive wastes stored in underground tanks could be partitioned into a very small volume of high-level waste (HLW) and a relatively large volume of low-level waste (LLW). The cost associated with vitrifying and disposing of just the HLW fraction in a geologic repository would be much less than those associated with vitrifying and disposing of all the wastes directly. Futhermore, the quality of the LLW form (e.g., grout) would be improved due to the lower inventory of radionuclides present in the LLW stream. In this report, we present the results of an evaluation of the pretreatment options for sludge taken from two different single-shell tanks at the Hanford Site-Tanks 241-B-110 and 241-U-110 (referred to as B-110 and U-110, respectively). The pretreatment options examined for these wastes included (1) leaching of transuranic (TRU) elements from the sludge, and (2) dissolution of the sludge followed by extraction of TRUs and {sup 90}Sr. In addition, the TRU leaching approach was examined for a third tank waste type, neutralized cladding removal waste.

Lumetta, G.J.; Wagner, M.J.; Colton, N.G.; Jones, E.O.

1993-06-01T23:59:59.000Z

213

Certification Plan, low-level waste Hazardous Waste Handling Facility  

SciTech Connect

The purpose of this plan is to describe the organization and methodology for the certification of low-level radioactive waste (LLW) handled in the Hazardous Waste Handling Facility (HWHF) at Lawrence Berkeley Laboratory (LBL). This plan also incorporates the applicable elements of waste reduction, which include both up-front minimization and end-product treatment to reduce the volume and toxicity of the waste; segregation of the waste as it applies to certification; an executive summary of the Waste Management Quality Assurance Implementing Management Plan (QAIMP) for the HWHF and a list of the current and planned implementing procedures used in waste certification. This plan provides guidance from the HWHF to waste generators, waste handlers, and the Waste Certification Specialist to enable them to conduct their activities and carry out their responsibilities in a manner that complies with the requirements of WHC-WAC. Waste generators have the primary responsibility for the proper characterization of LLW. The Waste Certification Specialist verifies and certifies that LBL LLW is characterized, handled, and shipped in accordance with the requirements of WHC-WAC. Certification is the governing process in which LBL personnel conduct their waste generating and waste handling activities in such a manner that the Waste Certification Specialist can verify that the requirements of WHC-WAC are met.

Albert, R.

1992-06-30T23:59:59.000Z

214

RESULTS FOR THE THIRD QUARTER 2011 TANK 50 WAC SLURRY SAMPLE: CHEMICAL AND RADIONUCLIDE CONTAMINANT RESULTS  

Science Conference Proceedings (OSTI)

The Saltstone Facility is designed and permitted to immobilize and dispose of low-level radioactive and hazardous liquid waste (salt solution) remaining from the processing of radioactive material at the Savannah River Site. Low-level waste (LLW) streams from the Effluent Treatment Project (ETP), H-Canyon, and the decontaminated salt solution product from the Actinide Removal Process/Modular Caustic Side Solvent Extraction (CSSX) Unit (ARP/MCU) process are stored in Tank 50 until the LLW can be transferred to the Saltstone Facility for treatment and disposal. The LLW must meet the specified waste acceptance criteria (WAC) before it is processed into saltstone. The specific chemical and radionuclide contaminants and their respective WAC limits are in the current Saltstone WAC. Waste Solidification Engineering (WSE) requested that Savannah River National Laboratory (SRNL) perform quarterly analysis on saltstone samples. The concentrations of chemical and radionuclide contaminants are measured to ensure the saltstone produced during each quarter is in compliance with the current WAC. This report documents the concentrations of chemical and radionuclide contaminants for the 2011 Third Quarter samples collected from Tank 50 on July 7, 2011 and discusses those results in further detail than the previously issued results report.

Reigel, M.

2011-10-20T23:59:59.000Z

215

RESULTS FOR THE FOURTH QUARTER 2011 TANK 50 WAC SLURRY SAMPLE: CHEMICAL AND RADIONUCLIDE CONTAMINANT RESULTS  

Science Conference Proceedings (OSTI)

The Saltstone Facility is designed and permitted to immobilize and dispose of low-level radioactive and hazardous liquid waste (salt solution) remaining from the processing of radioactive material at the Savannah River Site. Low-level waste (LLW) streams from the Effluent Treatment Project (ETP), H-Canyon, and the decontaminated salt solution product from the Actinide Removal Process/Modular Caustic Side Solvent Extraction (CSSX) Unit (ARP/MCU) process are stored in Tank 50 until the LLW can be transferred to the Saltstone Facility for treatment and disposal. The LLW must meet the specified waste acceptance criteria (WAC) before it is processed into saltstone. The specific chemical and radionuclide contaminants and their respective WAC limits are in the current Saltstone WAC. Waste Solidification Engineering (WSE) requested that Savannah River National Laboratory (SRNL) perform quarterly analysis on saltstone samples. The concentrations of chemical and radionuclide contaminants are measured to ensure the saltstone produced during each quarter is in compliance with the current WAC. This report documents the concentrations of chemical and radionuclide contaminants for the 2011 Fourth Quarter samples collected from Tank 50 on October 12, 2011 and discusses those results in further detail than the previously issued results report.

Bannochie, C.

2012-01-31T23:59:59.000Z

216

Waste minimization for commercial radioactive materials users generating low-level radioactive waste. Revision 1  

SciTech Connect

The objective of this document is to provide a resource for all states and compact regions interested in promoting the minimization of low-level radioactive waste (LLW). This project was initiated by the Commonwealth of Massachusetts, and Massachusetts waste streams have been used as examples; however, the methods of analysis presented here are applicable to similar waste streams generated elsewhere. This document is a guide for states/compact regions to use in developing a system to evaluate and prioritize various waste minimization techniques in order to encourage individual radioactive materials users (LLW generators) to consider these techniques in their own independent evaluations. This review discusses the application of specific waste minimization techniques to waste streams characteristic of three categories of radioactive materials users: (1) industrial operations using radioactive materials in the manufacture of commercial products, (2) health care institutions, including hospitals and clinics, and (3) educational and research institutions. Massachusetts waste stream characterization data from key radioactive materials users in each category are used to illustrate the applicability of various minimization techniques. The utility group is not included because extensive information specific to this category of LLW generators is available in the literature.

Fischer, D.K.; Gitt, M.; Williams, G.A.; Branch, S. [EG and G Idaho, Inc., Idaho Falls, ID (United States); Otis, M.D.; McKenzie-Carter, M.A.; Schurman, D.L. [Science Applications International Corp., Idaho Falls, ID (United States)

1991-07-01T23:59:59.000Z

217

Facility accident analysis for low-level waste management alternatives in the US Department of Energy Waste Management Program  

Science Conference Proceedings (OSTI)

The risk to human health of potential radiological releases resulting from facility accidents constitutes an important consideration in the US Department of Energy (DOE) waste management program. The DOE Office of Environmental Management (EM) is currently preparing a Programmatic Environmental Impact Statement (PEIS) that evaluates the risks associated with managing five types of radiological and chemical wastes in the DOE complex. Several alternatives for managing each of the five waste types are defined and compared in the EM PEIS. The alternatives cover a variety of options for storing, treating, and disposing of the wastes. Several treatment methods and operation locations are evaluated as part of the alternatives. The risk induced by potential facility accidents is evaluated for storage operations (current and projected waste storage and post-treatment storage) and for waste treatment facilities. For some of the five waste types considered, facility accidents cover both radiological and chemical releases. This paper summarizes the facility accident analysis that was performed for low-level (radioactive) waste (LLW). As defined in the EM PEIS, LLW includes all radioactive waste not classified as high-level, transuranic, or spent nuclear fuel. LLW that is also contaminated with chemically hazardous components is treated separately as low-level mixed waste (LLMW).

Roglans-Ribas, J.; Mueller, C.; Nabelssi, B.; Folga, S.; Tompkins, M.

1995-06-01T23:59:59.000Z

218

An experimental investigation of the thermal/fluid properties of the NAC product slurry  

SciTech Connect

As regulation of the waste decontamination process becomes increasingly restrictive, the safe storage of liquid nuclear waste is one of the major challenges worldwide. Over the past 50 years, more than 242,700 tons of low-level radioactive waste (LLW) has been generated at various U.S. weapons facilities. This LLW is temporarily stored at U.S. Department of Energy facilities such as the single-shell tanks at the Hanford site, the Savannah River site, the Melton Valley storage tanks at Oak Ridge National Laboratory, and the Pad A Waste site at Idaho Falls. The characteristics of this sodium nitrate-based waste, in addition to the levels of radioactivity, are as follows: pH, either < 1 or > 12, with a total salt content of > 5 M, and a sodium content of > 1.5 M. Radioactive waste in the liquid state poses a great threat due to the potential for seeping into groundwater supplies. Therefore, it must be immobilized before final disposal. Currently, the most common immobilized method for LLW is the use of cement-based grout. Unfortunately, radioactive leaching is a major obstacle for this technology since the nitrate anion is very difficult to immobilize, especially in the relatively porous cement-based grout.

Muguercla, J.; Yang, G.; Li, W.; Ebadian, M.A. [Florida International Univ., Miami, FL (United States). Dept. of Mechanical Engineering; Mattus, A.J.; Lee, D.D.; Hunt, R.D. [Oak Ridge National Lab., TN (United States)

1994-04-01T23:59:59.000Z

219

Seagate Crystal Reports - RADCM  

Office of Environmental Management (EM)

Kentucky Kentucky SITE: Paducah PROGRAM: EM WASTE TYPE: Low Level Waste OPERATIONS OFFICE: Oak Ridge Operations Office % of Stream Paducah - Low Level Waste - LLW Rubble/Debris WASTE STREAM CODE: 00438 STREAM NAME:LLW Rubble/Debris MPC NAME:Debris W aste TOTAL CURIES: Approved Volume : Future Volume Avg: Future Volume Lower Limit: Future Volume Upper Limit: 100.000 LLW Debris Isotopes Neptunium-237 Avg Concentration: 1.0000E+000 pCi/g Low Limit Concent:0.0000E+000 pCi/g Upper Limit Concent:2.4000E+001 pCi/g Technetium-99 Avg Concentration: 5.0000E+001 pCi/g Low Limit Concent:0.0000E+000 pCi/g Upper Limit Concent:1.4210E+003 pCi/g Uranium-238 Avg Concentration: 5.0000E+001 pCi/g Low Limit Concent:0.0000E+000 pCi/g Upper Limit Concent:9.7800E+002 pCi/g Uranium-235 Avg Concentration: 7.0000E-001 wt%

220

Seagate Crystal Reports - RADCM  

Office of Environmental Management (EM)

California California SITE: EnergyTech PROGRAM: EM WASTE TYPE: Low Level Waste OPERATIONS OFFICE: Oakland Operations Office % of Stream EnergyTech - Low Level Waste - LLW-Defense D&D Waste (from ER) WASTE STREAM CODE: 01669 STREAM NAME:LLW-Defense D&D Waste (from ER) MPC NAME:Solids TOTAL CURIES: Approved Volume : 0.000 Future Volume Avg: 221.000 Future Volume Lower Limit: Future Volume Upper Limit: 100.000 LLW -Defense D&D W aste (from ER) Isotopes Americium-241 Avg Concentration: Low Limit Concent: Upper Limit Concent:8.1000E-002 nCi/m l Europium-152 Avg Concentration: Low Limit Concent: Upper Limit Concent:2.7000E-002 nCi/m l Plutonium-239 Avg Concentration: Low Limit Concent: Upper Limit Concent:2.7000E-001 nCi/m l Cobalt-60 Avg Concentration: Low Limit Concent: Upper Limit Concent:5.4000E+002 nCi/m

Note: This page contains sample records for the topic "non-hlw wds llw" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


221

Seagate Crystal Reports - RADCM  

Office of Environmental Management (EM)

Nevada Nevada SITE: Nevada PROGRAM: EM WASTE TYPE: Low Level Waste OPERATIONS OFFICE: Nevada Operations Office % of Stream Nevada - Low Level Waste - LLW Contaminated Soil (Industrial Sites Project) WASTE STREAM CODE: 01025 STREAM NAME:LLW Contaminated Soil (Industrial Sites Project) MPC NAME:Soil TOTAL CURIES: Approved Volume : Future Volume Avg: 243.000 Future Volume Lower Limit: Future Volume Upper Limit: 100.000 SAFER & Houskpng LLW Soil Isotopes Cesium-137 Avg Concentration: 1.0700E+006 Bq/m3 Low Limit Concent:2.4200E+004 Bq/m3 Upper Limit Concent:2.3400E+007 Bq/m3 Plutonium-238 Avg Concentration: 9.5000E+001 Bq/m3 Low Limit Concent:4.4400E-001 Bq/m3 Upper Limit Concent:1.2700E+003 Bq/m3 Cobalt-60 Avg Concentration: 5.2300E+004 Bq/m3 Low Limit Concent:2.7400E+003 Bq/m3

222

Application of spectral summing to indeterminate suspect low-level drums at Los Alamos National Laboratory  

Science Conference Proceedings (OSTI)

An analytical technique developed by Pajarito Scientific Corporation (PSC), utilizing spectral summing of spectra from groups of drums of similar waste type, is being employed by the Waste Disposition Project - Low Level Waste Disposal (WDP-LLWD) Group at Los Alamos National Laboratory (LANL). This technique has been used to disposition low-level radioactive waste that has dropped out of the transuranic (TRU) category and has no place to go unless it can be proven to be LLW and not TRU. The TRU program at LANL run by Mobile Characterization Services (MCS) employs two High Efficiency Neutron Counters (HENC) with built-in gamma assay systems to assay radioactive waste for shipment and disposal as TRU waste at the Waste Isolation Pilot Plant (WIPP) at Carlsbad, New Mexico. As well as being certified for WIPP assays, the HENC systems can also be used for low-level waste assays for disposal at LANL or off-site disposal facilities, such as the Nevada Test Site (NTS). Some of the waste processed through the HENC systems cannot be confinned TRU due to the absence of detected TRU alpha emitters above the TRU cutoff of 100 nCi/g. This waste becomes suspect low-level waste (SLLW). In many cases, the waste also can't be classified as LLW because the minimum detectable activity (MDA) of TRU radio nuclides is above the 100 nCi/g level. These wastes that do not have enough detectable TRU activity to be classified as TRU waste and have too high a MDA to be classified as LLW enter a radioactive waste characterization indetenninate status that prevents their dispositioning as either TRU waste or LLW. Spectral summing allows an experienced ganuna spectroscopy analyst to add the HENC gamma spectra of a number of similar waste items together to form a consolidated (summed) spectrum. This summed spectrum contains the assay results of the group of items rather than the individual item, and gamma peaks that were not discernable in the individual spectra can become quantifiable in the summed spectrum and the MDA for group sum is reduced. The group of waste items can then be properly classified as LLW based on the summed spectrum and valid assay values can be assigned for disposal. This technique has been successfully applied to a set of 52 debris drums - with individual MDA > 100 nCi/g - with a resulting group total TRU alpha activity concentration below 40nCi/g. Further application of the technique at LANL to other waste drums that are measured on a WIPP certified HENC system is planned and good candidate drum sets are being evaluated as indeterminate situations develop.

Gruetzmacher, Kathleen M [Los Alamos National Laboratory; Veilleux, John M [Los Alamos National Laboratory; Lucero, Randy P [PAJARITO SCIENTIFIC CORAPTION; Seamans, Jr., James V [PAJARITO SCIENTIFIC CORPORATION; Clapham, Martin J [PAJARITO SCIENTIFIC CORPORATION

2010-11-09T23:59:59.000Z

223

Conditions For Successful Helium Detonations In Astrophysical Environments  

E-Print Network (OSTI)

Several models for type Ia-like supernovae events rely on the production of a self-sustained detonation powered by nuclear reactions.In the absence of hydrogen, the fuel that powers these detonations typically consists of either pure helium (He) or a mixture of carbon and oxygen (C/O). Studies that systematically determine the conditions required to initiate detonations in C/O material exist, but until now no analogous investigation of degenerate He matter has been conducted. We perform one-dimensional reactive hydrodynamical simulations at a variety of initial density and temperature combinations and find critical length scales for the initiation of He detonations that range between 1 -- $10^{10}$ cm. These sizes are consistently smaller than the corresponding Chapman-Jouguet (CJ) length scales by a factor of ~100, providing opportunities for thermonuclear explosions in a wider range of low mass white dwarfs (WDs) than previously thought possible. We find that virialized WDs with as little mass as 0.24 $M_\\o...

Holcomb, Cole; De Colle, Fabio; Ramirez-Ruiz, Enrico

2013-01-01T23:59:59.000Z

224

SPITZER 24 {mu}m IMAGES OF PLANETARY NEBULAE  

SciTech Connect

Spitzer MIPS 24 {mu}m images were obtained for 36 Galactic planetary nebulae (PNe) whose central stars are hot white dwarfs (WDs) or pre-WDs with effective temperatures of {approx}100,000 K or higher. Diffuse 24 {mu}m emission is detected in 28 of these PNe. The eight nondetections are angularly large PNe with very low H{alpha} surface brightnesses. We find three types of correspondence between the 24 {mu}m emission and H{alpha} line emission of these PNe: six show 24 {mu}m emission more extended than H{alpha} emission, nine have a similar extent at 24 {mu}m and H{alpha}, and 13 show diffuse 24 {mu}m emission near the center of the H{alpha} shell. The sizes and surface brightnesses of these three groups of PNe and the nondetections suggest an evolutionary sequence, with the youngest ones being brightest and the most evolved ones undetected. The 24 {mu}m band emission from these PNe is attributed to [O IV] 25.9 {mu}m and [Ne V] 24.3 {mu}m line emission and dust continuum emission, but the relative contributions of these three components depend on the temperature of the central star and the distribution of gas and dust in the nebula.

Chu, Y.-H.; Gruendl, Robert A.; Bilikova, Jana; Caulet, Adeline [Department of Astronomy, University of Illinois at Urbana-Champaign, 1002 West Green Street, Urbana, IL 61801 (United States); Guerrero, Martin A. [Instituto de Astrofisica de Andalucia, CSIC. c/ Camino Bajo de Huetor 50, E-18008 Granada (Spain); Su, Kate Y. L. [Stewart Observatory, University of Arizona, Tucson, AZ 85721 (United States); Cohen, Martin [Radio Astronomy Laboratory, University of California, Berkeley, CA 94720 (United States); Parker, Quentin A. [Department of Physics, Macquarie University, Sydney, NSW 2109 (Australia); Volk, Kevin [Space Telescope Science Institute, 3700 San Martin Drive, Baltimore, MD 21218 (United States); Chen, W.-P. [Institute of Astronomy, National Central University, Chung-Li, Taiwan (China); Hora, Joseph L. [Center for Astrophysics, 60 Garden Street, MS 65, Cambridge, MA 02138 (United States); Rauch, Thomas [Institut fuer Astronomie und Astrophysik Tuebingen (IAAT), Abteilung Astronomie, Sand 1, D-72076 Tuebingen (Germany)], E-mail: chu@astro.uiuc.edu

2009-08-15T23:59:59.000Z

225

TIDAL INTERACTIONS IN MERGING WHITE DWARF BINARIES  

SciTech Connect

The recently discovered system J0651 is the tightest known detached white dwarf (WD) binary. Since it has not yet initiated Roche-lobe overflow, it provides a relatively clean environment for testing our understanding of tidal interactions. I investigate the tidal heating of each WD, parameterized in terms of its tidal Q parameter. Assuming that the heating can be radiated efficiently, the current luminosities are consistent with Q {sub 1} {approx} 7 x 10{sup 10} and Q {sub 2} {approx} 2 x 10{sup 7}, for the He and C/O WDs, respectively. Conversely, if the observed luminosities are merely from the cooling of the WDs, these estimated values of Q represent the upper limits. A large Q {sub 1} for the He WD means its spin velocity will be slower than that expected if it was tidally locked, which, since the binary is eclipsing, may be measurable via the Rossiter-McLaughlin effect. After one year, gravitational wave emission shifts the time of eclipses by 5.5 s, but tidal interactions cause the orbit to shrink more rapidly, changing the time by up to an additional 0.3 s after a year. Future eclipse timing measurements may therefore infer the degree of tidal locking.

Piro, Anthony L., E-mail: piro@caltech.edu [Theoretical Astrophysics, California Institute of Technology, 1200 East California Boulevard, M/C 350-17, Pasadena, CA 91125 (United States)

2011-10-20T23:59:59.000Z

226

INNER EDGES OF COMPACT DEBRIS DISKS AROUND METAL-RICH WHITE DWARFS  

SciTech Connect

A number of metal-rich white dwarfs (WDs) are known to host compact, dense particle disks, which are thought to be responsible for metal pollution of these stars. In many such systems, the inner radii of disks inferred from their spectra are so close to the WD that particles directly exposed to starlight must be heated above 1500 K and are expected to be unstable against sublimation. To reconcile this expectation with observations, we explore particle sublimation in H-poor debris disks around WDs. We show that because of the high metal vapor pressure the characteristic sublimation temperature in these disks is 300-400 K higher than in their protoplanetary analogs, allowing particles to survive at higher temperatures. We then look at the structure of the inner edges of debris disks and show that they should generically feature superheated inner rims directly exposed to starlight with temperatures reaching 2500-3500 K. Particles migrating through the rim toward the WD (and rapidly sublimating) shield the disk behind them from strong stellar heating, making the survival of solids possible close to the WD. Our model agrees well with observations of WD+disk systems provided that disk particles are composed of Si-rich material such as olivine, and have sizes in the range {approx}0.03-30 cm.

Rafikov, Roman R.; Garmilla, Jose A., E-mail: rrr@astro.princeton.edu, E-mail: garmilla@astro.princeton.edu [Department of Astrophysical Sciences, Princeton University, Ivy Lane, Princeton, NJ 08540 (United States)

2012-12-01T23:59:59.000Z

227

Operational and Regulatory Performance of Waste Crate Assay Systems at RFETS  

SciTech Connect

As Rocky Flats Environmental Technology Site (RFETS) approaches its closure target of 2006 emphasis for Non-Destructive Assay (NDA) has shifted from small waste package assay systems towards larger systems that are designed to accommodate Standard Waste Boxes (SWB) and larger Low Level Waste (LLW) containers. To this end, Kaiser Hill, with the support of BNFL Instruments, Inc. (BII) and Los Alamos National Laboratory (LANL), has recently deployed two new crate assay systems. These systems provide the capacity to meet the assay requirements associated with the Deactivation and Decommissioning (D&D) at RFETS. The Super High Efficiency Neutron Coincidence Counting System (SuperHENC) was designed and fabricated as a collaborative effort between RFETS, LANL and BII. The purpose of this counter is to provide a WIPP certified assay capability for SWBs with a sensitivity that allows for TRU/LLW sorting. The SuperHENC has been in operation since early 2001. The BII Multi-Purpose Crate Counter (MPCC) is based on the Imaging Passive Active Neutron (IPAN) technology. This counter was designed to provide diverse capacity for WIPP certified assay of SWBs and to provide assay capability for larger LLW crates that are generated at RFETS. The MPCC has been in operation since early 2002. In order to meet the requirement for measurement of the WIPP tracked radionuclides, both systems incorporate a BII Gamma Energy Analysis sub-system. The unique Energy Times Attenuation (ETA) method is used to provide isotopic mass fractions for diverse waste streams. These systems were the first, and at this time the only, waste crate assay systems that have achieved WIPP certification. This represents a significant achievement given that the performance criteria applied to the measurements of large crates is identical to the criteria for 55-gallon (208 liter) drums. They are now both fully operational at RFETS and continue to successfully support the site closure mission.

Clapham, M. J.; Franco, J.; Simpson, A.; Santo, J.; Menlove, H. O.; Durel, F. M.

2003-02-27T23:59:59.000Z

228

Operational and regulatory performance of waste crate assay systems at RFETS.  

SciTech Connect

As Rocky Flats Environmental Technology Site (RFETS) approaches its closure target of 2006 emphasis for Non-Destructive Assay (NDA) has shifted from small waste package assay systems towards larger systems that are designed to accommodate Standard Waste Boxes (SWB) and larger Low Level Waste (LLW) containers. To this end, Kaiser Hill, with the support of BNFL Instruments, Inc . (BIn) and Los Alamos National Laboratory (LANL), has recently deployed two new crate assay systems . These systems provide the capacity to meet the assay requirements associated with the Deactivation and Decommissioning (D&D) at RFETS . The Super High Efficiency Neutron Coincidence Counting System (SuperHENC) was designed and fabricated as a collaborative effort between RFETS, LANL and BII. The purpose of this counter is to provide a WIPP certified assay capability for SWBs with a sensitivity that allows for TRU/LLW sorting. The SuperHENC has been in operation since early 2001 . The BII Mu1ti-Purpose Crate Counter (MPCC) is based on the Imaging Passive Active Neutron (IPANTM) technology. This counter was designed to provide diverse capacity for WIPP certified assay of SWBs and to provide assay capability for larger LLW crates that are generated at RFETS. The MPCC h as been in operation since early 2002 . In order to meet the requirement for measurement of the WIPP tracked radionuclides, both systems incorporate a BII Gamma Energy Analysis sub-system . The unique Energy Times . Attenuation (ETA) method is used to provide isotopic mass fractions for diverse wastes treams: These systems were the first, and at this time the only, waste crate assay systems that have achieved WIPP certification. This represents a significant achievement given that the performance criteria applied to the measurements of large crates is identical to the criteria for 55-gallon (208 liter) drums . They are now both fully operational at RFETS and continue to successfully support the site closure mission .

Clapham, M. (Martin); Franco, J. B. (Johnna B.); Simpson, A.; Santo, J.; Menlove, Howard O.; Durel, F. M.

2003-01-01T23:59:59.000Z

229

Proposal for Construction/Demonstration/Implementation of A Material Handling System  

SciTech Connect

Vortec Corporation, the United States Enrichment Corporation (USEC) and DOE/Paducah propose to complete the technology demonstration and the implementation of the Material Handling System developed under Contract Number DE-AC21-92MC29120. The demonstration testing and operational implementation will be done at the Paducah Gaseous Diffusion Plant. The scope of work, schedule and cost for the activities are included in this proposal. A description of the facility to be constructed and tested is provided in Exhibit 1, attached. The USEC proposal for implementation at Paducah is presented in Exhibit 2, and the commitment letters from the site are included in Exhibit 3. Under our agreements with USEC, Bechtel Jacobs Corporation and DOE/Paducah, Vortec will be responsible for the construction of the demonstration facility as documented in the engineering design package submitted under Phase 4 of this contract on August 9, 2001. USEC will have responsibility for the demonstration testing and commercial implementation of the plant. The demonstration testing and initial commercial implementation of the technology will be achieved by means of a USEC work authorization task with the Bechtel Jacobs Corporation. The initial processing activities will include the processing of approximately 4,250 drums of LLW. Subsequent processing of LLW and TSCA/LLW will be done under a separate contract or work authorization task. To meet the schedule for commercial implementation, it is important that the execution of the Phase 4 project option for construction of the demonstration system be executed as soon as possible. The schedule we have presented herein assumes initiation of the construction phase by the end of September 2001. Vortec proposes to complete construction of the demonstration test system for an estimated cost of $3,254,422. This price is based on the design submitted to DOE/NETL under the Phase 4 engineering design deliverable (9 august 2001). The cost is subject to the assumptions and conditions identified in Section 6 of this proposal.

Jim Jnatt

2001-08-24T23:59:59.000Z

230

3-25-10_Final_Testimony_(Triay).pdf  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Activities to maintain safe, secure, and compliant operations within the EM complex Radioactive tank waste stabilization, treatment, and disposal SNF storage, receipt, and disposition SNM consolidation, processing, and disposition High priority groundwater remediation TRU waste and MLLW/LLW disposition Soil and groundwater remediation Excess facilities decontamination and decommissioning (D&D) EM's FY 2011 budget request funds radioactive liquid tank waste activities that are a large part of the cleanup challenge EM faces at its Hanford, Savannah River and Idaho sites allowing the program to progress on its tank waste retrieval commitments and fund construction on tank waste treatment facilities. The request also targets $60 million in

231

Waste Disposition Update by Christine Gelles  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Waste Disposition Update Waste Disposition Update Christine Gelles Associate Deputy Assistant Secretary for Waste Management (EM-30) EM SSAB Chairs Meeting Washington, DC 2 October 2012 www.em.doe.gov 2 o Waste Stream Highlights o DOE Transportation Update o Greater Than Class C (GTCC) Low Level Waste Environmental Impact Statement o Blue Ribbon Commission on America's Nuclear Future o Nuclear Regulatory Commission's LLW Regulatory Initiatives Discussion Topics www.em.doe.gov 3 Waste Stream Highlights www.em.doe.gov 4 o Within current budget outlook, it is especially critical that EM ensures safe, reliable and cost effective disposition paths exist. o The program's refocused organization and the detailed

232

Glass science tutorial: Lecture No. 7, Waste glass technology for Hanford  

SciTech Connect

This paper presents the details of the waste glass tutorial session that was held to promote knowledge of waste glass technology and how this can be used at the Hanford Reservation. Topics discussed include: glass properties; statistical approach to glass development; processing properties of nuclear waste glass; glass composition and the effects of composition on durability; model comparisons of free energy of hydration; LLW glass structure; glass crystallization; amorphous phase separation; corrosion of refractories and electrodes in waste glass melters; and glass formulation for maximum waste loading.

Kruger, A.A.

1995-07-01T23:59:59.000Z

233

Application of spectral summing to indeterminate suspect low-level drums at Los Alamos National Laboratory  

Science Conference Proceedings (OSTI)

The spectral summing technique developed by Pajarito Scientific Corporation (PSC) is a unique modeling technique that is being employed by the Waste Disposition Project - Low Level Waste Disposition (WDP-LLWD) Group at Los Alamos National Laboratory (LANL). This technique has been used to disposition low-level radioactive waste that has dropped out of the transuranic (TRU) category and has no disposal path unless it can be proven to be LLW and not TRU. The TRU program at LANL run by Mobile Characterization Services (MCS) employs High Efficiency Neutron Counters (HENC) with built-in gamma assay systems to assay radioactive waste for shipment and disposal as TRU waste at the Waste Isolation Pilot Plant (WIPP) at Carlsbad, New Mexico. As well as being certified for WIPP assays, the HENC systems can also be used for low-level waste assays for disposal at LANL or off-site disposal facilities, such as the Nevada Test Site (NTS). Some of the waste processed through the HENC systems cannot be confirmed TRU due to the absence of detected TRU alpha emitters above the TRU cutoff of 100 nCi/g. This waste becomes suspect low-level waste (SLLW). In many cases, the waste also can't be classified as LLW because the minimum detectable activity (MDA) of TRU radionuclides is above the 100 nCi/g level. These wastes that do not have enough detectable TRU activity to be classified as TRU waste and have TRU MDAs > 100nCi/g enter a radioactive waste characterization indeterminate state that prevents their dispositioning as either TRU waste or LLW. Spectral summing allows an experienced gamma spectroscopy analyst to add the HENC gamma spectra of a number of similar waste items together to form a consolidated (summed) spectrum. This summed spectrum contains the assay results of the group of items rather than the individual item, and gamma peaks that were not discemable in the individual spectra become quantifiable in the summed spectrum and the MDA for the group sum is reduced. The group of waste items can then be properly classified as LLW waste on the summed spectrum and valid assay values can be assigned for disposal. This technique has been successfully applied to a set of 52 debris drums - with individual MDA > 100nCi/g - with a resulting group total TRU alpha activity concentration below 40nCi/g. Further application of the technique at LANL to other debris drums and sludge drums that were measured on a WIPP certified HENe is planned and good candidate drum sets are being evaluated.

Gruetzmacher, Kathleen M [Los Alamos National Laboratory; Veilleux, John M [Los Alamos National Laboratory; Lucero, Randy P [PAJARITO SCIENTIFIC CORPORATION; Seamans, Jr, J. V. [PAJARITO SCIENTIFIC CORPATION; Clapham, M. J. [PAJARITO SCIENTIFIC CORPORATION

2011-01-27T23:59:59.000Z

234

Technology, Safety and Costs of Decommissioning a Reference Low-Level Waste Burial Ground. Appendices  

SciTech Connect

Safety and cost information are developed for the conceptual decommissioning of commercial low-level waste (LLW) burial grounds. Two generic burial grounds, one located on an arid western site and the other located on a humid eastern site, are used as reference facilities for the study. The two burial grounds are assumed to have the same site capacity for waste, the same radioactive waste inventory, and similar trench characteristics and operating procedures. The climate, geology. and hydrology of the two sites are chosen to be typical of real western and eastern sites. Volume 2 (Appendices) contains the detailed analyses and data needed to support the results given in Volume 1.

None

1980-06-01T23:59:59.000Z

235

Environmental assessment for Sandia National Laboratories/New Mexico offsite transportation of low-level radioactive waste  

Science Conference Proceedings (OSTI)

Sandia National Laboratories, New Mexico (SNL/NM) is managed and operated by Sandia Corporation, a Lockheed Martin Company. SNL/NM is located on land owned by the U.S. Department of Energy (DOE) within the boundaries of the Kirtland Air Force Base (KAFB) in Albuquerque, New Mexico. The major responsibilities of SNL/NM are the support of national security and energy projects. Low-level radioactive waste (LLW) is generated by some of the activities performed at SNL/NM in support of the DOE. This report describes potential environmental effects of the shipments of low-level radioactive wastes to other sites.

NONE

1996-09-01T23:59:59.000Z

236

Environmental Management FY 2006 Budget Request DRAFT  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Christine Gelles Christine Gelles Director of Disposal Operations Office of Environmental Management US Dept. of Energy, Environmental Management Program Waste Disposition Highlights Presentation for the Transportation External Coordination Working Group 24 July 2007 * EM leads DOE's complex-wide efforts to improve disposition planning and optimize waste disposition projects * DOE's waste management policy remains unchanged and DOE's Programmatic Waste Management Environmental Statement and Records of Decision are still valid * "National Disposition Strategies" refer to updated plans, tools and management actions needed to strengthen disposition projects and provide greater transparency to DOE sites, communities, stakeholders and regulators Introduction * LLW/MLLW - If practical, disposal on the site where generated

237

Microsoft PowerPoint - Marcinowski April 2010 (Rev3).ppt [Compatibility Mode]  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Waste and Materials Disposition Update Waste and Materials Disposition Update EM Site Specific Advisory Board Chairs Meeting Oak Ridge, Tennessee April 28, 2010 Frank Marcinowski Acting Chief Technical Officer and Deputy Assistant Secretary for Technical and Regulatory Support Office of Environmental Management Office of Environmental Management Outline for Discussion * EM radioactive waste management priorities, budget, and policy overview * Programmatic updates and challenges - LLW/MLLW disposition - TRU waste acceleration and progress - High level waste and used fuel management GTCC EIS - GTCC EIS - Mercury management EIS DOE's Radioactive Waste Management Priorities * Continue to manage waste inventories in a safe and compliant manner Add hi h i k t

238

EMSSAB CHAIRS  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

May 11, 2006 May 11, 2006 3:00 - 4:00 p.m. Participants Chairs/Representatives: Fernald Jim Bierer Hanford Todd Martin, Shelly Cimon, Susan Leckband, Eric Olds, Lynn Lefkoff Idaho Shannon Brennan, Lisa Aldrich, William Flanery Nevada Carla Sanda NNM J. D. Campbell, Menice Santistevan Oak Ridge Norm Mulvenon, Pete Osborne Paducah Jeannie Brandstetter Rocky Flats Gerald DePoorter, Ken Korkia Savannah River Gerri Flemming DOE representatives: EM-13 Melissa Nielson, Doug Frost, Patricia Atkinson-Brown EM-12 Christine Gelles OPENING REMARKS Melissa Nielson welcomed everyone. NEW BUSINESS Update on LLW and MLLW Strategy Christine Gelles, Director, Office of Commercial Disposition Options, provided the following information:

239

Maintenance Guide for DOE Low-Level Waste Disposal Facility  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

4 4 G Approved: XX-XX-XX IMPLEMENTATION GUIDE for use with DOE M 435.1-1 Maintenance Guide for U.S. Department of Energy Low-Level Waste Disposal Facility Performance Assessments and Composite Analyses U.S. DEPARTMENT OF ENERGY DOE G 435.1-4 i (and ii) DRAFT XX-XX-XX LLW Maintenance Guide Revision 0, XX-XX-XX Maintenance Guide for U.S. Department of Energy Low-Level Waste Disposal Facility Performance Assessments and Composite Analyses CONTENTS 1. INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 1.1 Purpose . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 1.2 Organization . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 1.3 Background . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 1.3.1 Objectives . . . . . . . . . . . . . . . . . . . . . . . . .

240

Activities and Accomplishments  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Activities and Accomplishments Denver * May 11, 2011 Working Groups * Financial Guidance * PSR Improvements * Notification * Communications Webinars * RFID Demonstration and TRANSCOM Enhancements - November 17, 2010 - ARG-US RFID/TRANSCOM Real-time Tracking System - TRANSCOM Enhancements * Communications for Waste Movements - February 24, 2011 - Mixed/LLW Forecast: Baseline Disposition Data and Waste Information Management System (WIMS) - Prospective Shipment Report Improvements Wiki Site * Resource for NTSF members - Information on NTSF meetings and webinars - Ad hoc working group call summaries and documents for review - Information on DOE and other federal agency activities (e.g., NRC rulemaking) * Private site that requires participants to "join" in

Note: This page contains sample records for the topic "non-hlw wds llw" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


241

TEC Meeting Summaries - February 2008 Presentations | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

February 2008 Presentations February 2008 Presentations TEC Meeting Summaries - February 2008 Presentations San Antonio, Texas Presentations (Feb. 6 - 7, 2008) Documents Available for Download Welcome & Introduction - Opening Remarks DOE Program Updates - OCREM Update DOE Program Updates - EM Update Plenary II - Evaluation of Short Line Railroads - Track Safety Standards Plenary II - Evaluation of Short Line Railroads - FRA Evaluation of Shortline Railroads Plenary III - Addressing Risk Perception - Discussion of OCRWM Issues Breakout Session - OCRWM Issues - SNF Transfers Breakout Session - OCRWM Issues - WIPP Update Breakout Session - OCRWM Issues - LLW Disposition and WIMS Update Breakout Session - TEC Direction and Priorities - TEC Directions Path Forward and Summaries - Path Forward Introduction

242

Format and Content Guide for DOE Low-Level Waste Disposal Facility  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

2 2 G Approved: XX-XX-XX IMPLEMENTATION GUIDE for use with DOE M 435.1-1 Format and Content Guide for U.S. Department of Energy Low-Level Waste Disposal Facility Performance Assessments and Composite Analyses U.S. DEPARTMENT OF ENERGY DOE G 435.1-2 i DRAFT XX-XX-XX LLW PA and CA Format and Content Guide Revision 0, XX-XX-XX Format and Content Guide for U.S. Department of Energy Low-Level Waste Disposal Facility Performance Assessments and Composite Analyses CONTENTS List of Tables . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . v List of Figures . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . v List of Acronyms and Abbreviations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . v PART A: INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

243

Sludge Mass Reduction Update  

NLE Websites -- All DOE Office Websites (Extended Search)

Preparations Preparations within the Tank Farm D. Bumgardner Liquid Waste Engineering Washington Savannah River Company 12 May 2009 2 Agenda Liquid Waste System Overview Sludge Characteristics Sludge Batch Planning Sludge Batch Preparation Sequence - Aluminum Dissolution - Sludge Washing - Sludge Batch Qualification/Acceptance Questions 3 Liquid Waste Processing at SRS ARP - Actinide Removal Process AFP - Actinide Finishing Process ASP - Actinide Strike Process CSS - Clarified Salt Solution CSSX - Caustic-side Solvent Extraction DDA - Deliquification, Dissolution, and Adjustment DSS - Decontaminated Salt Solution DWPF - Defense Waste Processing Facility ETP - Effluent Treatment Project GWSB - Glass Waste Storage Building HLW - High-Level Waste LLW - Low-Level Waste MCU - Modular CSSX Unit

244

Model tracking system for low-level radioactive waste disposal facilities: License application interrogatories and responses  

SciTech Connect

This report describes a model tracking system for a low-level radioactive waste (LLW) disposal facility license application. In particular, the model tracks interrogatories (questions, requests for information, comments) and responses. A set of requirements and desired features for the model tracking system was developed, including required structure and computer screens. Nine tracking systems were then reviewed against the model system requirements and only two were found to meet all requirements. Using Kepner-Tregoe decision analysis, a model tracking system was selected.

Benbennick, M.E.; Broton, M.S.; Fuoto, J.S.; Novgrod, R.L.

1994-08-01T23:59:59.000Z

245

Alpha low-level stored waste systems design study  

SciTech Connect

The Stored Waste System Design Study (SWSDS), commissioned by the Waste Technology Development Department at the Idaho National Engineering Laboratory (INEL), examines relative life-cycle costs associated with three system concepts for processing the alpha low-level waste (alpha-LLW) stored at the Radioactive Waste Management Complex`s Transuranic Storage Area at the INEL. The three system concepts are incineration/melting; thermal treatment/solidification; and sort, treat, and repackage. The SWSDS identifies system functional and operational requirements and assesses implementability; effectiveness; cost; and demonstration, testing, and evaluation (DT&E) requirements for each of the three concepts.

Feizollahi, F.; Teheranian, B. [Morrison Knudson Corp., San Francisco, CA (United States). Environmental Services Div.; Quapp, W.J. [EG and G Idaho, Inc., Idaho Falls, ID (United States)

1992-08-01T23:59:59.000Z

246

Alpha low-level stored waste systems design study  

SciTech Connect

The Stored Waste System Design Study (SWSDS), commissioned by the Waste Technology Development Department at the Idaho National Engineering Laboratory (INEL), examines relative life-cycle costs associated with three system concepts for processing the alpha low-level waste (alpha-LLW) stored at the Radioactive Waste Management Complex's Transuranic Storage Area at the INEL. The three system concepts are incineration/melting; thermal treatment/solidification; and sort, treat, and repackage. The SWSDS identifies system functional and operational requirements and assesses implementability; effectiveness; cost; and demonstration, testing, and evaluation (DT E) requirements for each of the three concepts.

Feizollahi, F.; Teheranian, B. (Morrison Knudson Corp., San Francisco, CA (United States). Environmental Services Div.); Quapp, W.J. (EG and G Idaho, Inc., Idaho Falls, ID (United States))

1992-08-01T23:59:59.000Z

247

Preliminary Project Execution Plan for the Remote-Handled Low-Level Waste Disposal Project  

Science Conference Proceedings (OSTI)

This preliminary project execution plan (PEP) defines U.S. Department of Energy (DOE) project objectives, roles and responsibilities of project participants, project organization, and controls to effectively manage acquisition of capital funds for construction of a proposed remote-handled low-level waste (LLW) disposal facility at the Idaho National Laboratory (INL). The plan addresses the policies, requirements, and critical decision (CD) responsibilities identified in DOE Order 413.3B, 'Program and Project Management for the Acquisition of Capital Assets.' This plan is intended to be a 'living document' that will be periodically updated as the project progresses through the CD process to construction and turnover for operation.

David Duncan

2011-05-01T23:59:59.000Z

248

Waste Class B/C Reduction Guide, Revision 1  

Science Conference Proceedings (OSTI)

Low level waste (LLW) Class B/C wet waste, including filter and ion exchange media, is one of the most expensive radioactive wastes routinely generated by U.S. commercial reactors8212up to a factor of 10 higher than lower activity waste streams. This report is a continuation of the EPRI initiative to evaluate techniques and technologies that reduce the generation and packaged volume of Class B/C wastes. In addition to reducing Class B/C waste generation, several techniques described in this study also su...

2011-11-23T23:59:59.000Z

249

Closure Strategy for a Waste Disposal Facility with Multiple Waste Types and Regulatory Drivers at the Nevada Test Site  

SciTech Connect

The U.S. Department of Energy, National Security Administration Nevada Site Office (NNSA/NSO) is planning to close the 92-Acre Area of the Area 5 Radioactive Waste Management Site (RWMS) at the Nevada Test Site (NTS), which is about 65 miles northwest of Las Vegas, Nevada. Closure planning for this facility must take into account the regulatory requirements for a diversity of waste streams, disposal and storage configurations, disposal history, and site conditions. This paper provides a brief background of the Area 5 RWMS, identifies key closure issues, and presents the closure strategy. Disposals have been made in 25 shallow excavated pits and trenches and 13 Greater Confinement Disposal (GCD) boreholes at the 92-Acre Area since 1961. The pits and trenches have been used to dispose unclassified low-level waste (LLW), low-level mixed waste (LLMW), and asbestiform waste, and to store classified low-level and low-level mixed materials. The GCD boreholes are intermediate-depth disposal units about 10 feet (ft) in diameter and 120 ft deep. Classified and unclassified high-specific activity LLW, transuranic (TRU), and mixed TRU are disposed in the GCD boreholes. TRU waste was also disposed inadvertently in trench T-04C. Except for three disposal units that are active, all pits and trenches are operationally covered with 8-ft thick alluvium. The 92-Acre Area also includes a Mixed Waste Disposal Unit (MWDU) operating under Resource Conservation and Recovery Act (RCRA) Interim Status, and an asbestiform waste unit operating under a state of Nevada Solid Waste Disposal Site Permit. A single final closure cover is envisioned over the 92-Acre Area. The cover is the evapotranspirative-type cover that has been successfully employed at the NTS. Closure, post-closure care, and monitoring must meet the requirements of the following regulations: U.S. Department of Energy Order 435.1, Title 40 Code of Federal Regulations (CFR) Part 191, Title 40 CFR Part 265, Nevada Administrative Code (NAC) 444.743, RCRA requirements as incorporated into NAC 444.8632, and the Federal Facility Agreement and Consent Order (FFACO). A grouping of waste disposal units according to waste type, location, and similarity in regulatory requirements identified six closure units: LLW Unit, Corrective Action Unit (CAU) 111 under FFACO, Asbestiform LLW Unit, Pit 3 MWDU, TRU GCD Borehole Unit, and TRU Trench Unit. The closure schedule of all units is tied to the closure schedule of the Pit 3 MWDU under RCRA.

L. Desotell; D. Wieland; V. Yucel; G. Shott; J. Wrapp

2008-03-01T23:59:59.000Z

250

The effect of vitrification technology on waste loading  

SciTech Connect

Radioactive wastes on the Hanford Site are going to be permanently disposed of by incorporation into a durable glass. These wastes will be separated into low and high-level portions, and then vitrified. The low-level waste (LLW) is water soluble. Its vitrifiable part (other than off-gas) contains approximately 80 wt% Na{sub 2}O, the rest being Al{sub 2}O{sub 3}, P{sub 2}O{sub 5}, K{sub 2}O, and minor components. The challenge is to formulate durable LLW glasses with as high Na{sub 2}O content as possible by optimizing the additions of SiO{sub 2}, Al{sub 2}O{sub 3}, B{sub 2}O{sub 3}, CaO, and ZrO{sub 2}. This task will not be simple, considering the non-linear and interactive nature of glass properties as a function of composition. Once developed, the LLW glass, being similar in composition to commercial glasses, is unlikely to cause major processing problems, such as crystallization or molten salt segregation. For example, inexpensive LLW glass can be produced in a high-capacity Joule-heated melter with a cold cap to minimize volatilization. The high-level waste (HLW) consists of water-insoluble sludge (Fe{sub 2}O{sub 3}, Al{sub 2}O{sub 3}, ZrO{sub 2}, Cr{sub 2}O{sub 3}, NiO, and others) and a substantial water-soluble residue (Na{sub 2}O). Most of the water-insoluble components are refractory; i.e., their melting points are above the glass melting temperature. With regard to product acceptability, the maximum loading of Hanford HLW in the glass is limited by product durability, not by radiolytic heat generation. However, this maximum may not be achievable because of technological constraints imposed by melter feed rheology, frit properties, and glass melter limits. These restrictions are discussed in this paper. 38 refs.

Hrma, P.R.; Smith, P.A.

1994-08-01T23:59:59.000Z

251

Interim Storage of Greater than Class C Low Level Waste, Rev. 1  

Science Conference Proceedings (OSTI)

This report serves as a guideline for the safe, interim on-site storage of low-level radioactive waste (LLW) that exceeds the activity limitations for near-surface disposal set forth in 10 CFR 61.55. The nuclear industry refers to this waste as "greater than Class C (GTTC) waste" as it exceeds the Class C limits in the referenced regulation. At the present time, there is no licensed disposal facility for GTCC waste in the United States . This situation forces commercial nuclear reactors to store it on si...

2003-07-23T23:59:59.000Z

252

Interim Storage of Greater Than Class C Low Level Waste  

Science Conference Proceedings (OSTI)

This report serves as a guideline for the safe, interim, on-site storage of low level radioactive waste (LLW) that exceeds the activity limitations for near-surface disposal set forth in 10 CFR 61.55. This waste, referred to as greater than Class C (GTCC) waste, exceeds the Class C limits in the referenced regulation. At the present time, there is no licensed disposal facility for GTCC waste in the United States. This situation forces commercial nuclear reactors to store it on site until a disposal facil...

2001-11-12T23:59:59.000Z

253

Nevada Test Site Waste Acceptance Criteria  

Science Conference Proceedings (OSTI)

This document establishes the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) waste acceptance criteria (WAC). The WAC provides the requirements, terms, and conditions under which the Nevada Test Site (NTS) will accept low-level radioactive (LLW) and mixed waste (MW) for disposal. It includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NTS Area 3 and Area 5 Radioactive Waste Management Complex (RWMC) for storage or disposal.

U. S. Department of Energy, National Nuclear Security Administration Nevada Site Office

2005-10-01T23:59:59.000Z

254

NEVADA TEST SITE WASTE ACCEPTANCE CRITERIA, JUNE 2006  

Science Conference Proceedings (OSTI)

This document establishes the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) waste acceptance criteria (WAC). The WAC provides the requirements, terms, and conditions under which the Nevada Test Site (NTS) will accept low-level radioactive (LLW) and mixed waste (MW) for disposal. It includes requirements for the generator waste certification program, characterization, traceability, waste form, packaging, and transfer. The criteria apply to radioactive waste received at the NTS Area 3 and Area 5 Radioactive Waste Management Complex (RWMC) for storage or disposal.

U.S. DEPARTMENT OF ENERGY, NATIONAL NUCLEAR SECURITY ADMINISTRATION NEVADA SITE OFFICE

2006-06-01T23:59:59.000Z

255

The Little Green Data Book | Open Energy Information  

Open Energy Info (EERE)

The Little Green Data Book The Little Green Data Book Jump to: navigation, search Tool Summary LAUNCH TOOL Name: The Little Green Data Book Agency/Company /Organization: World Bank Resource Type: Dataset Website: www-wds.worldbank.org/external/default/WDSContentServer/WDSP/IB/2010/0 References: The Little Green Data Book[1] Overview "The Little Green Data Book 2010 is a knowledge resource that aids policymakers in using environmental data more effectively to support priority-setting and improved development outcomes. It is a collaboration between the Development Data Group of the Development Economics Vice Presidency and the Environment Department of the Sustainable Development Vice Presidency of the World Bank. As we have every year for 10 years, we welcome your suggestions on how to improve future editions and make them

256

Mexico-Country Note on Climate Change Aspects in Agriculture | Open Energy  

Open Energy Info (EERE)

Mexico-Country Note on Climate Change Aspects in Agriculture Mexico-Country Note on Climate Change Aspects in Agriculture Jump to: navigation, search Name Mexico-Country Note on Climate Change Aspects in Agriculture Agency/Company /Organization World Bank Sector Land Focus Area Agriculture Topics Co-benefits assessment, Background analysis Resource Type Publications Website http://www-wds.worldbank.org/e Country Mexico UN Region Latin America and the Caribbean References Mexico-Country Note on Climate Change Aspects in Agriculture[1] Summary "Mexico is the only developing country to have submitted three national communications to the United Nations Framework Convention on Climate Change (UNFCCC), indicating strong commitment by the government for addressing climate change across sectors. Agriculture contributes little, in relative

257

A NEW TIMESCALE FOR PERIOD CHANGE IN THE PULSATING DA WHITE DWARF WD 0111+0018  

SciTech Connect

We report the most rapid rate of period change measured to date for a pulsating DA (hydrogen atmosphere) white dwarf (WD), observed in the 292.9 s mode of WD 0111+0018. The observed period change, faster than 10{sup -12} s s{sup -1}, exceeds by more than two orders of magnitude the expected rate from cooling alone for this class of slow and simply evolving pulsating WDs. This result indicates the presence of an additional timescale for period evolution in these pulsating objects. We also measure the rates of period change of nonlinear combination frequencies and show that they share the evolutionary characteristics of their parent modes, confirming that these combination frequencies are not independent modes but rather artifacts of some nonlinear distortion in the outer layers of the star.

Hermes, J. J.; Montgomery, M. H.; Winget, D. E. [Department of Astronomy, University of Texas at Austin, Austin, TX - 78712 (United States)] [Department of Astronomy, University of Texas at Austin, Austin, TX - 78712 (United States); Mullally, Fergal [SETI Institute, 189 Bernardo Avenue, Suite 100, Mountain View, CA 94043 (United States)] [SETI Institute, 189 Bernardo Avenue, Suite 100, Mountain View, CA 94043 (United States); Bischoff-Kim, A., E-mail: jjhermes@astro.as.utexas.edu [Chemistry, Physics and Astronomy Department, Georgia College and State University, Milledgeville, GA 31061 (United States)

2013-03-20T23:59:59.000Z

258

Development of an x-ray fluorescence microprobe at the National Synchrotron Light Source, Brookhaven National Laboratory: Early results: Comparison with data from other techniques  

SciTech Connect

Theoretical predictions for the detection levels in x-ray fluorescence analysis with a synchrotron storage ring are being achieved experimentally at several laboratories. This paper is deliberately restricted to the state of development of the Brookhaven National Laboratory/University of Chicago instruments. Analyses at the parts per million (ppM) level are being made using white light apertured to 20 ..mu..m and an energy dispersive system. This system is particularly useful for elements with Z > 20 in materials dominated by elements with Z < 20. Diffraction causes an interference for crystalline materials. Development of a focusing microprobe for tunable monochromatic x-rays and a wavelength dispersive spectrometer (WDS) is delayed by problems in shaping an 8:1 focusing mirror to the required accuracy. Reconnaissance analyses with a wiggler source on the CHESS synchrotron have been made in the K spectrum up to Z = 80.

Smith, J.V.; Rivers, M.L.; Sutton, S.R.; Jones, K.W.; Hanson, A.L.; Gordon, B.M.

1986-01-01T23:59:59.000Z

259

DO R CORONAE BOREALIS STARS FORM FROM DOUBLE WHITE DWARF MERGERS?  

SciTech Connect

A leading formation scenario for R Coronae Borealis (RCB) stars invokes the merger of degenerate He and CO white dwarfs (WDs) in a binary. The observed ratio of {sup 16}O/{sup 18}O for RCB stars is in the range of 0.3-20 much smaller than the solar value of {approx}500. In this paper, we investigate whether such a low ratio can be obtained in simulations of the merger of a CO and a He WD. We present the results of five three-dimensional hydrodynamic simulations of the merger of a double WD system where the total mass is 0.9 M{sub Sun} and the initial mass ratio (q) varies between 0.5 and 0.99. We identify in simulations with q {approx}< 0.7 a feature around the merged stars where the temperatures and densities are suitable for forming {sup 18}O. However, more {sup 16}O is being dredged up from the C- and O-rich accretor during the merger than the amount of {sup 18}O that is produced. Therefore, on the dynamical timescale over which our hydrodynamics simulation runs, an {sup 16}O/{sup 18}O ratio of {approx}2000 in the 'best' case is found. If the conditions found in the hydrodynamic simulations persist for 10{sup 6} s the oxygen ratio drops to 16 in one case studied, while in a hundred years it drops to {approx}4 in another case studied, consistent with the observed values in RCB stars. Therefore, the merger of two WDs remains a strong candidate for the formation of these enigmatic stars.

Staff, Jan. E.; Clayton, Geoffrey C.; Tohline, Joel E. [Department of Physics and Astronomy, Louisiana State University, 202 Nicholson Hall, Tower Drive, Baton Rouge, LA 70803-4001 (United States); Menon, Athira; Herwig, Falk [Department of Physics and Astronomy, University of Victoria, Victoria, BC V8P5C2 (Canada); Even, Wesley; Fryer, Chris L. [Los Alamos National Laboratory, Los Alamos, NM 87545 (United States); Motl, Patrick M. [Department of Science, Mathematics and Informatics, Indiana University Kokomo, Kokomo, IN 46904-9003 (United States); Geballe, Tom [Gemini Observatory, 670 North A'ohoku Place, Hilo, HI 96720 (United States); Pignatari, Marco [Department of Physics, University of Basel, Klingelbergstrasse 82, CH-4056 Basel (Switzerland)

2012-09-20T23:59:59.000Z

260

ZERO IMPACT PARAMETER WHITE DWARF COLLISIONS IN FLASH  

Science Conference Proceedings (OSTI)

We systematically explore zero impact parameter collisions of white dwarfs (WDs) with the Eulerian adaptive grid code FLASH for 0.64 + 0.64 M {sub Sun} and 0.81 + 0.81 M {sub Sun} mass pairings. Our models span a range of effective linear spatial resolutions from 5.2 Multiplication-Sign 10{sup 7} to 1.2 Multiplication-Sign 10{sup 7} cm. However, even the highest resolution models do not quite achieve strict numerical convergence, due to the challenge of properly resolving small-scale burning and energy transport. The lack of strict numerical convergence from these idealized configurations suggests that quantitative predictions of the ejected elemental abundances that are generated by binary WD collision and merger simulations should be viewed with caution. Nevertheless, the convergence trends do allow some patterns to be discerned. We find that the 0.64 + 0.64 M {sub Sun} head-on collision model produces 0.32 M {sub Sun} of {sup 56}Ni and 0.38 M {sub Sun} of {sup 28}Si, while the 0.81 + 0.81 M {sub Sun} head-on collision model produces 0.39 M {sub Sun} of {sup 56}Ni and 0.55 M {sub Sun} of {sup 28}Si at the highest spatial resolutions. Both mass pairings produce {approx}0.2 M {sub Sun} of unburned {sup 12}C+{sup 16}O. We also find the 0.64 + 0.64 M {sub Sun} head-on collision begins carbon burning in the central region of the stalled shock between the two WDs, while the more energetic 0.81 + 0.81 M {sub Sun} head-on collision raises the initial post-shock temperature enough to burn the entire stalled shock region to nuclear statistical equilibrium.

Hawley, W. P.; Athanassiadou, T.; Timmes, F. X., E-mail: Wendy.Hawley@asu.edu [School of Earth and Space Exploration, Arizona State University, Tempe, AZ 85287 (United States)

2012-11-01T23:59:59.000Z

Note: This page contains sample records for the topic "non-hlw wds llw" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
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We encourage you to perform a real-time search of NLEBeta
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261

CLAB Transuranic Waste Spreadsheets  

Science Conference Proceedings (OSTI)

The Building 772-F Far-Field Transuranic (TRU) Waste Counting System is used to measure the radionuclide content of waste packages produced at the Central Laboratory Facilities (CLAB). Data from the instrument are entered into one of two Excel spreadsheets. The waste stream associated with the waste package determines which spreadsheet is actually used. The spreadsheets calculate the necessary information required for completion of the Transuranic Waste Characterization Form (OSR 29-90) and the Radioactive Solid Waste Burial Ground Record (OSR 7-375 or OSR 7-375A). In addition, the spreadsheets calculate the associated Low Level Waste (LLW) stream information that potentially could be useful if the waste container is ever downgraded from TRU to LLW. The spreadsheets also have the capability to sum activities from source material added to a waste container after assay. A validation data set for each spreadsheet along with the appropriate results are also presented in this report for spreadsheet verification prior to each use.

Leyba, J.D.

2000-08-11T23:59:59.000Z

262

Vitrification treatment options for disposal of greater-than-Class-C low-level waste in a deep geologic repository  

SciTech Connect

The Department of Energy (DOE), in keeping with their responsibility under Public Law 99-240, the Low-Level Radioactive Waste Policy Amendments Act of 1985, is investigating several disposal options for greater-than-Class C low-level waste (GTCC LLW), including emplacement in a deep geologic repository. At the present time vitrification, namely borosilicate glass, is the standard waste form assumed for high-level waste accepted into the Civilian Radioactive Waste Management System. This report supports DOE`s investigation of the deep geologic disposal option by comparing the vitrification treatments that are able to convert those GTCC LLWs that are inherently migratory into stable waste forms acceptable for disposal in a deep geologic repository. Eight vitrification treatments that utilize glass, glass ceramic, or basalt waste form matrices are identified. Six of these are discussed in detail, stating the advantages and limitations of each relative to their ability to immobilize GTCC LLW. The report concludes that the waste form most likely to provide the best composite of performance characteristics for GTCC process waste is Iron Enriched Basalt 4 (IEB4).

Fullmer, K.S.; Fish, L.W.; Fischer, D.K.

1994-11-01T23:59:59.000Z

263

Integrated data base for 1993: US spent fuel and radioactive waste inventories, projections, and characteristics. Revision 9  

Science Conference Proceedings (OSTI)

The Integrated Data Base (IDB) Program has compiled historic data on inventories and characteristics of both commercial and DOE spent fuel; also, commercial and U.S. government-owned radioactive wastes through December 31, 1992. These data are based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. The information forecasted is consistent with the latest U.S. Department of Energy/Energy Information Administration (DOE/EIA) projections of U.S. commercial nuclear power growth and the expected DOE-related and private industrial and institutional (I/I) activities. The radioactive materials considered, on a chapter-by-chapter basis, are spent nuclear fuel, high-level waste (HLW), transuranic (TRU), waste, low-level waste (LLW), commercial uranium mill tailings, environmental restoration wastes, commercial reactor and fuel-cycle facility decommissioning wastes, and mixed (hazardous and radioactive) LLW. For most of these categories, current and projected inventories are given through the calendar-year (CY) 2030, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions. In addition, characteristics and current inventories are reported for miscellaneous radioactive materials that may require geologic disposal.

Klein, J.A.; Storch, S.N.; Ashline, R.C. [and others

1994-03-01T23:59:59.000Z

264

INNOVATIVE FOSSIL FUEL FIRED VITRIFICATION TECHNOLOGY FOR SOIL REMEDIATION  

SciTech Connect

This Summary Report summarizes the progress of Phases 3, 3A and 4 of a waste technology Demonstration Project sponsored under a DOE Environmental Management Research and Development Program and administered by the U.S. Department of Energy National Energy Technology Laboratory-Morgantown (DOE-NETL) for an ''Innovative Fossil Fuel Fired Vitrification Technology for Soil Remediation''. The Summary Reports for Phases 1 and 2 of the Program were previously submitted to DOE. The total scope of Phase 3 was to have included the design, construction and demonstration of Vortec's integrated waste pretreatment and vitrification process for the treatment of low level waste (LLW), TSCA/LLW and mixed low-level waste (MLLW). Due to funding limitations and delays in the project resulting from a law suit filed by an environmental activist and the extended time for DOE to complete an Environmental Assessment for the project, the scope of the project was reduced to completing the design, construction and testing of the front end of the process which consists of the Material Handling and Waste Conditioning (MH/C) Subsystem of the vitrification plant. Activities completed under Phases 3A and 4 addressed completion of the engineering, design and documentation of the Material Handling and Conditioning System such that final procurement of the remaining process assemblies can be completed and construction of a Limited Demonstration Project be initiated in the event DOE elects to proceed with the construction and demonstration testing of the MH/C Subsystem.

J. Hnat; L.M. Bartone; M. Pineda

2001-07-13T23:59:59.000Z

265

Soil characterization methods for unsaturated low-level waste sites  

SciTech Connect

To support a license application for the disposal of low-level radioactive waste (LLW), applicants must characterize the unsaturated zone and demonstrate that waste will not migrate from the facility boundary. This document provides a strategy for developing this characterization plan. It describes principles of contaminant flow and transport, site characterization and monitoring strategies, and data management. It also discusses methods and practices that are currently used to monitor properties and conditions in the soil profile, how these properties influence water and waste migration, and why they are important to the license application. The methods part of the document is divided into sections on laboratory and field-based properties, then further subdivided into the description of methods for determining 18 physical, flow, and transport properties. Because of the availability of detailed procedures in many texts and journal articles, the reader is often directed for details to the available literature. References are made to experiments performed at the Las Cruces Trench site, New Mexico, that support LLW site characterization activities. A major contribution from the Las Cruces study is the experience gained in handling data sets for site characterization and the subsequent use of these data sets in modeling studies.

Wierenga, P.J.; Young, M.H. (Arizona Univ., Tucson, AZ (United States). Dept. of Soil and Water Science); Gee, G.W.; Kincaid, C.T. (Pacific Northwest Lab., Richland, WA (United States)); Hills, R.G. (New Mexico State Univ., Las Cruces, NM (United States). Dept. of Mechanical Engineering); Nicholson, T.J.; Cady, R.E. (Nuclear Regulatory Commission, Washington, DC (United States))

1993-01-01T23:59:59.000Z

266

W-026 integrated engineering cold run operational test report for balance of plant (BOP)  

SciTech Connect

This Cold Run test is designed to demonstrate the functionality of systems necessary to move waste drums throughout the plant using approved procedures, and the compatibility of these systems to function as an integrated process. This test excludes all internal functions of the gloveboxes. In the interest of efficiency and support of the facility schedule, the initial revision of the test (rev 0) was limited to the following: Receipt and storage of eight overpacked drums, four LLW and four TRU; Receipt, routing, and staging of eleven empty drums to the process area where they will be used later in this test; Receipt, processing, and shipping of two verification drums (Route 9); Receipt, processing, and shipping of two verification drums (Route 1). The above listed operations were tested using the rev 0 test document, through Section 5.4.25. The document was later revised to include movement of all staged drums to and from the LLW and TRU process and RWM gloveboxes. This testing was performed using Sections 5.5 though 5.11 of the rev 1 test document. The primary focus of this test is to prove the functionality of automatic operations for all mechanical and control processes listed. When necessary, the test demonstrates manual mode operations as well. Though the gloveboxes are listed, only waste and empty drum movement to, from, and between the gloveboxes was tested.

Kersten, J.K.

1998-02-24T23:59:59.000Z

267

Advanced Fuel Cycle Cost Basis  

SciTech Connect

This report, commissioned by the U.S. Department of Energy (DOE), provides a comprehensive set of cost data supporting a cost analysis for the relative economic comparison of options for use in the Advanced Fuel Cycle Initiative (AFCI) Program. The report describes the AFCI cost basis development process, reference information on AFCI cost modules, a procedure for estimating fuel cycle costs, economic evaluation guidelines, and a discussion on the integration of cost data into economic computer models. This report contains reference cost data for 25 cost modules23 fuel cycle cost modules and 2 reactor modules. The cost modules were developed in the areas of natural uranium mining and milling, conversion, enrichment, depleted uranium disposition, fuel fabrication, interim spent fuel storage, reprocessing, waste conditioning, spent nuclear fuel (SNF) packaging, long-term monitored retrievable storage, near surface disposal of low-level waste (LLW), geologic repository and other disposal concepts, and transportation processes for nuclear fuel, LLW, SNF, transuranic, and high-level waste.

D. E. Shropshire; K. A. Williams; W. B. Boore; J. D. Smith; B. W. Dixon; M. Dunzik-Gougar; R. D. Adams; D. Gombert; E. Schneider

2008-03-01T23:59:59.000Z

268

Advanced Fuel Cycle Cost Basis  

SciTech Connect

This report, commissioned by the U.S. Department of Energy (DOE), provides a comprehensive set of cost data supporting a cost analysis for the relative economic comparison of options for use in the Advanced Fuel Cycle Initiative (AFCI) Program. The report describes the AFCI cost basis development process, reference information on AFCI cost modules, a procedure for estimating fuel cycle costs, economic evaluation guidelines, and a discussion on the integration of cost data into economic computer models. This report contains reference cost data for 26 cost modules24 fuel cycle cost modules and 2 reactor modules. The cost modules were developed in the areas of natural uranium mining and milling, conversion, enrichment, depleted uranium disposition, fuel fabrication, interim spent fuel storage, reprocessing, waste conditioning, spent nuclear fuel (SNF) packaging, long-term monitored retrievable storage, near surface disposal of low-level waste (LLW), geologic repository and other disposal concepts, and transportation processes for nuclear fuel, LLW, SNF, and high-level waste.

D. E. Shropshire; K. A. Williams; W. B. Boore; J. D. Smith; B. W. Dixon; M. Dunzik-Gougar; R. D. Adams; D. Gombert

2007-04-01T23:59:59.000Z

269

Evaluation of Groundwater Impacts to Support the National Environmental Policy Act Environmental Assessment for the INL Remote-Handled Low-Level Waste Disposal Project  

Science Conference Proceedings (OSTI)

The groundwater impacts have been analyzed for the proposed RH-LLW disposal facility. A four-step analysis approach was documented and applied. This assessment compared the predicted groundwater ingestion dose to the more restrictive of either the 25 mrem/yr all pathway dose performance objective, or the maximum contaminant limit performance objective. The results of this analysis indicate that the groundwater impacts for either proposed facility location are expected to be less than the performance objectives. The analysis was prepared to support the NEPA-EA for the top two ranking of the proposed RH-LLW sites. As such, site-specific conditions were incorporated for each set of results generated. These site-specific conditions were included to account for the transport of radionuclides through the vadose zone and through the aquifer at each site. Site-specific parameters included the thickness of vadose zone sediments and basalts, moisture characteristics of the sediments, and aquifer velocity. Sorption parameters (Kd) were assumed to be very conservative values used in Track II analysis of CERCLA sites at INL. Infiltration was also conservatively assumed to represent higher rates corresponding to disturbed soil conditions. The results of this analysis indicate that the groundwater impacts for either proposed facility location are expected to be less than the performance objectives.

Annette Schafer; Arthur S. Rood; A. Jeffrey Sondrup

2011-12-01T23:59:59.000Z

270

Hazard Classification of the Remote Handled Low-Level Waste Disposal Facility  

Science Conference Proceedings (OSTI)

The Battelle Energy Alliance (BEA) at the Idaho National Laboratory (INL) is constructing a new facility to replace remote-handled low-level radioactive waste disposal capability for INL and Naval Reactors Facility operations. Current disposal capability at the Radioactive Waste Management Complex (RWMC) will continue until the facility is full or closed for remediation (estimated at approximately fiscal year 2015). Development of a new onsite disposal facility is the highest ranked alternative and will provide RH-LLW disposal capability and will ensure continuity of operations that generate RH-LLW for the foreseeable future. As a part of establishing a safety basis for facility operations, the facility will be categorized according to DOE-STD-1027-92. This classification is important in determining the scope of analyses performed in the safety basis and will also dictate operational requirements of the completed facility. This paper discusses the issues affecting hazard classification in this nuclear facility and impacts of the final hazard categorization.

Boyd D. Christensen

2012-05-01T23:59:59.000Z

271

Evaluation of Groundwater Impacts to Support the National Environmental Policy Act Environmental Assessment for the INL Remote-Handled Low-Level Waste Disposal Project  

Science Conference Proceedings (OSTI)

The groundwater impacts have been analyzed for the proposed RH-LLW disposal facility. A four-step analysis approach was documented and applied. This assessment compared the predicted groundwater ingestion dose to the more restrictive of either the 25 mrem/yr all pathway dose performance objective, or the maximum contaminant limit performance objective. The results of this analysis indicate that the groundwater impacts for either proposed facility location are expected to be less than the performance objectives. The analysis was prepared to support the NEPA-EA for the top two ranking of the proposed RH-LLW sites. As such, site-specific conditions were incorporated for each set of results generated. These site-specific conditions were included to account for the transport of radionuclides through the vadose zone and through the aquifer at each site. Site-specific parameters included the thickness of vadose zone sediments and basalts, moisture characteristics of the sediments, and aquifer velocity. Sorption parameters (Kd) were assumed to be very conservative values used in Track II analysis of CERCLA sites at INL. Infiltration was also conservatively assumed to represent higher rates corresponding to disturbed soil conditions. The results of this analysis indicate that the groundwater impacts for either proposed facility location are expected to be less than the performance objectives.

Annette Schafer; Arthur S. Rood; A. Jeffrey Sondrup

2011-08-01T23:59:59.000Z

272

The potential for criticality following disposal of uranium at low-level waste facilities: Uranium blended with soil  

SciTech Connect

The purpose of this study was to evaluate whether or not fissile uranium in low-level-waste (LLW) facilities can be concentrated by hydrogeochemical processes to permit nuclear criticality. A team of experts in hydrology, geology, geochemistry, soil chemistry, and criticality safety was formed to develop achievable scenarios for hydrogeochemical increases in concentration of special nuclear material (SNM), and to use these scenarios to aid in evaluating the potential for nuclear criticality. The team`s approach was to perform simultaneous hydrogeochemical and nuclear criticality studies to (1) identify some achievable scenarios for uranium migration and concentration increase at LLW disposal facilities, (2) model groundwater transport and subsequent concentration increase via sorption or precipitation of uranium, and (3) evaluate the potential for nuclear criticality resulting from potential increases in uranium concentration over disposal limits. The analysis of SNM was restricted to {sup 235}U in the present scope of work. The outcome of the work indicates that criticality is possible given established regulatory limits on SNM disposal. However, a review based on actual disposal records of an existing site operation indicates that the potential for criticality is not a concern under current burial practices.

Toran, L.E.; Hopper, C.M.; Naney, M.T. [and others

1997-06-01T23:59:59.000Z

273

Advanced Fuel Cycle Cost Basis  

SciTech Connect

This report, commissioned by the U.S. Department of Energy (DOE), provides a comprehensive set of cost data supporting a cost analysis for the relative economic comparison of options for use in the Advanced Fuel Cycle Initiative (AFCI) Program. The report describes the AFCI cost basis development process, reference information on AFCI cost modules, a procedure for estimating fuel cycle costs, economic evaluation guidelines, and a discussion on the integration of cost data into economic computer models. This report contains reference cost data for 25 cost modules23 fuel cycle cost modules and 2 reactor modules. The cost modules were developed in the areas of natural uranium mining and milling, conversion, enrichment, depleted uranium disposition, fuel fabrication, interim spent fuel storage, reprocessing, waste conditioning, spent nuclear fuel (SNF) packaging, long-term monitored retrievable storage, near surface disposal of low-level waste (LLW), geologic repository and other disposal concepts, and transportation processes for nuclear fuel, LLW, SNF, transuranic, and high-level waste.

D. E. Shropshire; K. A. Williams; W. B. Boore; J. D. Smith; B. W. Dixon; M. Dunzik-Gougar; R. D. Adams; D. Gombert; E. Schneider

2009-12-01T23:59:59.000Z

274

A radiological and chemical investigation of the 7500 Area Contamination Site at Oak Ridge National Laboratory, Oak Ridge, Tennessee  

Science Conference Proceedings (OSTI)

A radiological and chemical investigation of the 7500 Area Contamination Site at Oak Ridge National Laboratory (ORNL) was conducted intermittently from February 1992 through May 1992. The investigation was performed by the Measurement Applications and Development Group of the Health and Safety Research Division of ORNL at the request of the US Department of Energy`s Oak Ridge Operations Office and the ORNL Environmental Restoration Program. Results of this investigation indicate that the source of radioactive contamination at the point of the contamination incident is from one of the underground abandoned lines. The contamination in soil is likely the result of residual contamination from years of waste transport and maintenance operations (e.g., replacement of degraded joints, upgrading or replacement of entire pipelines, and associated landscaping activities). However, because (1) there is currently an active LLW line positioned in the same subsurface trench with the abandoned lines and (2) the physical condition of the abandoned lines may be brittle, this inquiry could not determine which abandoned line was responsible for the subsurface contamination. Soil sampling at the location of the contamination incident and along the pipeline route was performed in a manner so as not to damage the active LLW line and abandoned lines. Recommendations for corrective actions are included.

Williams, J.K.; Foley, R.D.; Tiner, P.F.; Hatmaker, T.L.; Uziel, M.S.; Swaja, R.E.

1993-05-01T23:59:59.000Z

275

Separation of strontium-90 from Hanford high-level radioactive waste  

SciTech Connect

Current guidelines for disposing of high-level radioactive wastes stored in underground tanks at the US Department of Energy`s Hanford Site call for vitrifying high-level waste (HLW) in borosilicate glass and disposing the glass canisters in a deep geologic repository. Disposition of the low-level waste (LLW) is yet to be determined, but it will likely be immobilized in a glass matrix and disposed of on site. To lower the radiological risk associated with the LLW form, methods are being developed to separate {sup 90}Sr from the bulk waste material so this isotope can be routed to the HLW stream. A solvent extraction method is being investigated to separate {sup 90}Sr from acid-dissolved Hanford tank wastes. Results of experiments with actual tank waste indicate that this method can be used to achieve separation of {sup 90}Sr from the bulk waste components. Greater than 99% of the {sup 90}Sr was removed from an acidic dissolved sludge solution by extraction with di-tbutylcyclohexano-18-crown-6 in 1-octanol (the SREX process). The major sludge components were not extracted.

Lumetta, G.J.; Wagner, M.J.; Jones, E.O.

1993-10-01T23:59:59.000Z

276

Low-level radioactive waste transportation safety history  

SciTech Connect

The Radioactive Materials Incident Report (RMIR) database was developed fin 1981 at the Transportation Technology Center of Sandia National Laboratories to support its research and development activities for the US department of Energy (DOE). This database contains information about radioactive material (RAM) transportation incidents that have occurred in the US since 1971. These data were drawn from the US Department of Transportation`s (DOT) Hazardous Materials Incident Report system, from Nuclear Regulatory Commission (NRC) files, and from various agencies including state radiological control offices. Support for the RMIR data base is funded by the US DOE National Transportation Program (NTP). Transportation events in RMIR are classified in one of the following ways: as a transportation accident, as a handling accident, or as a reported incident. This presentation will provide definitions for these classifications and give examples of each. The primary objective of this presentation is to provide information on nuclear materials transportation accident/incident events involving low-level waste (LLW) that have occurred in the US for the period 1971 through 1996. Among the areas to be examined are: transportation accidents by mode, package response during accidents, and an examination of accidents where release of contents has occurred. Where information is available, accident and incident history and package response for LLW packages in transportation accidents will be described.

McClure, J.D. [Sandia National Labs., Albuquerque, NM (United States). Transportation Systems Analysis Dept.

1997-08-01T23:59:59.000Z

277

Integration of health physics, safety and operational processes for management and disposition of recycled uranium wastes at the Fernald Environmental Management Project (FEMP)  

Science Conference Proceedings (OSTI)

Fluor Fernald, Inc. (Fluor Fernald), the contractor for the U. S. Department of Energy (DOE) Fernald Environmental Management Project (FEMP), recently submitted a new baseline plan for achieving site closure by the end of calendar year 2006. This plan was submitted at DOE's request, as the FEMP was selected as one of the sites for their accelerated closure initiative. In accordance with the accelerated baseline, the FEMP Waste Management Project (WMP) is actively evaluating innovative processes for the management and disposition of low-level uranium, fissile material, and thorium, all of which have been classified as waste. These activities are being conducted by the Low Level Waste (LLW) and Uranium Waste Disposition (UWD) projects. Alternatives associated with operational processing of individual waste streams, each of which poses potentially unique health physics, industrial hygiene and industrial hazards, are being evaluated for determination of the most cost effective and safe met hod for handling and disposition. Low-level Mixed Waste (LLMW) projects are not addressed in this paper. This paper summarizes historical uranium recycling programs and resultant trace quantity contamination of uranium waste streams with radionuclides, other than uranium. The presentation then describes how waste characterization data is reviewed for radiological and/or chemical hazards and exposure mitigation techniques, in conjunction with proposed operations for handling and disposition. The final part of the presentation consists of an overview of recent operations within LLW and UWD project dispositions, which have been safely completed, and a description of several current operations.

Barber, James; Buckley, James

2003-02-23T23:59:59.000Z

278

DOE site performance assessment activities. Radioactive Waste Technical Support Program  

Science Conference Proceedings (OSTI)

Information on performance assessment capabilities and activities was collected from eight DOE sites. All eight sites either currently dispose of low-level radioactive waste (LLW) or plan to dispose of LLW in the near future. A survey questionnaire was developed and sent to key individuals involved in DOE Order 5820.2A performance assessment activities at each site. The sites surveyed included: Hanford Site (Hanford), Idaho National Engineering Laboratory (INEL), Los Alamos National Laboratory (LANL), Nevada Test Site (NTS), Oak Ridge National Laboratory (ORNL), Paducah Gaseous Diffusion Plant (Paducah), Portsmouth Gaseous Diffusion Plant (Portsmouth), and Savannah River Site (SRS). The questionnaire addressed all aspects of the performance assessment process; from waste source term to dose conversion factors. This report presents the information developed from the site questionnaire and provides a comparison of site-specific performance assessment approaches, data needs, and ongoing and planned activities. All sites are engaged in completing the radioactive waste disposal facility performance assessment required by DOE Order 5820.2A. Each site has achieved various degrees of progress and have identified a set of critical needs. Within several areas, however, the sites identified common needs and questions.

Not Available

1990-07-01T23:59:59.000Z

279

Tank Waste Remediation System tank waste pretreatment and vitrification process development testing requirements assessment  

Science Conference Proceedings (OSTI)

A multi-faceted study was initiated in November 1993 to provide assurance that needed testing capabilities, facilities, and support infrastructure (sampling systems, casks, transportation systems, permits, etc.) would be available when needed for process and equipment development to support pretreatment and vitrification facility design and construction schedules. This first major report provides a snapshot of the known testing needs for pretreatment, low-level waste (LLW) and high-level waste (HLW) vitrification, and documents the results of a series of preliminary studies and workshops to define the issues needing resolution by cold or hot testing. Identified in this report are more than 140 Hanford Site tank waste pretreatment and LLW/HLW vitrification technology issues that can only be resolved by testing. The report also broadly characterizes the level of testing needed to resolve each issue. A second report will provide a strategy(ies) for ensuring timely test capability. Later reports will assess the capabilities of existing facilities to support needed testing and will recommend siting of the tests together with needed facility and infrastructure upgrades or additions.

Howden, G.F.

1994-10-24T23:59:59.000Z

280

Nevada National Security Site Waste Acceptance Criteria  

SciTech Connect

This document establishes the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Field Office (NNSA/NFO), Nevada National Security Site Waste Acceptance Criteria (NNSSWAC). The NNSSWAC provides the requirements, terms, and conditions under which the Nevada National Security Site (NNSS) will accept the following: ? DOE hazardous and non-hazardous non-radioactive classified waste ? DOE low-level radioactive waste (LLW) ? DOE mixed low-level waste (MLLW) ? U.S. Department of Defense (DOD) classified waste The LLW and MLLW listed above may also be classified waste. Classified waste is the only waste accepted for disposal that may be non-radioactive and shall be required to meet the waste acceptance criteria for radioactive waste as specified in this document. Classified waste may be sent to the NNSS as classified matter. Section 3.1.18 provides the requirements that must be met for permanent burial of classified matter. The NNSA/NFO and support contractors are available to assist the generator in understanding or interpreting this document. For assistance, please call the NNSA/NFO Environmental Management Operations (EMO) at (702) 295-7063, and the call will be directed to the appropriate contact.

none,

2013-06-01T23:59:59.000Z

Note: This page contains sample records for the topic "non-hlw wds llw" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


281

Closure Strategy for a Waste Disposal Facility with Multiple Waste Types and Regulatory Drivers at the Nevada Test Site  

SciTech Connect

The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) plans to close the waste and classified material storage cells in the southeast quadrant of the Area 5 Radioactive Waste Management Site (RWMS), informally known as the '92-Acre Area', by 2011. The 25 shallow trenches and pits and the 13 Greater Confinement Disposal (GCD) borings contain various waste streams including low-level waste (LLW), low-level mixed waste (LLMW), transuranic (TRU), mixed transuranic (MTRU), and high specific activity LLW. The cells are managed under several regulatory and permit programs by the U.S. Department of Energy (DOE) and the Nevada Division of Environmental Protection (NDEP). Although the specific closure requirements for each cell vary, 37 closely spaced cells will be closed under a single integrated monolayer evapotranspirative (ET) final cover. One cell will be closed under a separate cover concurrently. The site setting and climate constrain transport pathways and are factors in the technical approach to closure and performance assessment. Successful implementation of the integrated closure plan requires excellent communication and coordination between NNSA/NSO and the regulators.

D. Wieland, V. Yucel, L. Desotell, G. Shott, J. Wrapp

2008-04-01T23:59:59.000Z

282

A West Valley Demonstration Project Milestone - Achieving Certification to Ship Waste to the Nevada Test Site  

SciTech Connect

The West Valley Demonstration Project (WVDP) has successfully pretreated and vitrified nearly all of the 600,000 gallons of liquid high-level radioactive waste that was generated at the site of the only commercial nuclear fuel reprocessing plant to have operated in the United States. Low-level waste (LLW) generated during the course of the cleanup effort now requires disposal. Currently the WVDP only ships Class A LLW for off-site disposal. It has been shipping Class A wastes to Envirocare of Utah, Inc. since 1997. However, the WVDP may also have a future need to ship Class B and Class C waste, which Envirocare is not currently authorized to accept. The Nevada Test Site (NTS), a U.S. Department of Energy (DOE) facility, can accept all three waste classifications. The WVDP set a goal to receive certification to begin shipping Class A wastes to NTS by 2001. Formal certification/approval was granted by the DOE Nevada Operations Office on July 12, 2001. This paper discusses how the WVDP contractor, West Valley Nuclear Services Company (WVNSCO), completed the activities required to achieve NTS certification in 2001 to ship waste to its facility. The information and lessons learned provided are significant because the WVDP is the only new generator receiving certification based on an NTS audit in January 2001 that resulted in no findings and only two observations--a rating that is unparalleled in the DOE Complex.

Jackson, J. P.; Pastor, R. S.

2002-02-28T23:59:59.000Z

283

Seagate Crystal Reports - Rad94  

Office of Environmental Management (EM)

Annual Projections for Shipping and Receiving (RAD-9) Annual Projections for Shipping and Receiving (RAD-9) RECEIVING SITE: Hanford WASTE TYPE: Low Level Waste STATE: California Hanford - Low Level Waste - Offsite Cat 1 LLW from LEHR Non-Annualized 2016-20(P) 2008(P) 2009(P) 2010(P) 2061-65(P) 2066-70(P) 2056-60(P) 2007 (P) 2041-45(P) 2004 (P) 2005 (P) 2021-25(P) 2026-30(P) 2031-35(P) 2036-40(P) 2006 (P) 2011-15(P) 2003 (P) Shipped (m 3 ) Year 1998 (A) 1999 (A) 2000 (A) 2001 (P) 2002 (P) 2051-55(P) Year Shipped (m 3 ) Year 2046-50(P) Shipped (m 3 ) Shipped (m 3 ) Shipped (m 3 ) Year Year EnerHlthLb 0.640 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Hanford - Low Level Waste - Offsite Cat 1 LLW from ETEC Non-Annualized 2016-20(P) 2008(P) 2009(P) 2010(P) 2061-65(P) 2066-70(P)

284

Seagate Crystal Reports - RADCM  

Office of Environmental Management (EM)

Annual Projections for Shipping and Receiving (RAD/CM-9) Annual Projections for Shipping and Receiving (RAD/CM-9) Data Category: Combined Radioactive Waste and Ex-Situ Contaminated Media RECEIVING SITE: Hanford WASTE TYPE: Low Level Waste STATE: California Hanford - Low Level Waste - Offsite Cat 1 LLW from LEHR 2051-55(P) Year Shipped (m 3 ) Year 2046-50(P) Shipped (m 3 ) Shipped (m 3 ) Shipped (m 3 ) Year Year Shipped (m 3 ) Year 1998 (A) 1999 (A) 2000 (A) 2001 (P) 2002 (P) 2041-45(P) 2004 (P) 2005 (P) 2021-25(P) 2026-30(P) 2031-35(P) 2036-40(P) 2006 (P) 2011-15(P) 2003 (P) Non-Annualized 2016-20(P) 2008(P) 2009(P) 2010(P) 2061-65(P) 2066-70(P) 2056-60(P) 2007 (P) EnerHlthLb 0.640 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 Hanford - Low Level Waste - Offsite Cat 1 LLW from ETEC

285

Improvements in Container Management of Transuranic and Low-Level Radioactive Waste Stored at the Central Waste Complex at Hanford  

Science Conference Proceedings (OSTI)

The Central Waste Complex (CWC) is the interim storage facility for Resource Conservation and Recovery Act (RCRA) mixed waste, transuranic waste, transuranic mixed waste, low-level and low-level mixed radioactive waste at the Department of Energy's (DOE's) Hanford Site. The majority of the waste stored at the facility is retrieved from the low-level burial grounds in the 200 West Area at the Site, with minor quantities of newly generated waste from on-site and offsite waste generators. The CWC comprises 18 storage buildings that house 13,000 containers. Each waste container within the facility is scanned into its location by building, module, tier and position and the information is stored in a site-wide database. As waste is retrieved from the burial grounds, a preliminary non-destructive assay is performed to determine if the waste is transuranic (TRU) or low-level waste (LLW) and subsequently shipped to the CWC. In general, the TRU and LLW waste containers are stored in separate locations within the CWC, but the final disposition of each waste container is not known upon receipt. The final disposition of each waste container is determined by the appropriate program as process knowledge is applied and characterization data becomes available. Waste containers are stored within the CWC based on their physical chemical and radiological hazards. Further segregation within each building is done by container size (55-gallon, 85-gallon, Standard Waste Box) and waste stream. Due to this waste storage scheme, assembling waste containers for shipment out of the CWC has been time consuming and labor intensive. Qualitatively, the ratio of containers moved to containers in the outgoing shipment has been excessively high, which correlates to additional worker exposure, shipment delays, and operational inefficiencies. These inefficiencies impacted the LLW Program's ability to meet commitments established by the Tri-Party Agreement, an agreement between the State of Washington, the Department of Energy, and the Environmental Protection Agency. These commitments require waste containers to be shipped off site for disposal and/or treatment within a certain time frame. Because the program was struggling to meet production demands, the Production and Planning group was tasked with developing a method to assist the LLW Program in fulfilling its requirements. Using existing databases for container management, a single electronic spreadsheet was created to visually map every waste container within the CWC. The file displays the exact location (e.g., building, module, tier, position) of each container in a format that replicates the actual layout in the facility. In addition, each container was placed into a queue defined by the LLW and TRU waste management programs. The queues were developed based on characterization requirements, treatment type and location, and potential final disposition. This visual aid allows the user to select containers from similar queues and view their location within the facility. The user selects containers in a centralized location, rather than random locations, to expedite shipments out of the facility. This increases efficiency for generating the shipments, as well as decreasing worker exposure and container handling time when gathering containers for shipment by reducing movements of waste containers. As the containers are collected for shipment, the remaining containers are segregated by queue, which further reduces future container movements. (authors)

Uytioco, E. [Fluor Government Group, Richland, WA (United States); Baynes, P.A.; Bailey, K.B.; McKenney, D.E. [Fluor Hanford, Inc., Richland WA (United States)

2008-07-01T23:59:59.000Z

286

IMPROVEMENTS IN CONTAINER MANAGEMENT OF TRANSURANIC (TRU) AND LOW LEVEL RADIOACTIVE WASTE STORED AT THE CENTRAL WASTE COMPLEX (CWC) AT HANFORD  

Science Conference Proceedings (OSTI)

The Central Waste Complex (CWC) is the interim storage facility for Resource Conservation & Recovery Act (RCRA) mixed waste, transuranic waste, transuranic mixed waste, low-level and low-level mixed radioactive waste at the Department of Energy's (DOE'S) Hanford Site. The majority of the waste stored at the facility is retrieved from the low-level burial grounds in the 200 West Area at the Site, with minor quantities of newly generated waste from on-site and off-site waste generators. The CWC comprises 18 storage buildings that house 13,000 containers. Each waste container within the facility is scanned into its location by building, module, tier and position and the information is stored in a site-wide database. As waste is retrieved from the burial grounds, a preliminary non-destructive assay is performed to determine if the waste is transuranic (TRU) or low-level waste (LLW) and subsequently shipped to the CWC. In general, the TRU and LLW waste containers are stored in separate locations within the CWC, but the final disposition of each waste container is not known upon receipt. The final disposition of each waste container is determined by the appropriate program as process knowledge is applied and characterization data becomes available. Waste containers are stored within the CWC based on their physical chemical and radiological hazards. Further segregation within each building is done by container size (55-gallon, 85-gallon, Standard Waste Box) and waste stream. Due to this waste storage scheme, assembling waste containers for shipment out of the CWC has been time consuming and labor intensive. Qualitatively, the ratio of containers moved to containers in the outgoing shipment has been excessively high, which correlates to additional worker exposure, shipment delays, and operational inefficiencies. These inefficiencies impacted the LLW Program's ability to meet commitments established by the Tri-Party Agreement, an agreement between the State of Washington, the Department of Energy, and the Environmental Protection Agency. These commitments require waste containers to be shipped off site for disposal and/or treatment within a certain time frame. Because the program was struggling to meet production demands, the Production and Planning group was tasked with developing a method to assist the LLW Program in fulfilling its requirements. Using existing databases for container management, a single electronic spreadsheet was created to visually map every waste container within the CWC. The file displays the exact location (e.g., building, module, tier, position) of each container in a format that replicates the actual layout in the facility. In addition, each container was placed into a queue defined by the LLW and TRU waste management programs. The queues were developed based on characterization requirements, treatment type and location, and potential final disposition. This visual aid allows the user to select containers from similar queues and view their location within the facility. The user selects containers in a centralized location, rather than random locations, to expedite shipments out of the facility. This increases efficiency for generating the shipments, as well as decreasing worker exposure and container handling time when gathering containers for shipment by reducing movements of waste container. As the containers are collected for shipment, the remaining containers are segregated by queue, which further reduces future container movements.

UYTIOCO EM

2007-11-14T23:59:59.000Z

287

West Valley Melter Draft Waste Evaluation Released for Public Comment |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Melter Draft Waste Evaluation Released for Public Melter Draft Waste Evaluation Released for Public Comment West Valley Melter Draft Waste Evaluation Released for Public Comment March 11, 2011 - 12:00pm Addthis Media Contact Bill Taylor (513) 246-0539 william.taylor@emcbc.doe.gov West Valley, New York - The U.S. Department of Energy today released a Draft Waste Incidental to Reprocessing (WIR) Evaluation of a vitrification melter at the West Valley Demonstration Project (WVDP) for review and comment by the public, states and Nuclear Regulatory Commission (NRC). This draft evaluation shows that the melter meets the criteria for "waste incidental to reprocessing" and may be managed and disposed of as low-level radioactive waste (LLW). It is an important step in DOE's efforts to clean up the WVDP and meet its obligations under the WVDP Act of

288

EIS-0286: Draft Environmental Impact Statement | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Draft Environmental Impact Statement Draft Environmental Impact Statement EIS-0286: Draft Environmental Impact Statement Hanford Site Solid (Radioactive and Hazardous) Waste Program, Richland, Washington DOE needs to provide capabilities to continue, or modify, the way it treats, stores, and/or disposes of existing and anticipated quantities of solid LLW, MLLW, TRU waste, and ILAW at the Hanford Site in order to protect human health and the environment; facilitate cleanup at Hanford and other DOE facilities; take actions consistent with decisions reached by DOE under the WM PEIS; comply with local, State, and federal laws and regulations; and meet other obligations such as the Hanford Federal Facility Agreement and Consent Order (also referred to as the Tri-Party Agreement, or TPA) (Ecology et al. 1989).

289

Slide 1  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

site history, site history, cleanup status, and role of the West Valley Citizen Task Force Raymond C. Vaughan, Ph.D. West Valley Citizen Task Force DOE National Transportation Stakeholders Forum Buffalo, May 16, 2013 WEST VALLEY SITE * Only U.S. commercial reprocessing plant (1966-1972) * Owned by NY State; operated by Nuclear Fuel Services * Reprocessed both defense and commercial spent fuel * High worker exposures, poor control of contaminants during period of operation prior to 1980 * Sited on erosion-prone land (glacial fill) in the Great Lakes watershed, about 50 km (30 mi) south of Buffalo * Two onsite burial grounds operated 1963-1975; hold wastes exceeding 10 CFR 61 limits * Onsite source term includes HLW, TRU, LLW, mixed waste (roughly 16 million curies current total)

290

Microsoft PowerPoint - Freeze.NE PA Overview_052511.ppt  

NLE Websites -- All DOE Office Websites (Extended Search)

Used Fuel Disposition Campaign Used Fuel Disposition Campaign Summary of DOE-NE PA Modeling for Storage and Disposal of Used Nuclear Fuel (UNF), High-Level Radioactive Waste (HLW), and Low-Level Waste (LLW) Geoff Freeze Sandia National Laboratories PA Community of Practice Technical Exchange May 25-26, 2011 Print Close Used Fuel Disposition 2 DOE-Nuclear Energy (NE) - PA Modeling Activities NE Advanced Modeling and Simulation (NEAMS) Waste Integrated Performance and Safety Codes (Waste IPSC) Used Fuel Disposition (UFD) Generic Performance Assessment Model (GPAM) *** Initial modeling focus in both campaigns in on UNF/HLW disposal Print Close Used Fuel Disposition 3  UFD GPAM  Short time horizon (2-3 yrs) - Simplified generic system models (i.e., PA-fidelity using GoldSim) - Current computing capabilities

291

EIS-0283-SA-02: Supplement Analysis | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

2: Supplement Analysis 2: Supplement Analysis EIS-0283-SA-02: Supplement Analysis Surplus Plutonium Dispostion Program: Waste Solidification Building The National Nuclear Security Administration (NNSA), a separately organized agency within the U.S. Department of Energy (DOE), is proposing to construct and operate a standalone Waste Solidification Building 1 (WSR) in F-Area at the Savannah River Site (SRS) near Aiken, South Carolina. Certain liquid low-level radioactive waste (LLW) and liquid transuranic (TRU) waste expected to be generated in the Mixed Oxide Fuel Fabrication Facility (MFFF) and Pit Disassembly and Conversion Facility (PDCF) as part of the U.S. Surplus Plutonium Disposition Program would be treated and solidified in WSB. DOE/EIS-0283, National Nuclear Security Administration, Supplement Analysis

292

Microsoft Word - SSABchairs.conferencecall.december15.012506rev31.doc  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

December 15, 2005 December 15, 2005 3:00 - 4:30 p.m. Participants Chairs/Representatives: Fernald Sue Walpole Hanford Todd Martin Idaho David Kipping, Shannon Brennan, Lisa Aldrich Nevada Kathleen Peterson NNM J.D. Campbell, Grace Perez Oak Ridge Norm Mulvenon, Rhonda Bogard, Pete Osborne, Spencer Gross Paducah Jeannie Brandstetter Rocky Flats Gerald DePoorter, Ken Korkia Savannah River Jean Sulc, Gerri Fleming DOE representatives: EM-30.1 Melissa Nielson, Doug Frost, Patricia Atkinson-Brown OPENING REMARKS Melissa Nielson welcomed everyone. NEW BUSINESS Update on LLW and MLLW Strategy Christine Gelles, Director, Office of Commercial Disposition Options, passed along the thanks of Frank Marcinowski, Deputy Assistant Secretary for Logistics and Waste Disposition Enhancements, to the Nevada Board for its support in getting the permit

293

EIS-0283-SA-02: Supplement Analysis | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

3-SA-02: Supplement Analysis 3-SA-02: Supplement Analysis EIS-0283-SA-02: Supplement Analysis Surplus Plutonium Dispostion Program: Waste Solidification Building The National Nuclear Security Administration (NNSA), a separately organized agency within the U.S. Department of Energy (DOE), is proposing to construct and operate a standalone Waste Solidification Building 1 (WSR) in F-Area at the Savannah River Site (SRS) near Aiken, South Carolina. Certain liquid low-level radioactive waste (LLW) and liquid transuranic (TRU) waste expected to be generated in the Mixed Oxide Fuel Fabrication Facility (MFFF) and Pit Disassembly and Conversion Facility (PDCF) as part of the U.S. Surplus Plutonium Disposition Program would be treated and solidified in WSB. DOE/EIS-0283, National Nuclear Security Administration, Supplement Analysis

294

EIS-0287: Notice of Preferred Sodium Bearing Waste Treatment Technology |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Preferred Sodium Bearing Waste Treatment Preferred Sodium Bearing Waste Treatment Technology EIS-0287: Notice of Preferred Sodium Bearing Waste Treatment Technology Idaho High-Level Waste (HLW) and Facilities Disposition In October 2002, the U.S. Department of Energy (DOE or the Department) issued the Final Idaho High-Level Waste (HLW) and Facilities Disposition Environmental Impact Statement (DOE/EIS-0287 (Final EIS)). The Final EIS contains an evaluation of reasonable alternatives for the management of mixed transuranic waste/sodium bearing waste (SBW),1 mixed HLW calcine, and associated low-level waste (LLW), as well as disposition alternatives for HLW facilities when their missions are completed. DOE/EIS-0287, Notice of Preferred Sodium Bearing Waste Treatment Technology, Office of Environmental Management, Idaho, 70 FR 44598 (August

295

Page not found | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

21 - 11230 of 29,416 results. 21 - 11230 of 29,416 results. Download CX-008178: Categorical Exclusion Determination Clinch River Environmental Studies Organization (CRESO) Partners Wetland Project CX(s) Applied: B3.3, B3.8 Date: 03/30/2012 Location(s): Tennessee Offices(s): Oak Ridge Office http://energy.gov/nepa/downloads/cx-008178-categorical-exclusion-determination Page LFRG DOE Order 435.1 Chapter 4 of the DOE Manual on Order 435.1, Low-level Waste Requirements, addresses the procedures whereby Department of Energy LLW Disposal Facilities will operated and maintained. Section P and... http://energy.gov/em/lfrg-doe-order-4351 Page Impact Assessments PIA Template with Guidance (MS Word) http://energy.gov/cio/office-chief-information-officer/services/guidance/privacy/impact-assessments

296

West Valley  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Nuclear Facility Nuclear Facility Coalition on West Valley Nuclear Wastes PO Box 603 Springville NY 14141 WV-DigItUp@roadrunner.com Joanne Hameister CFMT (Concentrator Feed Make-up Tank) Packaged 13'x14'x19' 177.5 tons MFHT (Melter Feed Hold Tank) Packaged 13'x14'x16' 152.5 tons WIR Shipments pending to LLW facility MELTER 10'x10'x10' Packaged: 14'x13'x13' 159 tons 4,570 Curies Waste Categories High-Level Waste Based on source * Nuclear Fuel * Reprocessing * TRU Low-Level Waste Not Low Risk Complex classification based on * Nuclide inventory * Half-life(s) * Quantity * Decay products Background Radiation 1978 - average was 100 mRem per person 2011 - BRC* estimate 620 mRem per person Naturally occurring radioactive elements Additions accumulate - from fall-out,

297

National Transportation Stakeholders Forum  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

TRANSPORTATION STAKEHOLDERS TRANSPORTATION STAKEHOLDERS FORUM Activities and Accomplishments May 16, 2013 Buffalo, New York NTSF RESOURCES  Wiki Site  Private domain / Registration required  Repository of information  Users are allowed editing capabilities  Webinars  Cover a variety of topics (NRC Rulemaking, Section 180(c), BRC Recommendations, Strategy for Management and Disposal of UNF and HLRW, etc.)  Recording are available on the wiki site  Input is needed for future content NTSF Working Groups COMMUNICATIONS WORKING GROUP  Webinars  Development Guide  LLW Fact Sheet  Table of Waste Types  New Fact Sheets  Newsletter  NFSTPP Communications Products TEPP WORKING GROUP  Formed a TEPP Working Group after the 2012 NTSF to

298

Final Environmental Assessment for Waste Disposition Activities at the Paducah Site Paducah, Kentucky  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

0-347(doc)/093002 0-347(doc)/093002 1 FINDING OF NO SIGNIFICANT IMPACT WASTE DISPOSITION ACTIVITIES AT THE PADUCAH SITE PADUCAH, KENTUCKY AGENCY: U.S. DEPARTMENT OF ENERGY ACTION: FINDING OF NO SIGNIFICANT IMPACT SUMMARY: The U.S. Department of Energy (DOE) has completed an environmental assessment (DOE/EA-1339), which is incorporated herein by reference, for proposed disposition of polychlorinated biphenyl (PCB) wastes, low-level radioactive waste (LLW), mixed low- level radioactive waste (MLLW), and transuranic (TRU) waste from the Paducah Gaseous Diffusion Plant Site (Paducah Site) in Paducah, Kentucky. All of the wastes would be transported for disposal at various locations in the United States. Based on the results of the impact analysis reported in the EA, DOE has determined that the proposed action is

299

EA-1793: Replacement Capability for Disposal of Remote-handled Low-level  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

793: Replacement Capability for Disposal of Remote-handled 793: Replacement Capability for Disposal of Remote-handled Low-level Waste Generated at the Department of Energy's Idaho Site EA-1793: Replacement Capability for Disposal of Remote-handled Low-level Waste Generated at the Department of Energy's Idaho Site Summary This EA evaluates the environmental impacts of replacement capability for disposal of remote-handled low-level radioactive waste (LLW) generated at the Idaho National Laboratory (INL) site beginning in October 2017. Public Comment Opportunities Submit Comments to: Mr. Chuck Ljungberg 1955 Fremont Avenue, Mailstop 1216 Idaho Falls, ID 83415 Electronic mail: rhllwea@id.doe.gov Documents Available for Download December 21, 2011 EA-1793: Finding of No Significant Impact Replacement Capability for Disposal of Remote-Handled Low-Level Radioactive

300

Format and Content Guide for DOE Low-Level Waste Disposal Facility Closure Plans  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

3 3 G Approved: XX-XX-XX IMPLEMENTATION GUIDE for use with DOE M 435.1-1 Format and Content Guide for U.S. Department of Energy Low-Level Waste Disposal Facility Closure Plans U.S. DEPARTMENT OF ENERGY DOE G 435.1-3 i DRAFT XX-XX-XX LLW Closure Plan Format and Content Guide Revision 0, XX-XX-XX Format and Content Guide for U.S. Department of Energy Low-Level Waste Disposal Facility Closure Plans CONTENTS PART A: INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 1. PURPOSE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 2. ORGANIZATION OF DOCUMENT . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 3. BACKGROUND . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 3.1 Closure Objectives and Relationship to Other Programs . . . . . . . . . . . . . . . . . . . . . . 2 3.2

Note: This page contains sample records for the topic "non-hlw wds llw" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


301

Slide 1  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Update for the Transportation Update for the Transportation External Coordination Working Group Ella McNeil Office of Transportation, EM-63 2 * www.casacappellino.com * djashw@yahoo.com 3 EM Shipments Continue. . . * LLW & MLLW shipments continue from WVDP, OR, and Mound * MOX shipments from Hanford to ID 4 Uranium Oxide Transportation Logistics * Each uranium oxide cylinder will weigh ~14-18 tons. * 11 railcars are planned to be shipped each week. - Group of 5 or 6 railcars will be shipped from each site - Each gondola railcar will contain up to 6 cylinders 5 Update of DOE Manual 460.2-1 * Formal review ended April 2007 * Comment resolution is complete * Manual is in formal concurrence process - All program offices - Nonconcurrence from GC * Working to address issues

302

Composite analysis E-area vaults and saltstone disposal facilities  

Science Conference Proceedings (OSTI)

This report documents the Composite Analysis (CA) performed on the two active Savannah River Site (SRS) low-level radioactive waste (LLW) disposal facilities. The facilities are the Z-Area Saltstone Disposal Facility and the E-Area Vaults (EAV) Disposal Facility. The analysis calculated potential releases to the environment from all sources of residual radioactive material expected to remain in the General Separations Area (GSA). The GSA is the central part of SRS and contains all of the waste disposal facilities, chemical separations facilities and associated high-level waste storage facilities as well as numerous other sources of radioactive material. The analysis considered 114 potential sources of radioactive material containing 115 radionuclides. The results of the CA clearly indicate that continued disposal of low-level waste in the saltstone and EAV facilities, consistent with their respective radiological performance assessments, will have no adverse impact on future members of the public.

Cook, J.R.

1997-09-01T23:59:59.000Z

303

Page not found | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

61 - 23770 of 31,917 results. 61 - 23770 of 31,917 results. Page EA-0821: Operation of the Glass Melter Thermal Treatment Unit at the U.S. Department of Energy's Mound Plant, Miamisburg, Ohio This EA evaluates the environmental impacts of a proposal to use an existing glass melter thermal treatment unit (also known as a Penberthy Pyro-Converter joule-heated glass furnace) for the... http://energy.gov/nepa/ea-0821-operation-glass-melter-thermal-treatment-unit-us-department-energys-mound-plant Page EA-0843: Idaho National Engineering Laboratory Low-Level and Mixed Waste Processing, Idaho Falls, Idaho This EA evaluates the environmental impacts of a proposal to (1) reduce the volume of the U.S. Department of Energy's Idaho National Engineering Laboratory's (INEL) generated low-level waste (LLW)...

304

Slide 1  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

site history, site history, cleanup status, and role of the West Valley Citizen Task Force Raymond C. Vaughan, Ph.D. West Valley Citizen Task Force DOE National Transportation Stakeholders Forum Buffalo, May 16, 2013 WEST VALLEY SITE * Only U.S. commercial reprocessing plant (1966-1972) * Owned by NY State; operated by Nuclear Fuel Services * Reprocessed both defense and commercial spent fuel * High worker exposures, poor control of contaminants during period of operation prior to 1980 * Sited on erosion-prone land (glacial fill) in the Great Lakes watershed, about 50 km (30 mi) south of Buffalo * Two onsite burial grounds operated 1963-1975; hold wastes exceeding 10 CFR 61 limits * Onsite source term includes HLW, TRU, LLW, mixed waste (roughly 16 million curies current total)

305

Page not found | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

01 - 11110 of 26,764 results. 01 - 11110 of 26,764 results. Download EIS-0285-SA-38: Supplement Analysis Transmission System Vegetation Management Program http://energy.gov/nepa/downloads/eis-0285-sa-38-supplement-analysis Download LFRG Charter The Low - Level Waste (LLW) Disposal Facility Federal Review Group (LFRG) Cliarter identifies the purpose, objectives, and membership requirements of the group. http://energy.gov/em/downloads/lfrg-charter Download SPR Pro Forma Contract An exchange agreement for SPR oil involves return of the principal amount of similar quality crude oil to the SPR, plus payment of an in-kind premium determined according to the period negotiated... http://energy.gov/fe/downloads/spr-pro-forma-contract Download FY_09_DM_RM_AM_Reporting_Memo_and_attachment_072009.pdf

306

Microsoft PowerPoint - Benson LP PA CoP Summer 2011.pptx  

NLE Websites -- All DOE Office Websites (Extended Search)

CRESP DOE LANDFILL PARTNERSHIP CRESP DOE LANDFILL PARTNERSHIP Craig H. Benson, PhD, PE, DGE Wisconsin Distinguished Professor Geological Engineering University of Wisconsin-Madison www.cresp.org 26 May 2011 1 Print Close Hanford's ERDF Print Close W A S T E A C C E S S R O A D On-Site Disposal Facility (OSDF): aka LLW or MW Landfill Final Cover System Liner System MONITORING WELLS Figure courtesy M. Othman, Geosyntec Consultants Print Close Purpose of Landfill Partnership 4 * Conduct independent applied research to address landfill technology issues that cross- cut the DOE complex. * Provide forum to discuss regulatory conflicts and shortcomings, and to recommend technological solutions. * Participate in independent technical reviews related to DOE technologies or sites.

307

Performance Assessment Community of Practice  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

L L l W t C t B d High-Level Waste Corporate Board Performance Assessment Community of Practice Community of Practice John E. Marra, Ph.D. Associate Laboratory Director Associate Laboratory Director 5 March 2009 DOE EM HLW Corporate Board Meeting Phoenix, Arizona DOE-EM HLW Corporate Board Meeting Performance Assessment Process Community of Practice Background EM Senior Management would like to have g improved consistency in the execution of the Performance Assessment* process; Originally formed a sub-committee to draft a guidance document for practitioners; Th b itt b li C it f The sub-committee now believes a Community of Practice having broader scope should replace it; Draft Charter in review and presented for Draft Charter in review and presented for discussion. * Performance Assessment (PA) is used broadly to encompass assessments for LLW

308

Introduction  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

-- -- September 2005 1 What's Happening in EM? Ella McNeil Office of Transportation, EM-11 TEC -- September 2005 2 Cleanup and waste disposition continue. . . * Continuing progress toward site closures * Disposition of "orphan" or special waste streams are some of the remaining obstacles to closure * Working with sites to develop comprehensive lists of these streams and to identify needed treatment and disposal options * Identification of disposal facility - commercial or Federal * Ability to continue to accelerate cleanup is directly dependent on the ability to ship and dispose of waste safely TEC -- September 2005 3 Current DOE/EM Waste Management Policy * LLW and MLLW: * If practical, disposal at generation site * If on-site disposal not available, then disposal at another

309

DRAFT EM SSAB Chairs Meeting Waste Disposition Strategies Update  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

EM HQ Updates Waste Disposition Overview Christine Gelles Associate Deputy Assistant Secretary for Waste Management Office of Environmental Management EM SSAB Chairs Meeting 5 November 2013 www.energy.gov/EM 2 * Waste Management Accomplishments and Priorities * National TRU Program Update * LLW/MLLW Disposal Update * Other Programmatic Updates * Disposition Maps - Current Tools Discussion Outline www.energy.gov/EM 3 FY13 Waste Management Accomplishments * WIPP: Emplaced 5,065 cubic meters of TRU with 89 percent of shipments departed from TRU waste sites as planned * Los Alamos: Met Framework Agreement goal for FY 13 ahead of schedule, disposing of over 1,800 cubic meters of legacy managed TRU waste * Oak Ridge: Partnered with regulators to develop strategy for

310

Page not found | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

51 - 18560 of 31,917 results. 51 - 18560 of 31,917 results. Article DOE to Weigh Alternatives for Greater Than Class C Low-Level Waste Disposal WASHINGTON, DC - The U.S. Department of Energy (DOE) today announced that it will evaluate disposal options for Greater Than Class C (GTCC) low-level radioactive waste (LLW) generated from the... http://energy.gov/articles/doe-weigh-alternatives-greater-class-c-low-level-waste-disposal Download EMAB Reports and Recommendations- September 2009 Environmental Management Advisory board letters, reports, and recommendations. http://energy.gov/em/downloads/emab-reports-and-recommendations-september-2009 Download Memorandum Memorializing Ex Parte Communication, DOE impending determination of coverage for commercial and industrial fans, blowers, and

311

DOE-STD-5507-2013 | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

7-2013 7-2013 DOE-STD-5507-2013 April 04, 2013 Standard for Communicating Waste Characterization and DOT Hazard Classification Requirements for Low Specific Activity Materials and Surface Contaminated Objects Although other types of radioactive material and waste may be candidate LSA material or SCO, this standard focuses solely on low-level waste (LLW)3. The DOE ships various types of radioactive waste stemming from current and historical operations. Generally, candidate LSA material and SCO within the DOE complex are wastes generated from the clean-up and deactivation of World War II and Cold War era nuclear processing and weapons support operations. These waste matrices can be complex. The level of effort required to characterize waste varies based on the type and origin of waste

312

DOE - Safety of Radioactive Material Transportation  

NLE Websites -- All DOE Office Websites (Extended Search)

How are they moved? What's their construction? Who uses them? Who makes rules? What are the requirements? Safety Record Packagings are used to safely transport radioactive materials across the United States in over 1.6 million shipments per year. [Weiner et. al., 1991, Risk Analysis, Vol. 11, No. 4, p. 663] Most shipments are destined for hospitals and medical facilities. Other destinations include industrial, research and manufacturing plants, nuclear power plants and national defense facilities. The last comprehensive survey showed that less than 1 percent of these shipments involve high-level radioactive material. [Javitz et. al., 1985, SAND84-7174, Tables 4 and 8] The types of materials transported include: Surface Contaminated Object (SCO) Low Specific Activity (LSA) materials, Low-Level Waste (LLW),

313

EIS-0286: Record of Decision | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Record of Decision Record of Decision EIS-0286: Record of Decision Solid Waste Program, Hanford Site, Richland, WA: Storage and Treatment of Low-Level Waste and Mixed Low-Level Waste; Disposal of Low-Level Waste and Mixed Low-Level Waste, and Storage, Processing, and Certification of Transuranic Waste for Shipment to the Waste Isolation Pilot Plant The U.S. Department of Energy (DOE) is making decisions regarding low-level radioactive waste (LLW), mixed low-level waste (MLLW), which contains both radioactive and chemically hazardous components, and transuranic (TRU) waste (including mixed TRU waste) at the Hanford Site in southeastern Washington State. Record of Decision for the Solid Waste Program, Hanford Site, Richland, WA: Storage and Treatment of Low-Level Waste and Mixed Low-Level Waste;

314

Microsoft PowerPoint - 1-06 Subramanian Sams11-12.ppt  

NLE Websites -- All DOE Office Websites (Extended Search)

WP Technical Exchange WP Technical Exchange Hanford/SRS Tank Waste Path Forward Karthik Subramanian, SRR Terry Sams, WRPS 11/16/2010 SRR-MS-2010-00249 Print Close 2 Overview * Technology Deployment Vision * Tank Waste Strategy and Life-Cycle Benefits - Transformational Technology Scenarios * Hanford - Vitrification Technologies - Salt Processing: LAW Pretreatment and Immobilization * Rotary Microfiltration/Small Column Ion Exchange (RMF/SCIX) * Alternate LLW: Fluidized Bed Steam Reforming (FBSR) - Accelerated SST Retrieval * SRS - Vitrification Technologies - Salt Processing * Rotary Microfiltration/Small Column Ion Exchange (RMF/SCIX) * Next Generation Modular Caustic Side Solvent Extraction (MCU) Print Close 3 Technology Deployment * Goal-oriented technology deployment process to integrate and manage resources through collaboration

315

I  

Office of Legacy Management (LM)

II II DOE PROJECT RISKS April 30, 2005 Revision 0 Publication Records Revision Number Approval Date 0 April 30, 2005 TABLE OF CONTENT I INTRODCUTION 1 II RISK DESCRIPTION AND ASSESSMENT 2 A. Delays and Cost Impacts Associated with Site Reuse 2 B. Discovery of TRU Waste Past Expiration of OHOX Rail Car 4 C. Landscaping or Removal of PRS-8 Landfill 5 D. Government Furnished Services/Items (GFS/I) 9 E. Final Site-wide Record of Decision (ROD) Definition and Canal ROD 10 F. Groundwater Contamination and Mitigation 11 G. Legacy Medical and Pension Costs 12 H Estimated Low Level Waste (LLW) Soil Volumes 13 I. MMCIC Acceptance of T Building as is e.g., HVAC System 13 J. Added Scope Items 14

316

Finding of No Significant Impact for the Offsite Transportation of Certain Low-Level and Mixed Radioactive Waste from Savannah River Site for Treatment and Disposal at Commercial and Government Facilities, DOE/EA-1308 (02/15/01)  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Finding of No Significant Impact Finding of No Significant Impact for the Offsite Transportation of Certain Low-level and Mixed Radioactive Waste from the Savannah River Site for Treatment and Disposal at Commercial and Government Facilities Agency: U. S. Department of Energy Action: Finding of No Significant Impact Summary: The Department of Energy (DOE) has prepared an environmental assessment (EA) (DOE/EA-1308) to analyze the potential environmental impacts associated with the proposed offsite transportation of certain low-level radioactive waste (LLW) and mixed (i.e., hazardous and radioactive) low-level radioactive waste (MLLW) from the Savannah River Site (SRS), located near Aiken, South Carolina. Based on the analyses in the EA, DOE has determined that the action is not a major Federal action significantly affecting

317

Summary - Idaho CERCLA Disposal Facility (ICDF) at Idaho National Laboratory  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

INL, Idaho INL, Idaho EM Project: Idaho CERCLA Disposal Facility ETR Report Date: December 2007 ETR-10 United States Department of Energy Office of Environmental Management (DOE-EM) External Technical Review of Idaho CERCLA Disposal Facility (ICDF) At Idaho National Laboratory (INL) Why DOE-EM Did This Review The Idaho CERCLA Disposal Facility (ICDF) is a land disposal facility that is used to dispose of LLW and MLW generated from remedial activities at the Idaho National Laboratory (INL). Components of the ICDF include a landfill that is used for disposal of solid waste, an evaporation pond that is used to manage leachate from the landfill and other aqueous wastes (8.3 million L capacity), and a staging and treatment facility. The ICDF is located near the southwest

318

TYNtìÐ!ÈK N,/jlonat Nudeü Secww Admlnlsttailon  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

tl^^r^YêÈÁr tl^^r^YêÈÁr TYNtìÐ!ÈK N,/jlonat Nudeü Secww Admlnlsttailon Department of Energy National Nuclear Security Administration Los Alamos Site Office DOE/ErS-0380-SA-01 Supplement Analysis Site-Wide Environmental lmpact Statement for Continued Operation of Los Alamos National Laboratory Proposed Transport of Low Level Radioactive Waste by Truck and Rail from Los Alamos National Laboratory (LANL) for Disposal at EnergySolutions at Clive, Utah October 2009 DOE/ErS-0380-SA-01 Introduction This analysis is prepared to determine if the Final Site-Wide Environmental Impact Statement (2008 SWEIS) for Continued Operation of Los Alamos National Laboratory, Los Alamos, New Mexico, (DOE/EIS 0380) adequately bounds ofÊsite transpofiation of Low Specific Activity (LSA) and Low Level V/aste (LLW) by a combination of truck

319

CX-004455: Categorical Exclusion Determination | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

455: Categorical Exclusion Determination 455: Categorical Exclusion Determination CX-004455: Categorical Exclusion Determination Geotechnical Investigation for Idaho National Laboratory Remote-Handled Low-Level Waste Disposal CX(s) Applied: B3.1 Date: 11/12/2010 Location(s): Idaho Falls, Idaho Office(s): Nuclear Energy, Idaho Operations Office The proposed action would conduct geotechnical investigations at two 4-6 acre candidate sites for a Remote-Handled Low-Level Waste (RH LLW) Facility at the Idaho National Laboratory (INL). One site is located southwest of the Advanced Test Reactor (ATR)-Complex and the other site is located west of and across Lincoln Boulevard from the Idaho Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Disposal Facility (ICDF). DOCUMENT(S) AVAILABLE FOR DOWNLOAD

320

West Valley Seeks Comment on Draft Waste Evaluation | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Seeks Comment on Draft Waste Evaluation Seeks Comment on Draft Waste Evaluation West Valley Seeks Comment on Draft Waste Evaluation June 29, 2012 - 12:00pm Addthis Media Contacts Bryan Bower 716-942-4368 Bill Taylor bill.taylor@srs.gov 803-952-8564 West Valley, NY - The U.S. Department of Energy (DOE) today released to the Nuclear Regulatory Commission (NRC), the public and the states of Nevada and Texas, and the Seneca Nation of Indians for review and comment, a Draft Waste Incidental to Reprocessing Evaluation for the concentrator feed makeup tank and the melter feed hold tank (the vessels) at the West Valley Demonstration Project (WVDP). This Draft Evaluation, which may enable the Department to dispose of the vessels as low-level radioactive waste (LLW), is a necessary step in the Department's cleanup efforts at

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321

Microsoft PowerPoint - EM SSAB Chairs Webinar - Marcinowski Waste Strategies.042413  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Chair's Meeting Chair's Meeting Waste Disposition Strategies Update www.energy.gov/EM 1 Waste Disposition Strategies Update Frank Marcinowski Deputy Assistant Secretary for Waste Management Office of Environmental Management April 25, 2013 * Recent Program Accomplishments * FY13 Waste Management Priorities * FY14 Waste Management Priorities * Los Alamos Update * LLW/MLLW Disposition Options Discussion Outline www.energy.gov/EM 2 * Hanford TRU Tank Disposition Initiative * GTCC EIS * Mercury Supplemental EIS * Excess Material and Metal Recycling * DOE Order 435.1, Radioactive Waste Management * Blue Ribbon Commission Related Activities Recent Program Accomplishments * Continued progress towards removal of Los Alamos TRU waste, in accord with Framework Agreement * Submitted WIPP Hazardous Waste Facility permit modification for

322

PowerPoint Presentation  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

1613 NTSF 1613 NTSF National Transportation Stakeholder Forum West Valley Demonstration Project A Short History and Status May 7, 2013 www.wv.doe.gov Bryan C. Bower, Director bryan.bower@wv.doe.gov 1 051613 NTSF West Valley Demonstration Project (WVDP) Mission 2 The WVDP mission was defined by an act of Congress in 1980 - Public Law 98-368 1. Solidify the high-level radioactive waste at the Center * 99.7% of the curies in the tanks were vitrified and the glass is contained in 275 stainless steel canisters 2. Develop containers suitable for permanent disposal of the waste 3. Transport the solidified waste to a federal repository for permanent disposal 4. Dispose of low-level radioactive waste (LLW) and transuranic (TRU) waste 5. Decontaminate and decommission the underground

323

DOEIEA-1061 ENVIRONMENTAL ASSESSMENT FOR THE OFF-SITE VOLUME REDUCTION OF  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

61 61 ENVIRONMENTAL ASSESSMENT FOR THE OFF-SITE VOLUME REDUCTION OF LOW-LEVEL RADIOACTIVE WASTE FROM THE SAVANNAH IUVER SITE JULY 1995 U. S. DEPARTMENT OF ENERGY SAVANNAH RIVER OPERATIONS OFFICE SAVANNAH RIVER SITE A . RECEIVED Finding of No Significant Impact for the JAN 3 1 19% Off-Site Volume Reduction of Low-Level Radioactive Waste - from the Savannah River Site O S T I Agency: Action: U . S. Department of Energy Finding of No Significant Impact Summary: The Department of Energy (DOE) has prepared an environmental assessment (EA) (DOEM-1061) for the proposed off-site volume duction of low-bel radioactive wastes (LLW) generated at the Savannah River Site (SRS), near Aiken,South Carolina. Based on the analyses in the EA, DOE has determined that the proposed

324

DOE-STD-5507-2013 | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

5507-2013 5507-2013 DOE-STD-5507-2013 April 04, 2013 Standard for Communicating Waste Characterization and DOT Hazard Classification Requirements for Low Specific Activity Materials and Surface Contaminated Objects Although other types of radioactive material and waste may be candidate LSA material or SCO, this standard focuses solely on low-level waste (LLW)3. The DOE ships various types of radioactive waste stemming from current and historical operations. Generally, candidate LSA material and SCO within the DOE complex are wastes generated from the clean-up and deactivation of World War II and Cold War era nuclear processing and weapons support operations. These waste matrices can be complex. The level of effort required to characterize waste varies based on the type and origin of waste

325

12/2000 Low-Level Waste Disposal Capacity Report Version 2 | Department of  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Services » Waste Management » Waste Disposition » 12/2000 Services » Waste Management » Waste Disposition » 12/2000 Low-Level Waste Disposal Capacity Report Version 2 12/2000 Low-Level Waste Disposal Capacity Report Version 2 The purpose of this Report is to assess whether U.S. Department of Energy (DOE or the Department) disposal facilities have sufficient volumetric and radiological capacity to accommodate the low-level waste (LLW) and mixed low-level waste (MLLW) that the Department expects to dispose at these facilities. 12/2000 Low-Level Waste Disposal Capacity Report Version 2 More Documents & Publications EIS-0243: Record of Decision EIS-0200: Record of Decision EIS-0286: Record of Decision Waste Management Nuclear Materials & Waste Tank Waste and Waste Processing Waste Disposition Packaging and Transportation

326

Microsoft PowerPoint - SSAB Chairs Presentation_Marcinowski (corrected version) [Compatibility Mode]  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Frank Marcinowski Frank Marcinowski Deputy Assistant Secretary for Technical and Regulatory Support Office of Environmental Management EM Site-Specific Advisory Board Chairs Meeting Santa Fe, New Mexico September 15, 2010 Outline * EM radioactive waste management system, policy and priorities * DOE Order 435.1 * Programmatic updates and challenges - LLW/MLLW disposition - TRU waste acceleration and progress - TRU waste acceleration and progress - High level waste and used fuel management - GTCC EIS - Mercury management EIS Brief history of DOE's current waste management system - EM established in 1989 to address the legacy contamination from DOE defense and research missions - Federal Facility Compliance Act (FFCAct) enacted in 1992 - DNFSB issued recommendation 94-2, calling for safety

327

Federal Register Notice | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Federal Register Notice Federal Register Notice Federal Register Notice The U.S. Nuclear Regulatory Commission (NRC), in coordination with the U.S. Department of Energy (DOE), plans to conduct a workshop to discuss possible approaches to revising the regulatory framework for the management of commercial low-level radioactive waste (LLW). The purpose of this workshop is to gather information from a broad spectrum of stakeholders concerning the NRC's proposed options for a comprehensive revision to NRC's and DOE's waste regulations and to discuss possible options. Federal Register Notice More Documents & Publications Fourth National Report for the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management Nuclear Regulatory Commission's Integrated Strategy for Spent Fuel

328

Plutonium Oxication State Transformations and Their Consequence on Plutonium Transport through Sediment During an 11-year Field Study  

Science Conference Proceedings (OSTI)

The Savannah River Site (SRS) contains a large inventory of plutonium (Pu), some of it in the form of Low-Level Waste (LLW). Much of this LLW has been or will be disposed at the E Area LLW Facility. As part of the permitting of LLW on-site disposal, SRS is required to periodically update the Performance Assessment calculations used in part to establish the facility specific amount of waste that can be safely disposed (or establish the Waste Acceptance Criteria). The objective of this project was to determine if a recent discovered change in plutonium chemistry (i.e., oxidation of PuO2, a common form of Pu waste, may form plutonium in the more mobile hexavalent form) was within the assumptions, parameters, and bases of the approved Performance Assessment WSRC (2000) and Composite Assessment, WSRC (1997). This project was initiated in 2001, and this is the final report describing laboratory and lysimeter (field) studies. Results from this year's work provided additional technical support f or the conceptual Pu geochemical model proposed for future risk-based calculations. When lysimeters containing Pu(III) or Pu(IV) were left exposed to the natural environment for 11 years, essentially all of the sediment-bound Pu existed as Pu(IV) and possibly Pu(III), the least mobile forms of Pu. This result was confirmed by two independent measurements, a very sensitive, indirect wet-chemistry method and a less-sensitive, direct spectroscopic technique, micro-X-ray adsorption near-edge structure (micro-XANES) spectroscopy. In these lysimeters, Pu sediment concentrations decreased on average an order-of-magnitude per centimeter for the first 5 cm below the source, an astounding rate of contaminant retardation. When Pu(VI), the more mobile form, may form from PuO2, was added to the lysimeters, the Pu moved faster than it had in the other lysimeters: Pu moving on average 12.5 cm/yr in the Pu(VI) lysimeter, compared to 0.9 cm/yr in the Pu(III) and Pu(IV) lysimeters. Importantly, transport modeling of the data clearly suggested that reduction of the original Pu(VI) occurred,thus most of the transport of the Pu in the lysimeter must have progressed during the early portion of the study, prior to the sediment-induced reduction of Pu(VI). When Pu(V) was added to the lysimeter sediment in a laboratory study, the Pu(V) quickly reduced to Pu(IV) within a couple days. These data together with those from previous reports for this project conclusively show that Pu, irrespective of the form it is introduced into SRS sediments, tends to convert rapidly to the plus 4, and possible plus 3, oxidation state, the least mobile form of Pu.

KAPLAN, DANIEL

2004-09-30T23:59:59.000Z

329

Statement of work for architect-engineer services, initial pretreatment module  

SciTech Connect

This Statement of Work describes the Architect-Engineer services to be provided by Raytheon/BNFL in providing a conceptual design (Contract TGW-SVV-063869) for the Initial Pretreatment Module (IPM), Project W-236B, at the Hanford site, Richland, Washington. The IPM Project, a radiochemical process facility, will be designed and constructed for an initial phase of waste pretreatment, which will be for the removal of cesium from supernatant wastes to produce a Low-level waste (LLW) stream to a vitrification facility. The design shall also accommodate side streams of High-Level Waste (HLW) fractions that will be directed to suitable, existing storage tanks where they will be recombined with an additional high-activity waste fraction generated from pretreatment of the tank waste sludges and solids. This combined high-activity waste fraction will be immobilized as glass and disposed in a geological repository.

Sowa, K.B.

1994-09-15T23:59:59.000Z

330

Bench-scale studies with mercury contaminated SRS soil  

SciTech Connect

The Savannah River Technology Center (SRTC) has been charactered by the Department of Enregy (DOE) - Office of Technology Development (OTD) to investigate vitrification technology for the treatment of Low Level Mixed Wastes (LLMW). In fiscal year 1995, LLW streams containing mercury and organics were targeted. This report will present the results of studies with mercury contaminated waste. In order to successfully apply vitrification technology to LLMW, the types and quantities of glass forming additives necessary for producing homogeneous glasses from the wastes had to be determined, and the treatment for the mercury portion had to also be determined. The selected additives had to ensure that a durable and leach resistant waste form was produced, while the mercury treatment had to ensure that hazardous amounts of mercury were not released into the environment.

Cicero, C.A.

1996-05-08T23:59:59.000Z

331

Low-Level Waste Forum notes and summary reports for 1994. Volume 9, Number 3, May-June 1994  

SciTech Connect

This issue includes the following articles: Vermont ratifies Texas compact; Pennsylvania study on rates of decay for classes of low-level radioactive waste; South Carolina legislature adjourns without extending access to Barnwell for out-of-region generators; Southeast Compact Commission authorizes payments for facility development, also votes on petitions, access contracts; storage of low-level radioactive waste at Rancho Seco removed from consideration; plutonium estimates for Ward Valley, California; judgment issued in Ward Valley lawsuits; Central Midwest Commission questions court`s jurisdiction over surcharge rebates litigation; Supreme Court decides commerce clause case involving solid waste; parties voluntarily dismiss Envirocare case; appellate court affirms dismissal of suit against Central Commission; LLW Forum mixed waste working group meets; US EPA Office of Radiation and Indoor Air rulemakings; EPA issues draft radiation site cleanup regulation; EPA extends mixed waste enforcement moratorium; and NRC denies petition to amend low-level radioactive waste classification regulations.

NONE

1994-06-01T23:59:59.000Z

332

Spent Fuel and Waste Management Technology Development Program. Annual progress report  

SciTech Connect

This report provides information on the progress of activities during fiscal year 1993 in the Spent Fuel and Waste Management Technology Development Program (SF&WMTDP) at the Idaho Chemical Processing Plant (ICPP). As a new program, efforts are just getting underway toward addressing major issues related to the fuel and waste stored at the ICPP. The SF&WMTDP has the following principal objectives: Investigate direct dispositioning of spent fuel, striving for one acceptable waste form; determine the best treatment process(es) for liquid and calcine wastes to minimize the volume of high level radioactive waste (HLW) and low level waste (LLW); demonstrate the integrated operability and maintainability of selected treatment and immobilization processes; and assure that implementation of the selected waste treatment process is environmentally acceptable, ensures public and worker safety, and is economically feasible.

Bryant, J.W.

1994-01-01T23:59:59.000Z

333

Performance assessment for a hypothetical low-level waste disposal facility  

Science Conference Proceedings (OSTI)

Disposing of low-level waste (LLW) is a concern for many states throughout the United States. A common disposal method is below-grade concrete vaults. Performance assessment analyses make predictions of contaminant release, transport, ingestion, inhalation, or other routes of exposure, and the resulting doses for various disposal methods such as the below-grade concrete vaults. Numerous assumptions are required to simplify the processes associated with the disposal facility to make predictions feasible. In general, these assumptions are made conservatively so as to underestimate the performance of the facility. The objective of this report is to describe the methodology used in conducting a performance assessment for a hypothetical waste facility located in the northeastern United States using real data as much as possible. This report consists of the following: (a) a description of the disposal facility and site, (b) methods used to analyze performance of the facility, (c) the results of the analysis, and (d) the conclusions of this study.

Smith, C.S.; Rohe, M.J.; Ritter, P.D. [and others

1997-01-01T23:59:59.000Z

334

Environmental review of options for managing radioactively contaminated carbon steel  

SciTech Connect

The U.S. Department of Energy (DOE) is proposing to develop a strategy for the management of radioactively contaminated carbon steel (RCCS). Currently, most of this material either is placed in special containers and disposed of by shallow land burial in facilities designed for low-level radioactive waste (LLW) or is stored indefinitely pending sufficient funding to support alternative disposition. The growing amount of RCCS with which DOE will have to deal in the foreseeable future, coupled with the continued need to protect the human and natural environment, has led the Department to evaluate other approaches for managing this material. This environmental review (ER) describes the options that could be used for RCCS management and examines the potential environmental consequences of implementing each. Because much of the analysis underlying this document is available from previous studies, wherever possible the ER relies on incorporating the conclusions of those studies as summaries or by reference.

NONE

1996-10-01T23:59:59.000Z

335

Disposal concepts and characteristics of existing and potential low-waste repositories - 9076  

Science Conference Proceedings (OSTI)

The closure of the Barnwell low-level waste (LLW) disposal facility to non-Atlantic Compact users poses significant problems for organizations seeking to remove waste material from public circulation. Beta-gamma sources such as {sup 137}Cs and {sup 90}Sr in particular create problems because in 36 states no path forward exists for disposal. Furthermore, several other countries are considering disposition of sealed sources in a variety of facilities. Like much of the United States, many of these countries currently have no means of disposal. Consequently, there is a greater tendency for sources to be misplaced or stored in insufficient facilities, resulting in an increased likelihood of unwitting exposure of nearby people to radioactive materials. This paper provides an overview of the various disposal concepts that have been employed or attempted in the United States. From these concepts, a general overview of characteristics necessary for long-term disposal is synthesized.

Johnson, Peter J [Los Alamos National Laboratory; Zarling, John C [Los Alamos National Laboratory

2009-01-01T23:59:59.000Z

336

HIGH SENSITIVITY NEUTRON ASSAY OF GROUTED SPENT NUCLEAR FUEL SLUDGE AT HANFORD  

SciTech Connect

The disposal of the North Loadout Pit (NLOP) waste at Hanford will produce 208-liter grouted sludge drums bearing transuranic (TRU) radionuclides and fission products. Discrimination between low level waste (LLW) and TRU waste requires a lower limit of detection (LLD) of less than 100 nCi (3700 Bq) of TRU alpha activity per gram of waste matrix in order to correctly certify the final waste form. Hanford's Waste Receiving and Processing (WRAP) facility operates two identical Imaging Passive Active Neutron (IPAN{trademark}) systems which had previously demonstrated this low detection limit capability for debris waste. These two IPAN{trademark} systems were selected as the appropriate technology to assay this challenging waste stream.

ABDURRAHMAN NM

2007-10-12T23:59:59.000Z

337

Annual Transportation Report for Radioactive Waste Shipments to and from the Nevada Test Site, Fiscal Year 2006  

SciTech Connect

In February 1997, the U.S. Department of Energy, Nevada Operations Office issued the Mitigation Action Plan which addressed potential impacts described in the Final Environmental Impact Statement for the Nevada Test Site and Off-Site Locations in the State of Nevada (DOE/EIS 0243). The U.S. Department of Energy, Nevada Operations Office committed to several actions, including the preparation of an annual report, which summarizes waste shipments to and from the Nevada Test Site (NTS) Radioactive Waste Management Sites (RWMS) at Area 3 and Area 5. This document satisfies requirements with regard to low-level radioactive waste (LLW) and mixed low-level radioactive waste (MLLW) transported to or from the NTS during fiscal year (FY) 2006.

DOE /NNSA NSO

2007-01-01T23:59:59.000Z

338

Evaluating off-site disposal of low-level waste at LANL-9498  

SciTech Connect

Los Alamos National Laboratory generates a wide range of waste types, including solid low-level radioactive waste (LL W), in conducting its national security mission and other science and technology activities. Although most ofLANL's LLW has been disposed on-site, limitations on expansion, stakeholder concerns, and the potential for significant volumes from environmental remediation and decontamination and demolition (D&D) have led LANL to evaluate the feasibility of increasing off-site disposal. It appears that most of the LL W generated at LANL would meet the Waste Acceptance Criteria at the Nevada Test Site or the available commercial LL W disposal site. Some waste is considered to be problematic to transport to off-site disposal even though it could meet the off-site Waste Acceptance Criteria. Cost estimates for off-site disposal are being evaluated for comparison to estimated costs under the current plans for continued on-site disposal.

Hargis, Kenneth M [Los Alamos National Laboratory; French, Sean B [Los Alamos National Laboratory; Boyance, Julien A [NORTH WIND, INC.

2009-01-01T23:59:59.000Z

339

Multi-Stage Supercompaction Of Large Low-Level Waste Components  

E-Print Network (OSTI)

This paper demonstrates that multi-stage compaction (supercompaction) (high-force compaction) has an important role to play in treating metallic LLW. A specialized shear/compactor can produce significant labor and burial cost savings, as well as better operational safety and environmental protection. A case study is the supercompaction facility presently nearing completion at the DOE East Tennessee Technology Park--ETTP--(formerly, the K-25 Gaseous Diffusion Plant) in Oak Ridge. The facility will initially process some 63,000 tons of mainly metallic materials arising from the D&D clean-up project presently being undertaken by BNFL Inc. for the DOE. These materials cannot be economically recycled and prior to burial disposal will be supercompacted with up to 7:1 volume reduction. The paper will confirm progress toward facility handover to production in October 2000. 1. INTRODUCTION Supercompaction is a loosely defined term, and this paper starts by offering a definition, and by re...

Martin Cottam Bsc; Martin Cottam; C Eng

2000-01-01T23:59:59.000Z

340

Pretreatment of neutralized cladding removal waste sludge: Status Report  

SciTech Connect

This report describes the status of process development for pretreating Hanford neutralized cladding removal waste (NCRW) sludge, of which [approximately] 3.3 [times] 10[sup 6] L is stored in Tanks 103-AW and 105-AW at the Hanford Site. The initial baseline process chosen for pretreating NCRW sludge is to dissolve the sludge in nitric acid and extract the -transuranic (MU) elements from the dissolved sludge solution with octyl(phenyl)-N,N-diisobutylcarbamoyl methyl phosphine oxide (CNWO). This process converts the NCRW sludge into a relatively large volume of low-level waste (LLW) to be disposed of as grout, leaving only a small volume of high-level waste (HLW) requiring vitrification in the Hanford Waste Vitrification Plant (HWVP).

Lumetta, G J; Swanson, J L

1993-03-01T23:59:59.000Z

Note: This page contains sample records for the topic "non-hlw wds llw" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


341

Survey of life-cycle costs of glass-paper HEPA filters  

SciTech Connect

We have conducted a survey of the major users of glass-paper HEPA filters in the DOE complex to ascertain the life cycle costs of these filters. Purchase price of the filters is only a minor portion of the costs; the major expenditures are incurred during the removal and disposal of contaminated filters. Through personal interviews, site visits and completion of questionnaires, we have determined the costs associated with the use of HEPA filters in the DOE complex. The total approximate life-cycle cost for a standard (2 in. {times} 2 in. {times} 1 in.) glass-paper HEPA filter is $3,000 for one considered low-level waste (LLW), $11,780 for transuranic (TRU) and $15,000 for high-level waste (HLW). The weighted-average cost for a standard HEPA filter in the complex is $4,753.

Moore, P.; Bergman, W. [Lawrence Livermore National Lab., CA (United States); Gilbert, H. [Gilbert (Humphrey), McLean, VA (United States)

1992-08-01T23:59:59.000Z

342

Radiological performance assessment for the Z-Area Saltstone Disposal Facility  

SciTech Connect

This radiological performance assessment (RPA) for the Savannah River Site (SRS) Saltstone Disposal Facility (SDF) was prepared in accordance with the requirements of Chapter III of the US Department of Energy Order 5820.2A. The Order specifies that an RPA should provide reasonable assurance that a low-level waste (LLW) disposal facility will comply with the performance objectives of the Order. The performance objectives require that: (1) exposures of the general public to radioactivity in the waste or released from the waste will not result in an effective dose equivalent of 25 mrem per year; (2) releases to the atmosphere will meet the requirements of 40 CFR 61; (3) inadvertent intruders will not be committed to an excess of an effective dose equivalent of 100 mrem per year from chronic exposure, or 500 mrem from a single acute exposure; and (4) groundwater resources will be protected in accordance with Federal, State and local requirements.

Cook, J.R.; Fowler, J.R. [Westinghouse Savannah River Co., Aiken, SC (United States)

1992-12-18T23:59:59.000Z

343

Alternatives generation and analysis for the Phase I intermediate waste feed staging system design requirements  

SciTech Connect

This alternatives generation and analysis (AGA) addresses the question: What is the design basis for the facilities required to stage low-level waste (LLW) feed to the Phase I private contractors? Alternative designs for the intermediate waste feed staging system were developed, analyzed, and compared. Based on these analyses, this document recommends installing mixer pumps in the central pump pit of double-shell tanks 241-AP-102 and 241-AP-104. Also recommended is installing decant/transfer pumps at these tanks. These recommendations have clear advantages in that they provide a low shedule impact/risk and the highest operability of all the alternatives investigated. This revision incorporates comments from the decision board.

Claghorn, R.D., Fluor Daniel Hanford

1997-02-06T23:59:59.000Z

344

LFRG DOE Order 435.1 | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

LFRG DOE Order 435.1 LFRG DOE Order 435.1 LFRG DOE Order 435.1 Chapter 4 of the DOE Manual on Order 435.1, Low-level Waste Requirements, addresses the procedures whereby Department of Energy LLW Disposal Facilities will operated and maintained. Section P and Section Q describe the Performance Assessment and Composite Analysis documents that each DOE disposal facility will submit to the LFRG. To view the entire DOE Order, Manual, and Implementation Guidance documents, choose the link below to get to the main DOE Directives portal and follow the search requirements. DOE Directives, Regulations, and Standards Portal Note - For DOE O 435.1 Chg 1 (08-28-01), please use the above link and follow the search option to locate this document. P. Disposal. Low-level waste disposal facilities shall meet the following

345

West Valley  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Nuclear Facility Nuclear Facility Coalition on West Valley Nuclear Wastes PO Box 603 Springville NY 14141 WV-DigItUp@roadrunner.com Joanne Hameister CFMT (Concentrator Feed Make-up Tank) Packaged 13'x14'x19' 177.5 tons MFHT (Melter Feed Hold Tank) Packaged 13'x14'x16' 152.5 tons WIR Shipments pending to LLW facility MELTER 10'x10'x10' Packaged: 14'x13'x13' 159 tons 4,570 Curies Waste Categories High-Level Waste Based on source * Nuclear Fuel * Reprocessing * TRU Low-Level Waste Not Low Risk Complex classification based on * Nuclide inventory * Half-life(s) * Quantity * Decay products Background Radiation 1978 - average was 100 mRem per person 2011 - BRC* estimate 620 mRem per person Naturally occurring radioactive elements Additions accumulate - from fall-out,

346

Maintenance Plan for the Performance Assessments and Composite Analyses for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada Test Site  

SciTech Connect

U.S. Department of Energy (DOE) Order 435.1 requires that performance assessments (PAs) and composite analyses (CAs) for low-level waste (LLW) disposal facilities be maintained by the field offices. This plan describes the activities to be performed in maintaining the Performance Assessment (PA) and Composite Analysis (CA) for the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) at the Nevada Test Site (NTS). The Disposal Authorization Statement (DAS) for the continuing operations of a LLW facility at the DOE complex specifies the conditions for operations based on approval of a PA and CA, and requires the facility to implement a maintenance program to assure that these conditions will remain protective of the public health and the environment in the future. The goal of the maintenance program is to provide that assurance. The maintenance process is an iterative one in which changing conditions may result in a revision of PA and CA; the revised PA and CA may impose a different set of conditions for facility operation, closure, and postclosure. The maintenance process includes managing uncertainty, performing annual reviews, submitting annual summary reports to DOE Headquarters (DOE/HQ), carrying out special analyses, and revising the PAs and CAs, if necessary. Management of uncertainty is an essential component of the maintenance program because results of the original PAs and CAs are understood to be based on uncertain assumptions about the conceptual models; the mathematical models and parameters; and the future state of the lands, disposal facilities, and human activities. The annual reviews for the PAs include consideration of waste receipts, facility specific factors, results of monitoring, and results of research and development (R&D) activities. Likewise, results of ongoing R&D, changes in land-use planning, new information on known sources of residual radioactive materials, and identification of new sources may warrant an evaluation to determine the impacts on the conclusions of the CAs.

V. Yucel

2002-09-01T23:59:59.000Z

347

Comparison of modified sulfur cement and hydraulic cement for encapsulation of radioactive and mixed wastes  

SciTech Connect

The majority of solidification/stabilization systems for low-level radioactive waste (LLW) and mixed waste, both in the commercial sector and at Department of Energy (DOE) facilities, utilize hydraulic cement (such as portland cement) to encapsulate waste materials and yield a monolithic solid waste form for disposal. A new and innovative process utilizing modified sulfur cement developed by the US Bureau of Mines has been applied at Brookhaven National Laboratory (BNL) for the encapsulation of many of these problem'' wastes. Modified sulfur cement is a thermoplastic material, and as such, it can be heated above it's melting point (120{degree}C), combined with dry waste products to form a homogeneous mixture, and cooled to form a monolithic solid product. Under sponsorship of the DOE, research and development efforts at BNL have successfully applied the modified sulfur cement process for treatment of a range of LLWs including sodium sulfate salts, boric acid salts, and incinerator bottom ash and for mixed waste contaminated incinerator fly ash. Process development studies were conducted to determine optimal waste loadings for each waste type. Property evaluation studies were conducted to test waste form behavior under disposal conditions by applying relevant performance testing criteria established by the Nuclear Regulatory Commission (for LLW) and the Environmental Protection Agency (for hazardous wastes). Based on both processing and performance considerations, significantly greater waste loadings were achieved using modified sulfur cement when compared with hydraulic cement. Technology demonstration of the modified sulfur cement encapsulation system using production-scale equipment is scheduled for FY 1991. 12 refs., 8 figs., 3 tabs.

Kalb, P.D.; Heiser, J.H. III; Colombo, P.

1990-01-01T23:59:59.000Z

348

Landfill stabilization focus area: Technology summary  

SciTech Connect

Landfills within the DOE Complex as of 1990 are estimated to contain 3 million cubic meters of buried waste. The DOE facilities where the waste is predominantly located are at Hanford, the Savannah River Site (SRS), the Idaho National Engineering Laboratory (INEL), the Los Alamos National Laboratory (LANL), the Oak Ridge Reservation (ORR), the Nevada Test Site (NTS), and the Rocky Flats Plant (RFP). Landfills include buried waste, whether on pads or in trenches, sumps, ponds, pits, cribs, heaps and piles, auger holes, caissons, and sanitary landfills. Approximately half of all DOE buried waste was disposed of before 1970. Disposal regulations at that time permitted the commingling of various types of waste (i.e., transuranic, low-level radioactive, hazardous). As a result, much of the buried waste throughout the DOE Complex is presently believed to be contaminated with both hazardous and radioactive materials. DOE buried waste typically includes transuranic-contaminated radioactive waste (TRU), low-level radioactive waste (LLW), hazardous waste per 40 CFR 26 1, greater-than-class-C waste per CFR 61 55 (GTCC), mixed TRU waste, and mixed LLW. The mission of the Landfill Stabilization Focus Area is to develop, demonstrate, and deliver safer,more cost-effective and efficient technologies which satisfy DOE site needs for the remediation and management of landfills. The LSFA is structured into five technology areas to meet the landfill remediation and management needs across the DOE complex. These technology areas are: assessment, retrieval, treatment, containment, and stabilization. Technical tasks in each of these areas are reviewed.

NONE

1995-06-01T23:59:59.000Z

349

High sensitivity assay of cement encapsulated spent nuclear fuel sludge using the Imaging Passive Active Neutron (IPAN) system  

SciTech Connect

A new technique has been developed for high sensitivity assay of grouted spent nuclear fuel (SNF) sludge waste in 208 liter drums. The method uses the Imaging Passive Active Neutron (IPAN{sup TM}) system to provide regulatory acceptable measurements. At the Waste Receiving and Processing (WRAP) Facility in Hanford, two IPAN{sup TM} systems have been successfully calibrated and validated for assay of SNF grouted sludge drums (encapsulated with a cement mixture). The systems have been demonstrated to be capable of performing low level waste (LLW) / transuranic (TRU) waste sorting even in the presence of high gamma radiation fields emitted by the fission and activation products associated with SNF. The active and passive modes of the IPAN{sup TM} provide a wide dynamic range of assay: from below the TRU/LLW sorting threshold (100 nCi/g or 3700 Bq/g) up to several hundred grams of Weapons Grade Pu Equivalent. A new calibration technique was developed that uses a radial weighted average method to define the imaging response matrix. This method provides the required sensitivity to the height distribution of special nuclear material within the 208 liter drum, and makes use of the uniform radial distribution that will occur for a distribution of a large population of small particles in a homogeneous matrix. Extensive validation and testing with specially designed surrogate grouted sludge drums and radioactive standards have resulted in regulatory acceptance of this technique, permitting ultimate disposal of the SNF sludge drums at the Waste Isolation Pilot Plant. (authors)

Simpson, A.P. [BIL Solutions Inc, Santa Fe, NM (United States); Abdurrahman, N.M. [Fluor Hanford, Richland, WA (United States)

2007-07-01T23:59:59.000Z

350

FY 1996 solid waste integrated life-cycle forecast volume summary - Volume 1 and Volume 2  

Science Conference Proceedings (OSTI)

Solid waste forecast volumes to be generated or received ;at Westinghouse Hanford Company`s Solid Waste program over the life cycle of the site are described in this report. Previous forecast summary reports have covered only a 30-year period; however, the life-cycle approach was adopted for this FY 1996 report to ensure consistency with waste volumes reported in the 1996 Multi-Year Program Plans (MYPP). The volume data were collected on a life-cycle basis from onsite and offsite waste generators who currently ship or plan to ship solid waste to the Solid Waste program. The volumes described in detail are low-level mixed waste (LLMW) and transuranic/transuranic-mixed (TRU(M)) waste. The volumes reported in this document represent the external volume of the containers selected to ship the waste. Summary level information pertaining to low-level waste (LLW) is described in Appendix B. Hazardous waste volumes are also provided in Appendices E and F but are not described in detail since they will be managed by a commercial facility. Emphasis is placed on LLMW and TRU(M) waste because it will require processing and storage at Hanford Solid Waste`s Central Waste Complex (CORK) prior to final disposal. The LLW will generally be sent directly to disposal. The total baselines volume of LLMW and TRU(M) waste forecast to be received by the Solid Waste program (until 2070) is approximately 100,900 cubic meters. This total waste volume is composed of the following waste categories: 077,080 cubic meters of LLMW; 23,180 cubic meters of TRU(M); 640 cubic meters of greater-than-class III LLMW. This total is about 40% of the total volume reported last year (FY 1995).

Valero, O.J.

1996-02-22T23:59:59.000Z

351

ALTERNATIVES ANALYSIS FOR SELECTING ET #3 SITE  

Science Conference Proceedings (OSTI)

Engineered trenches (ETs) are considered to be a cost-effective method for disposing Low Level Waste (LLW). Based on waste forecasts from waste generators, the last engineered trench in operation (ET No.2) is anticipated to close in FY14, requiring development of a new ET. Solid Waste requested that SRNL develop an assessment report that reviews four disposal options for this new ET (ET No.3) and determine which option would provide the 'best' Performance Assessment (PA) disposal limits for LLW (Appendix A). Those four options (see option footprint locations in Figure 1-1) are: (1) Disposal at grade on TRU Pads 7-13 where soil would be mounded over waste packages; (2) Excavation at a slightly modified SLIT No.13 location - near the Used Equipment Storage Area; (3) Excavation at a modified SLIT No.12 location - near the 643-26E Naval Reactor Component Disposal Area; and (4) Excavation east of TRU Pad No.26 that replaces northeast portions of four slit trench (ST) disposal units in the eastern set of STs. The assessment consisted of both quantitative and qualitative analyses. The quantitative analysis captured key aspects that were readily quantifiable and had predictable impacts on limits and doses. A simplified modeling strategy stemming from current Special Analysis (SA) practices was employed. Both inventory capacity for a specific nuclide (a quasi-inventory limit) and overall performance for specified inventory mixtures (doses resulting from historical inventories) were considered. The qualitative analysis evaluated other key aspects based on engineering judgment in the form of pros and cons.

Collard, L.; Hamm, L.

2012-02-13T23:59:59.000Z

352

Field testing plan for unsaturated zone monitoring and field studies  

Science Conference Proceedings (OSTI)

The University of Arizona, in cooperation with the Bureau of Economic Geology at The University of Texas at Austin, and Stephens and Associates in Albuquerque, New Mexico has developed a field testing plan for evaluating subsurface monitoring systems. The U.S. Nuclear Regulatory Commission has requested development of these testing plans for low-level radioactive waste disposal sites (LLW) and for monitoring at decommissioned facilities designated under the {open_quotes}Site Decommissioning Management Plan{close_quotes} (SDMP). The tests are conducted on a 50 m by 50 m plot on the University of Arizona`s Maricopa Agricultural Center. Within the 50 m by 50 m plot one finds: (1) an instrumented buried trench, (2) monitoring islands similar to those proposed for the Ward Valley, California LLW Facility, (3) deep borehole monitoring sites, (4) gaseous transport monitoring, and (5) locations for testing non-invasive geophysical measurement techniques. The various subplot areas are instrumented with commercially available instruments such as neutron probes, time domain reflectometry probes, tensiometers, psychrometers, heat dissipation sensors, thermocouples, solution samplers, and cross-hole geophysics electrodes. Measurement depths vary from ground surface to 15 m. The data from the controlled flow and transport experiments, conducted over the plot, will be used to develop an integrated approach to long-term monitoring of the vadose zone at waste disposal sites. The data will also be used to test field-scale flow and transport models. This report describes in detail the design of the experiment and the methodology proposed for evaluating the data.

Young, M.H.; Wierenga, P.J.; Warrick, A.W. [and others

1996-10-01T23:59:59.000Z

353

PUBLIC AND REGULATORY ACCEPTANCE OF BLENDING OF RADIOACTIVE WASTE VS DILUTION  

SciTech Connect

On April 21, 2009, the Energy Facilities Contractors Group (EFCOG) Waste Management Working Group (WMWG) provided a recommendation to the Department of Energy's Environmental Management program (DOE-EM) concerning supplemental guidance on blending methodologies to use to classify waste forms to determine if the waste form meets the definition of Transuranic (TRU) Waste or can be classified as Low-Level Waste (LLW). The guidance provides specific examples and methods to allow DOE and its Contractors to properly classify waste forms while reducing the generation of TRU wastes. TRU wastes are much more expensive to characterize at the generator's facilities, ship, and then dispose at the Waste Isolation Pilot Plant (WIPP) than Low-Level Radioactive Waste's disposal. Also the reduction of handling and packaging of LLW is inherently less hazardous to the nuclear workforce. Therefore, it is important to perform the characterization properly, but in a manner that minimizes the generation of TRU wastes if at all possible. In fact, the generation of additional volumes of radioactive wastes under the ARRA programs, this recommendation should improve the cost effective implementation of DOE requirements while properly protecting human health and the environment. This paper will describe how the message of appropriate, less expensive, less hazardous blending of radioactive waste is the 'right' thing to do in many cases, but can be confused with inappropriate 'dilution' that is frowned upon by regulators and stakeholders in the public. A proposal will be made in this paper on how to communicate this very complex and confusing technical issue to regulatory bodies and interested stakeholders to gain understanding and approval of the concept. The results of application of the proposed communication method and attempt to change the regulatory requirements in this area will be discussed including efforts by DOE and the NRC on this very complex subject.

Goldston, W.

2010-11-30T23:59:59.000Z

354

Feed Materials Production Center Waste Management Plan  

SciTech Connect

In the process of producing uranium metal products used in Department of Energy (DOE) defense programs at other DOE facilities, various types of wastes are generated at the Feed Materials Production Center (FMPC). Process wastes, both generated and stored, are discussed in the Waste Management Plan and include low-level radioactive waste (LLW), mixed hazardous/radioactive waste, and sanitary/industrial waste. Scrap metal waste and wastes requiring special remediation are also addressed in the Plan. The Waste Management Plan identifies the comprehensive programs developed to address safe storage and disposition of all wastes from past, present, and future operations at the FMPC. Waste streams discussed in this Plan are representative of the waste generated and waste types that concern worker and public health and safety. Budgets and schedules for implementation of waste disposition are also addressed. The waste streams receiving the largest amount of funding include LLW approved for shipment by DOE/ORO to the Nevada Test Site (NTS) (MgF/sub 2/, slag leach filter cake, and neutralized raffinate); remedial action wastes (waste pits, K-65 silo waste); thorium; scrap metal (contaminated and noncontaminated ferrous and copper scrap); construction rubble and soil generated from decontamination and decommissioning of outdated facilities; and low-level wastes that will be handled through the Low-Level Waste Processing and Shipping System (LLWPSS). Waste Management milestones are also provided. The Waste Management Plan is divided into eight major sections: Introduction; Site Waste and Waste Generating Process; Strategy; Projects and Operations; Waste Stream Budgets; Milestones; Quality Assurance for Waste Management; and Environmental Monitoring Program.

Watts, R.E.; Allen, T.; Castle, S.A.; Hopper, J.P.; Oelrich, R.L.

1986-12-31T23:59:59.000Z

355

Feed Materials Production Center waste management plan (Revision to NLCO-1100, R. 6)  

Science Conference Proceedings (OSTI)

In the process of producing uranium metal products used in Department of Energy (DOE) defense programs at other DOE facilities, various types of wastes are generated at the Feed Materials Production Center (FMPC). Process wastes, both generated and stored, are discussed in the Waste Management Plan and include low-level radioactive waste (LLW), mixed hazardous/radioactive waste, and sanitary/industrial waste. Scrap metal waste and wastes requiring special remediation are also addressed in the Plan. The Waste Management Plan identifies the comprehensive programs developed to address safe storage and disposition of all wastes from past, present, and future operations at the FMPC. Waste streams discussed in this Plan are representative of the wastes generated and waste types that concern worker and public health and safety. Budgets and schedules for implementation of waste disposition are also addressed. The waste streams receiving the largest amount of funding include LLW approved for shipment by DOE/ORO to the Nevada Test Site (NTS) (MgF/sub 2/, slag leach filter cake, and neutralized raffinate); remedial action wastes (waste pits, K-65 silo waste); thorium; scrap metal (contaminated and noncontaminated ferrous and copper scrap); construction rubble and soil generated from decontamination and decommissioning of outdated facilities; and low-level wastes that will be handled through the Low-Level Waste Processing and Shipping System (LLWPSS). Waste Management milestones are also provided. The Waste Management Plan is divided into eight major sections: Introduction; Site Waste and Waste Generating Process; Strategy; Projects and Operations; Waste Stream Budgets; Milestones; Quality Assurance for Waste Management; and Environmental Monitoring Program.

Watts, R.E.; Allen, T.; Castle, S.A.; Hopper, J.P.; Oelrich, R.L.

1986-10-15T23:59:59.000Z

356

An Experimental Study of Diffusivity of Technetium-99 in Hanford Vadose Zone Sediments  

Science Conference Proceedings (OSTI)

One of the methods being considered at the Hanford site in Washington for safely disposing of low-level radioactive wastes (LLW) is to encase the waste in concrete and entomb the packages in the Hanford vadose zone sediments. The current plan for waste isolation consists of stacking low-level waste packages on a trench floor, surrounding the stacks with reinforced steel, and encasing these packages with concrete. Any failure of the concrete encasement may result in water intrusion and consequent mobilization of radionuclides from the waste packages. The mobilized radionuclides may escape from the encased concrete by mass flow and/or diffusion and move into the surrounding subsurface sediments. It is therefore necessary to conduct an assessment of the performance of the concrete encasement structure and the surrounding soils ability to retard radionuclide migration. The retardation factors for radionuclides contained in the waste packages can be determined from measurements of diffusion coefficients for these contaminants through concrete and fill material. Because of their anionic nature in aqueous solutions, the radionuclides, 99Tc and 129I were identified as long-term dose contributors in LLW. The leachability and/or diffusion of these radionuclide species must be measured in order to assess the long-term performance of waste grouts when contacted with vadose-zone porewater or groundwater. To measure the diffusivity, a set of experiments were conducted using 99Tc-spiked concrete (with 0 and 4% metallic iron additions) in contact with unsaturated soil half-cells that reflected the typical moisture contents of Hanford vadose zone sediments. The 99Tc diffusion profiles in the soil half cells were measured after a time lapse of ~1.9 yr. Using the concentration profiles, the 99Tc diffusivity coefficients were calculated based on Ficks Second Law.

Mattigod, Shas V.; Bovaird, Chase C.; Wellman, Dawn M.; Parker, Kent E.; Wood, Marcus I.

2012-11-01T23:59:59.000Z

357

Use of engineered soils and other site modifications for low-level radioactive waste disposal  

SciTech Connect

The U.S. Nuclear Regulatory Commission requires that low-level radioactive waste (LLW) disposal facilities be designed to minimize contact between waste and infiltrating water through the use of site design features. The purpose of this investigation is to identify engineered barriers and evaluate their ability to enhance the long-term performance of an LLW disposal facility. Previously used barriers such as concrete overpacks, vaults, backfill, and engineered soil covers, are evaluated as well as state-of-the-art barriers, including an engineered sorptive soil layer underlying a facility and an advanced design soil cover incorporating a double-capillary layer. The purpose of this investigation is also to provide information in incorporating or excluding specific engineered barriers as part of new disposal facility designs. Evaluations are performed using performance assessment modeling techniques. A generic reference disposal facility design is used as a baseline for comparing the improvements in long-term performance offered by designs incorporating engineered barriers in generic and humid environments. These evaluations simulate water infiltration through the facility, waste leaching, radionuclide transport through the facility, and decay and ingrowth. They also calculate a maximum (peak annual) dose for each disposal system design. A relative dose reduction factor is calculated for each design evaluated. The results of this investigation are presented for concrete overpacks, concrete vaults, sorptive backfill, sorptive engineered soil underlying the facility, and sloped engineered soil covers using a single-capillary barrier and a double-capillary barrier. Designs using combinations of barriers are also evaluated. These designs include a vault plus overpacks, sorptive backfill plus overpacks, and overpack with vault plus sorptive backfill, underlying sorptive soil, and engineered soil cover.

Not Available

1994-08-01T23:59:59.000Z

358

CHARACTERIZING THE GALACTIC WHITE DWARF BINARY POPULATION WITH SPARSELY SAMPLED RADIAL VELOCITY DATA  

Science Conference Proceedings (OSTI)

We present a method to characterize statistically the parameters of a detached binary sample-binary fraction, separation distribution, and mass-ratio distribution-using noisy radial velocity data with as few as two, randomly spaced, epochs per object. To do this, we analyze the distribution of {Delta}RV{sub max}, the maximum radial velocity difference between any two epochs for the same object. At low values, the core of this distribution is dominated by measurement errors, but for large enough samples there is a high-velocity tail that can effectively constrain the parameters of the binary population. We discuss our approach for the case of a population of detached white dwarf (WD) binaries with separations that are decaying via gravitational wave emission. We derive analytic expressions for the present-day distribution of separations, integrated over the star formation history of the Galaxy, for parameterized initial WD separation distributions at the end of the common-envelope phase. We use Monte Carlo techniques to produce grids of simulated {Delta}RV{sub max} distributions with specific binary population parameters, and the same sampling cadences and radial velocity errors as the observations, and we compare them to the real {Delta}RV{sub max} distribution to constrain the properties of the binary population. We illustrate the sensitivity of the method to both the model and observational parameters. In the particular case of binary WDs, every model population predicts a merger rate per star which can easily be compared to specific Type Ia supernova rates. In a companion paper, we apply the method to a sample of {approx}4000 WDs from the Sloan Digital Sky Survey. The binary fractions and separation distribution parameters allowed by the data indicate a rate of WD-WD mergers per unit stellar mass in the Galactic disk, {approx}1 Multiplication-Sign 10{sup -13} mergers yr{sup -1} M{sup -1}{sub Sun }, remarkably similar to the rate per unit mass of Type Ia supernovae in Milky Way like galaxies.

Maoz, Dan; Badenes, Carles [School of Physics and Astronomy, Tel Aviv University, Tel Aviv 69978 (Israel); Bickerton, Steven J., E-mail: maoz@astro.tau.ac.il, E-mail: badenes@pitt.edu, E-mail: bick@astro.princeton.edu [Department of Astrophysical Sciences, Princeton University, Peyton Hall, Ivy Lane, Princeton, NJ 08544-1001 (United States)

2012-06-01T23:59:59.000Z

359

Auger line shape and electron energy loss spectroscopy analysis of amorphous, microcrystalline, and. beta. -SiC  

DOE Green Energy (OSTI)

Auger electron spectroscopy (AES) line shape analysis of the Si-{ital L}{sub 23}{ital VV} and C-{ital KLL} peaks has been performed in conjunction with electron energy loss spectroscopy (EELS) on Hg-sensitized photodeposited amorphous and microcyrstalline SiC films. Mixtures of SiH{sub 4}/CH{sub 3}SiH{sub 3} and SiH{sub 4}/(CH{sub 3}){sub 2}SiH{sub 2} with helium or hydrogen dilution were used for the depositions. AES line shape and EELS analyses were also performed on {beta}-SiC for comparison. Quantitative bulk compositional analysis to determine the Si and C concentrations in these films was performed with an electron microprobe (EMPA) using x-ray wavelength dispersive spectroscopy (WDS). AES and EELS results reveal the predominant Si--C bonding and relative crystallinity in the films as a function of deposition parameters, which includes the gas mixture, pressure, and H{sub 2}/He dilution. These parameters determine the H radical flux during growth, which leads to changes in the film structure.

Nelson, A.J.; Mason, A.R.; Swartzlander, A.B.; Kazmerski, L.L. (Solar Energy Research Institute, Golden, CO (USA)); Saxena, N.; Fortmann, C.M.; Russell, T.W.F. (Institute of Energy Conversion, University of Delaware, Newark, DE (USA))

1990-05-01T23:59:59.000Z

360

Rapid Orbital Decay in the 12.75-minute WD+WD Binary J0651+2844  

E-Print Network (OSTI)

We report the detection of orbital decay in the 12.75-min, detached binary white dwarf (WD) SDSS J065133.338+284423.37 (hereafter J0651). Our photometric observations over a 13-month baseline constrain the orbital period to 765.206543(55) s and indicate the orbit is decreasing as a rate of (-9.8 +/- 2.8) x 10^(-12) s/s (or -0.31 +/- 0.09 ms/yr). We revise the system parameters based on our new photometric and spectroscopic observations: J0651 contains two WDs with M1 = 0.26 +/- 0.04 Msun and M2 = 0.50 +/- 0.04 Msun. General relativity predicts orbital decay due to gravitational wave radiation of (-8.2 +/- 1.7) x 10^(-12) s/s (or -0.26 +/- 0.05 ms/yr). Our observed rate of orbital decay is consistent with this expectation. J0651 is currently the second-loudest gravitational wave source known in the milli-Hertz range and the loudest non-interacting binary, which makes it an excellent verification source for future missions aimed at directly detecting gravitational waves. Our work establishes the feasibility of ...

Hermes, J J; Brown, Warren R; Winget, D E; Prieto, Carlos Allende; Gianninas, A; Mukadam, Anjum S; Cabrera-Lavers, Antonio; Kenyon, Scott J

2012-01-01T23:59:59.000Z

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361

Type Iax Supernovae: A New Class of Stellar Explosion  

E-Print Network (OSTI)

We describe observed properties of the Type Iax class of supernovae (SNe Iax), consisting of SNe observationally similar to its prototypical member, SN 2002cx. The class currently has 25 members, and we present optical photometry and/or optical spectroscopy for most of them. SNe Iax are spectroscopically similar to SNe Ia, but have lower maximum-light velocities (2000 M_V,peak > -18.9 mag), and most have hot photospheres. Relative to SNe Ia, SNe Iax have low luminosities for their light-curve shape. There is a correlation between luminosity and light-curve shape, similar to that of SNe Ia, but offset from that of SNe Ia and with larger scatter. Despite a host-galaxy morphology distribution that is highly skewed to late-type galaxies without any SNe Iax discovered in elliptical galaxies, there are several indications that the progenitor stars are white dwarfs (WDs): evidence of C/O burning in their maximum-light spectra, low ejecta masses, strong Fe lines in their late-time spectra, a lack of X-ray detections...

Foley, Ryan J; Chornock, R; Ganeshalingam, M; Li, W; Marion, G H; Morrell, N I; Pignata, G; Stritzinger, M D; Silverman, J M; Wang, X; Anderson, J P; Filippenko, A V; Freedman, W L; Hamuy, M; Jha, S W; Kirshner, R P; McCully, C; Persson, S E; Phillips, M M; Reichart, D E; Soderberg, A M

2012-01-01T23:59:59.000Z

362

An Experimental Platform for Creating White Dwarf Photospheres in the Laboratory  

E-Print Network (OSTI)

We present an experimental platform for measuring hydrogen Balmer emission and absorption line profiles for plasmas with white dwarf (WD) photospheric conditions (T_e ~ 1 eV, n_e ~ 10^17 cm^-3). These profiles will be used to benchmark WD atmosphere models, which, used with the spectroscopic method, are responsible for determining fundamental parameters (e.g., effective temperature, mass) for tens of thousands of WDs. Our experiment, performed at the Z Pulsed Power Facility at Sandia National Laboratories, uses the large amount of x-rays generated from a z-pinch dynamic hohlraum to drive plasma formation in a gas cell. The platform is unique compared to past hydrogen line profile experiments in that the plasma is radiation-driven. This decouples the heating source from the plasma to be studied in the sense that the radiation temperature causing the photoionization is independent of the initial conditions of the gas. For the first time we measure hydrogen Balmer lines in absorption at these conditions in the l...

Falcon, Ross E; Bailey, J E; Ellis, J L; Carlson, A L; Gomez, T A; Montgomery, M H; Winget, D E; Chen, E Y; Gomez, M R; Nash, T J

2012-01-01T23:59:59.000Z

363

An Experimental Platform for Creating White Dwarf Photospheres in the Laboratory  

E-Print Network (OSTI)

We present an experimental platform for measuring hydrogen Balmer emission and absorption line profiles for plasmas with white dwarf (WD) photospheric conditions (T_e ~ 1 eV, n_e ~ 10^17 cm^-3). These profiles will be used to benchmark WD atmosphere models, which, used with the spectroscopic method, are responsible for determining fundamental parameters (e.g., effective temperature, mass) for tens of thousands of WDs. Our experiment, performed at the Z Pulsed Power Facility at Sandia National Laboratories, uses the large amount of x-rays generated from a z-pinch dynamic hohlraum to drive plasma formation in a gas cell. The platform is unique compared to past hydrogen line profile experiments in that the plasma is radiation-driven. This decouples the heating source from the plasma to be studied in the sense that the radiation temperature causing the photoionization is independent of the initial conditions of the gas. For the first time we measure hydrogen Balmer lines in absorption at these conditions in the laboratory for the purpose of benchmarking Stark-broadened line shapes. The platform can be used to study other plasma species and to explore non-LTE, time-dependent collisional-radiative atomic kinetics.

Ross E. Falcon; G. A. Rochau; J. E. Bailey; J. L. Ellis; A. L. Carlson; T. A. Gomez; M. H. Montgomery; D. E. Winget; E. Y. Chen; M. R. Gomez; T. J. Nash

2012-10-26T23:59:59.000Z

364

THE FAST-ROTATING, LOW-GRAVITY SUBDWARF B STAR EC 22081-1916: REMNANT OF A COMMON ENVELOPE MERGER EVENT  

Science Conference Proceedings (OSTI)

Hot subdwarf B stars (sdBs) are evolved core helium-burning stars with very thin hydrogen envelopes. In order to form an sdB, the progenitor has to lose almost all of its hydrogen envelope right at the tip of the red-giant branch. In binary systems, mass transfer to the companion provides the extraordinary mass loss required for their formation. However, apparently single sdBs exist as well and their formation has been unclear for decades. The merger of helium white dwarfs (He-WDs) leading to an ignition of core helium burning or the merger of a helium core and a low-mass star during the common envelope phase have been proposed as processes leading to sdB formation. Here we report the discovery of EC 22081-1916 as a fast-rotating, single sdB star of low gravity. Its atmospheric parameters indicate that the hydrogen envelope must be unusually thick, which is at variance with the He-WD merger scenario, but consistent with a common envelope merger of a low-mass, possibly substellar object with a red-giant core.

Geier, S.; Classen, L.; Heber, U., E-mail: geier@sternwarte.uni-erlangen.de [Dr. Karl Remeis-Observatory and ECAP, Astronomical Institute, Friedrich-Alexander University Erlangen-Nuremberg, Sternwartstr. 7, D 96049 Bamberg (Germany)

2011-05-20T23:59:59.000Z

365

ON THE NATURE OF THE PROGENITOR OF THE Type Ia SN2011fe IN M101  

SciTech Connect

The explosion of a Type Ia supernova, SN2011fe, in the nearby Pinwheel galaxy (M101 at 6.4 Mpc) provides an opportunity to study pre-explosion images and search for the progenitor, which should consist of a white dwarf (WD), possibly surrounded by an accretion disk, in orbit with another star. We report on our use of deep Chandra observations and Hubble Space Telescope observations to limit the luminosity and temperature of the pre-explosion WD. It is found that if the spectrum was a blackbody, then pre-SN WDs with steady nuclear burning of the highest possible temperatures and luminosities are excluded assuming moderate n{sub H} values, but values of kT between roughly 10 eV and 60 eV are permitted even if the WD was emitting at the Eddington luminosity. This allows the progenitor to be an accreting nuclear-burning WD with an expanded photosphere 4-100 times the WD itself, or a super-critically accreting WD blowing off an optically thick strong wind, or possibly a recurrent nova with luminosities an order of magnitude lower than Eddington. The observations are also consistent with a double degenerate scenario, or a spinning down WD that has been spun up by accretion from the donor.

Liu Jifeng [National Astronomical Observatory of China, Beijing 100012 (China); Di Stefano, Rosanne; Wang Tao; Moe, Maxwell [Harvard-Smithsonian Center for Astrophysics, 60 Garden Street, Cambridge, MA 02138 (United States)

2012-04-20T23:59:59.000Z

366

AN EVALUATION OF POTENTIAL LINER MATERIALS FOR ELIMINATING FCCI IN IRRADIATED METALLIC NUCLEAR FUEL ELEMENTS  

Science Conference Proceedings (OSTI)

Metallic nuclear fuels are being looked at as part of the Global Nuclear Energy Program for transmuting longlive transuranic actinide isotopes contained in spent nuclear fuel into shorter-lived fission products. In order to optimize the performance of these fuels, the concept of using liners to eliminate the fuel/cladding chemical interactions that can occur during irradiation of a fuel element has been investigated. The potential liner materials Zr and V have been tested using solid-solid diffusion couples, consisting of liner materials butted against fuel alloys and against cladding materials. The couples were annealed at the relatively high temperature of 700C. This temperature would be the absolute maximum temperature present at the fuel/cladding interface for a fuel element in-reactor. Analysis was performed using a scanning electron microscope equipped with energy-dispersive and wavelengthdispersive spectrometers (SEM/EDS/WDS) to evaluate any developed diffusion structures. At 700C, minimal interaction was observed between the metallic fuels and either Zr or V. Similarly, limited interaction was observed between the Zr and V and the cladding materials. The best performing liner material appeared to be the V, based on amounts of interaction.

D. D. Keiser; J. I. Cole

2007-09-01T23:59:59.000Z

367

Los Alamos: MST-MTM: EML: Electron Microscopy Laboratory  

NLE Websites -- All DOE Office Websites (Extended Search)

Electron Microscopy Laboratory, MST-6 Electron Microscopy Laboratory, MST-6 MST-6 Home Home In the MSL FEI Tecnai F30 Analytical TEM/STEM JEOL 6300FXV High Resolution SEM JEOL 3000F High Resolution Transmission Electron Microscope Philips XL30 F Scanning Electron Microscope & Orientation Imaging System Phillips CM30 Transmission Electron Microscope In the Sigma Building JEOL 840 EPMA with Wavelength Dispersive Spectroscopy FEI Strata DB235 FIB/SEM FEI XL30 Environmental Scanning Electron Microscope & Orientation Imaging System CONTACTS Bob Field 665.3938 Pat Dickerson 665.3036 Rob Dickerson 667.6337 Rod McCabe 606.1649 The Electron Microscopy Laboratory's Capabilities The Electron Microscopy Laboratory's Capabilities The Electron Microscopy Laboratory (EML) is part of MST-6, the Materials Technology - Metallurgy Group within the Materials Science and Technology Division at Los Alamos National Laboratory. It is a facility dedicated to the characterization of materials primarily through imaging, chemical, and crystallographic analyses of material microstructures with several electron and ion beam instruments. Accessory characterization techniques and equipment include energy dispersive x-ray analysis (EDS), wavelength dispersive x-ray analysis (WDS), electron backscatter diffraction (EBSD) and orientation imaging microscopy (OIM), and electron energy loss spectroscopy (EELS).

368

Closure Report for Corrective Action Unit 166: Storage Yards and Contaminated Materials, Nevada Test Site, Nevada  

Science Conference Proceedings (OSTI)

Corrective Action Unit (CAU) 166 is identified in the Federal Facility Agreement and Consent Order (FFACO) as 'Storage Yards and Contaminated Materials' and consists of the following seven Corrective Action Sites (CASs), located in Areas 2, 3, 5, and 18 of the Nevada Test Site: CAS 02-42-01, Condo Release Storage Yd - North; CAS 02-42-02, Condo Release Storage Yd - South; CAS 02-99-10, D-38 Storage Area; CAS 03-42-01, Conditional Release Storage Yard; CAS 05-19-02, Contaminated Soil and Drum; CAS 18-01-01, Aboveground Storage Tank; and CAS 18-99-03, Wax Piles/Oil Stain. Closure activities were conducted from March to July 2009 according to the FF ACO (1996, as amended February 2008) and the Corrective Action Plan for CAU 166 (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, 2007b). The corrective action alternatives included No Further Action and Clean Closure. Closure activities are summarized. CAU 166, Storage Yards and Contaminated Materials, consists of seven CASs in Areas 2, 3, 5, and 18 of the NTS. The closure alternatives included No Further Action and Clean Closure. This CR provides a summary of completed closure activities, documentation of waste disposal, and confirmation that remediation goals were met. The following site closure activities were performed at CAU 166 as documented in this CR: (1) At CAS 02-99-10, D-38 Storage Area, approximately 40 gal of lead shot were removed and are currently pending treatment and disposal as MW, and approximately 50 small pieces of DU were removed and disposed as LLW. (2) At CAS 03-42-01, Conditional Release Storage Yard, approximately 7.5 yd{sup 3} of soil impacted with lead and Am-241 were removed and disposed as LLW. As a BMP, approximately 22 ft{sup 3} of asbestos tile were removed from a portable building and disposed as ALLW, approximately 55 gal of oil were drained from accumulators and are currently pending disposal as HW, the portable building was removed and disposed as LLW, and accumulators, gas cylinders, and associated debris were removed and are currently pending treatment and disposal as MW. (3) At CAS 05-19-02, Contaminated Soil and Drum, as a BMP, an empty drum was removed and disposed as sanitary waste. (4) At CAS 18-01-01, Aboveground Storage Tank, approximately 165 gal of lead-impacted liquid were removed and are currently pending disposal as HW, and approximately 10 gal of lead shot and 6 yd{sup 3} of wax embedded with lead shot were removed and are currently pending treatment and disposal as MW. As a BMP, approximately 0.5 yd{sup 3} of wax were removed and disposed as hydrocarbon waste, approximately 55 gal of liquid were removed and disposed as sanitary waste, and two metal containers were grouted in place. (5) At CAS 18-99-03, Wax Piles/Oil Stain, no further action was required; however, as a BMP, approximately l.5 yd{sup 3} of wax were removed and disposed as hydrocarbon waste, and one metal container was grouted in place.

NSTec Environmental Restoration

2009-08-01T23:59:59.000Z

369

Application for a Permit to Operate a Class III Solid Waste Disposal Site at the Nevada National Security Site Area 5 Asbestiform Low-Level Solid Waste Disposal Site  

Science Conference Proceedings (OSTI)

The Nevada National Security Site (NNSS) is located approximately 105 km (65 mi) northwest of Las Vegas, Nevada. The U.S. Department of Energy National Nuclear Security Administration Nevada Site Office (NNSA/NSO) is the federal lands management authority for the NNSS and National Security Technologies, LLC (NSTec) is the Management and Operations contractor. Access on and off the NNSS is tightly controlled, restricted, and guarded on a 24-hour basis. The NNSS is posted with signs along its entire perimeter. NSTec is the operator of all solid waste disposal sites on the NNSS. The Area 5 Radioactive Waste Management Site (RWMS) is the location of the permitted facility for the Solid Waste Disposal Site (SWDS). The Area 5 RWMS is located near the eastern edge of the NNSS (Figure 1), approximately 26 km (16 mi) north of Mercury, Nevada. The Area 5 RWMS is used for the disposal of low-level waste (LLW) and mixed low-level waste. Many areas surrounding the RWMS have been used in conducting nuclear tests. The site will be used for the disposal of regulated Asbestiform Low-Level Waste (ALLW), small quantities of low-level radioactive hydrocarbon-burdened (LLHB) media and debris, LLW, LLW that contains Polychlorinated Biphenyl (PCB) Bulk Product Waste greater than 50 ppm that leaches at a rate of less than 10 micrograms of PCB per liter of water, and small quantities of LLHB demolition and construction waste (hereafter called permissible waste). Waste containing free liquids, or waste that is regulated as hazardous waste under the Resource Conservation and Recovery Act (RCRA) or state-of-generation hazardous waste regulations, will not be accepted for disposal at the site. Waste regulated under the Toxic Substances Control Act (TSCA) that will be accepted at the disposal site is regulated asbestos-containing materials (RACM) and PCB Bulk Product Waste greater than 50 ppm that leaches at a rate of less than 10 micrograms of PCB per liter of water. The term asbestiform is used throughout this document to describe RACM. The disposal site will be used as a depository of permissible waste generated both on site and off site. All generators designated by NNSA/NSO will be eligible to dispose regulated ALLW at the Asbestiform Low-Level Waste Disposal Site in accordance with the DOE/NV-325, Nevada National Security Site Waste Acceptance Criteria (NNSSWAC, current revision). Approval will be given by NNSA/NSO to generators that have successfully demonstrated through process knowledge (PK) and/or sampling and analysis that the waste is low-level, contains asbestiform material, or contains PCB Bulk Product Waste greater than 50 ppm that leaches at a rate of less than 10 micrograms of PCB per liter of water, or small quantities of LLHB demolition and construction waste and does not contain prohibited waste materials. Each waste stream will be approved through the Radioactive Waste Acceptance Program (RWAP), which ensures that the waste meets acceptance requirements outlined in the NNSSWAC.

NSTec Environmental Programs

2010-10-04T23:59:59.000Z

370

Evaluation of Low-Level Waste Disposal Receipt Data for Los Alamos National Laboratory Technical Area 54, Area G Disposal Facility - Fiscal Year 2011  

Science Conference Proceedings (OSTI)

The Los Alamos National Laboratory (LANL or the Laboratory) generates radioactive waste as a result of various activities. Operational or institutional waste is generated from a wide variety of research and development activities including nuclear weapons development, energy production, and medical research. Environmental restoration (ER), and decontamination and decommissioning (D and D) waste is generated as contaminated sites and facilities at LANL undergo cleanup or remediation. The majority of this waste is low-level radioactive waste (LLW) and is disposed of at the Technical Area 54 (TA-54), Area G disposal facility. U.S. Department of Energy (DOE) Order 435.1 (DOE, 2001) requires that radioactive waste be managed in a manner that protects public health and safety, and the environment. To comply with this order, DOE field sites must prepare and maintain site-specific radiological performance assessments for LLW disposal facilities that accept waste after September 26, 1988. Furthermore, sites are required to conduct composite analyses that account for the cumulative impacts of all waste that has been (or will be) disposed of at the facilities and other sources of radioactive material that may interact with the facilities. Revision 4 of the Area G performance assessment and composite analysis was issued in 2008 (LANL, 2008). These analyses estimate rates of radionuclide release from the waste disposed of at the facility, simulate the movement of radionuclides through the environment, and project potential radiation doses to humans for several on-site and off-site exposure scenarios. The assessments are based on existing site and disposal facility data and on assumptions about future rates and methods of waste disposal. The accuracy of the performance assessment and composite analysis depends upon the validity of the data used and assumptions made in conducting the analyses. If changes in these data and assumptions are significant, they may invalidate or call into question certain aspects of the analyses. For example, if the volumes and activities of waste disposed of during the remainder of the disposal facility's lifetime differ significantly from those projected, the doses projected by the analyses may no longer apply. DOE field sites are required to implement a performance assessment and composite analysis maintenance program. The purpose of this program is to ensure the continued applicability of the analyses through incremental improvement of the level of understanding of the disposal site and facility. Site personnel are required to conduct field and experimental work to reduce the uncertainty in the data and models used in the assessments. Furthermore, they are required to conduct periodic reviews of waste receipts, comparing them to projected waste disposal rates. The radiological inventory for Area G was updated in conjunction with Revision 4 of the performance assessment and composite analysis (Shuman, 2008). That effort used disposal records and other sources of information to estimate the quantities of radioactive waste that have been disposed of at Area G from 1959, the year the facility started receiving waste on a routine basis, through 2007. It also estimated the quantities of LLW that will require disposal from 2008 through 2044, the year in which it is assumed that disposal operations at Area G will cease. This report documents the fourth review of Area G disposal receipts since the inventory was updated and examines information for waste placed in the ground during fiscal years (FY) 2008 through 2011. The primary objective of the disposal receipt review is to ensure that the future waste inventory projections developed for the performance assessment and composite analysis are consistent with the actual types and quantities of waste being disposed of at Area G. Toward this end, the disposal data that are the subject of this review are used to update the future waste inventory projections for the disposal facility. These projections are compared to the future inventory projections that were develope

French, Sean B. [Los Alamos National Laboratory; Shuman, Robert [WPS: WASTE PROJECTS AND SERVICES

2012-04-17T23:59:59.000Z

371

Repackaging Rocky Flats Legacy Transuranic Waste  

Science Conference Proceedings (OSTI)

Repackaging legacy Transuranic (TRU), Transuranic Mixed (TRM), Low Level Waste (LLW), and Low Level Mixed (LLM) waste requires good characterization skills and the ability to adapt to less than ideal conditions. Repackaging legacy waste in a facility that is not undergoing Decontamination and Decommission (D and D) is optimum. However, repackaging any waste in a D and D facility, under cold and dark conditions, can be difficult. Cold and dark conditions are when the heating and air conditioning are no longer in service and the lighting consists of strands of lights hung throughout each of the rooms. Working under these conditions adds an additional level of stress and danger that must be addressed. The use of glovebags was very useful at Rocky Flats during the D and D of many buildings. Glovebags can be adapted for many different types of wastes and unusual conditions. Repackaging of legacy TRU waste, in a D and D facility, can be accomplished safely and cost effectively with the use of glovebags. In conclusion: the use of glovebags to repackage legacy TRU, TRM, LLW, or LLM waste was done safely and cost effectively at Rocky Flats. The cost of using glovebags was minimal. Glovebags are easily adaptable to whatever the waste configuration is. The use of glovebags, for repackaging of Legacy waste, allows D and D efforts to stay on schedule and on task. Without the use of glovebags, additional gloveboxes would have been required at Rocky Flats. Larger items, such as the HEPA filters, would have required the construction of a new large item repackaging glovebox. Repackaging in glovebags allows the freedom to either locate the glovebag by the waste or locate the glovebag in a place that least impacts D and D efforts. The use of glovebags allowed numerous configurations of waste to be repackaged without the use of gloveboxes. During the D and D of the Rocky Flats facility, which was in a cold and dark stage, D and D work was not impacted by the repackaging activity. Glovebags work well in facilities that are in the process of D and D or still in full operations because glovebags are very safe and cost effective.

McTaggart, Jerri Lynne [Los Alamos National Laboratory, 115 N. Main St., Carlsbad, New Mexico, 88220 (United States)

2008-01-15T23:59:59.000Z

372

Assessing Potential Exposure from Truck Transport of Low-level Radioactive Waste to the Nevada Test Site  

SciTech Connect

This study has shown that, based upon measurements from industry standard radiation detection instruments, such as the RS model RSS-131 PICs in a controlled configuration, a person may be exposed to gamma radiation above background when in close proximity to some LLW trucks. However, in approximately half (47.7 percent) the population of trucks measured in this study, a person would receive no exposure above background at a distance of 1.0 m (3.3 ft) away from a LLW truck. An additional 206 trucks had net exposures greater than zero, but equal to or less than 1 {micro}R/h. Finally, nearly 80 percent of the population of trucks (802 of 1,012) had net exposures less than or equal to 10 {micro}R/h. Although there are no shipping or exposure standards at 1.0 m (3.3 ft) distance, one relevant point of comparison is the DOT shipping standard of 10 mrem/h at 2.0 m (6.6 ft) distance. Assuming a one-to-one correspondence between Roentgens and Rems, then 903 trucks (89.2 percent of the trucks measured) were no greater than one percent of the DOT standard at 1.0 m (3.3 ft). Had the distance at which the trucks been measured increased to 2.0 m (6.6 ft), the net exposure would be even less because of the increase in distance between the truck and the receptor. However, based on the empirical data from this study, the rate of decrease may be slower than for either a point or line source as was done for previous studies (Gertz, 2001; Davis et al., 2001). The highest net exposure value at 1.0 m (3.3 ft) distance, 11.9 mR/h, came from the only truck with a value greater than 10 mR/h at 1.0 m (3.3 ft) distance.

J. Miller; D. Shafer; K. Gray; B. Church; S.Campbell; B. Holz

2005-08-15T23:59:59.000Z

373

Evolution Of USDOE Performance Assessments Over 20 Years  

SciTech Connect

Performance assessments (PAs) have been used for many years for the analysis of post-closure hazards associated with a radioactive waste disposal facility and to provide a reasonable expectation of the ability of the site and facility design to meet objectives for the protection of members of the public and the environment. The use of PA to support decision-making for LLW disposal facilities has been mandated in United States Department of Energy (USDOE) directives governing radioactive waste management since 1988 (currently DOE Order 435.1, Radioactive Waste Management). Prior to that time, PAs were also used in a less formal role. Over the past 20+ years, the USDOE approach to conduct, review and apply PAs has evolved into an efficient, rigorous and mature process that includes specific requirements for continuous improvement and independent reviews. The PA process has evolved through refinement of a graded and iterative approach designed to help focus efforts on those aspects of the problem expected to have the greatest influence on the decision being made. Many of the evolutionary changes to the PA process are linked to the refinement of the PA maintenance concept that has proven to be an important element of USDOE PA requirements in the context of supporting decision-making for safe disposal of LLW. The PA maintenance concept represents the evolution of the graded and iterative philosophy and has helped to drive the evolution of PAs from a deterministic compliance calculation into a systematic approach that helps to focus on critical aspects of the disposal system in a manner designed to provide a more informed basis for decision-making throughout the life of a disposal facility (e.g., monitoring, research and testing, waste acceptance criteria, design improvements, data collection, model refinements). A significant evolution in PA modeling has been associated with improved use of uncertainty and sensitivity analysis techniques to support efficient implementation of the graded and iterative approach. Rather than attempt to exactly predict the migration of radionuclides in a disposal unit, the best PAs have evolved into tools that provide a range of results to guide decision-makers in planning the most efficient, cost effective, and safe disposal of radionuclides.

Seitz, Roger R. [Savannah River Site (SRS), Aiken, SC (United States); Suttora, Linda C. [U.S. Department of Energy, Office of Site Restoration, Germantown, MD (United States)

2013-02-26T23:59:59.000Z

374

Closure Report for Corrective Action Unit 139: Waste Disposal Sites, Nevada Test Site, Nevada  

SciTech Connect

Corrective Action Unit (CAU) 139 is identified in the Federal Facility Agreement and Consent Order (FFACO) as 'Waste Disposal Sites' and consists of the following seven Corrective Action Sites (CASs), located in Areas 3, 4, 6, and 9 of the Nevada Test Site: CAS 03-35-01, Burn Pit; CAS 04-08-02, Waste Disposal Site; CAS 04-99-01, Contaminated Surface Debris; CAS 06-19-02, Waste Disposal Site/Burn Pit; CAS 06-19-03, Waste Disposal Trenches; CAS 09-23-01, Area 9 Gravel Gertie; and CAS 09-34-01, Underground Detection Station. Closure activities were conducted from December 2008 to April 2009 according to the FFACO (1996, as amended February 2008) and the Corrective Action Plan for CAU 139 (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, 2007b). The corrective action alternatives included No Further Action, Clean Closure, and Closure in Place with Administrative Controls. Closure activities are summarized. CAU 139, 'Waste Disposal Sites,' consists of seven CASs in Areas 3, 4, 6, and 9 of the NTS. The closure alternatives included No Further Action, Clean Closure, and Closure in Place with Administrative Controls. This CR provides a summary of completed closure activities, documentation of waste disposal, and confirmation that remediation goals were met. The following site closure activities were performed at CAU 139 as documented in this CR: (1) At CAS 03-35-01, Burn Pit, soil and debris were removed and disposed as LLW, and debris was removed and disposed as sanitary waste. (2) At CAS 04-08-02, Waste Disposal Site, an administrative UR was implemented. No postings or post-closure monitoring are required. (3) At CAS 04-99-01, Contaminated Surface Debris, soil and debris were removed and disposed as LLW, and debris was removed and disposed as sanitary waste. (4) At CAS 06-19-02, Waste Disposal Site/Burn Pit, no work was performed. (5) At CAS 06-19-03, Waste Disposal Trenches, a native soil cover was installed, and a UR was implemented. (6) At CAS 09-23-01, Area 9 Gravel Gertie, a UR was implemented. (7) At CAS 09-34-01, Underground Detection Station, no work was performed.

NSTec Environmental Restoration

2009-07-31T23:59:59.000Z

375

Lessons Learned from Radioactive Waste Storage and Disposal Facilities  

Science Conference Proceedings (OSTI)

The safety of radioactive waste disposal facilities and the decommissioning of complex sites may be predicated on the performance of engineered and natural barriers. For assessing the safety of a waste disposal facility or a decommissioned site, a performance assessment or similar analysis is often completed. The analysis is typically based on a site conceptual model that is developed from site characterization information, observations, and, in many cases, expert judgment. Because waste disposal facilities are sited, constructed, monitored, and maintained, a fair amount of data has been generated at a variety of sites in a variety of natural systems. This paper provides select examples of lessons learned from the observations developed from the monitoring of various radioactive waste facilities (storage and disposal), and discusses the implications for modeling of future waste disposal facilities that are yet to be constructed or for the development of dose assessments for the release of decommissioning sites. Monitoring has been and continues to be performed at a variety of different facilities for the disposal of radioactive waste. These include facilities for the disposal of commercial low-level waste (LLW), reprocessing wastes, and uranium mill tailings. Many of the lessons learned and problems encountered provide a unique opportunity to improve future designs of waste disposal facilities, to improve dose modeling for decommissioning sites, and to be proactive in identifying future problems. Typically, an initial conceptual model was developed and the siting and design of the disposal facility was based on the conceptual model. After facility construction and operation, monitoring data was collected and evaluated. In many cases the monitoring data did not comport with the original site conceptual model, leading to additional investigation and changes to the site conceptual model and modifications to the design of the facility. The following cases are discussed: commercial LLW disposal facilities; uranium mill tailings disposal facilities; and reprocessing waste storage and disposal facilities. The observations developed from the monitoring and maintenance of waste disposal and storage facilities provide valuable lessons learned for the design and modeling of future waste disposal facilities and the decommissioning of complex sites.

Esh, David W.; Bradford, Anna H. [U.S. Nuclear Regulatory Commission, Two White Flint North, MS T7J8, 11545 Rockville Pike, Rockville, MD 20852 (United States)

2008-01-15T23:59:59.000Z

376

ANALYSIS OF THE SALT FEED TANK CORE SAMPLE  

Science Conference Proceedings (OSTI)

The Saltstone Production Facility (SPF) immobilizes and disposes of low-level radioactive and hazardous liquid waste (salt solution) remaining from the processing of radioactive material at the Savannah River Site (SRS). Low-level waste (LLW) streams from processes at SRS are stored in Tank 50 until the LLW can be transferred to the SPF for treatment and disposal. The Salt Feed Tank (SFT) at the Saltstone Production Facility (SPF) holds approximately 6500 gallons of low level waste from Tank 50 as well as drain water returned from the Saltstone Disposal Facility (SDF) vaults. Over the past several years, Saltstone Engineering has noted the accumulation of solids in the SFT. The solids are causing issues with pump performance, agitator performance, density/level monitoring, as well as taking up volume in the tank. The tank has been sounded at the same location multiple times to determine the level of the solids. The readings have been 12, 25 and 15 inches. The SFT is 8.5 feet high and 12 feet in diameter, therefore the solids account for approximately 10 % of the tank volume. Saltstone Engineering has unsuccessfully attempted to obtain scrape samples of the solids for analysis. As a result, Savannah River National Laboratory (SRNL) was tasked with developing a soft core sampler to obtain a sample of the solids and to analyze the core sample to aid in determining a path forward for removing the solids from the SFT. The source of the material in the SFT is the drain water return system where excess liquid from the Saltstone disposal vaults is pumped back to the SFT for reprocessing. It has been shown that fresh grout from the vault enter the drain water system piping. Once these grout solids return to the SFT, they settle in the tank, set up, and can't be reprocessed, causing buildup in the tank over time. The composition of the material indicates that it is potentially toxic for chromium and mercury and the primary radionuclide is cesium-137. Qualitative measurements show that the material is not cohesive and will break apart with some force.

Reigel, M.; Cheng, W.

2012-01-26T23:59:59.000Z

377

Finding benchmark brown dwarfs to probe the IMF as a function of time  

E-Print Network (OSTI)

Using a simulated disk brown dwarf (BD) population, we find that new large area infrared surveys are expected to identify enough BDs covering wide enough mass--age ranges to potentially measure the mass function down to ~0.03Mo, and the BD formation history out to 10 Gyr, at a level capable of establishing if BD formation follows star formation. We suggest these capabilities are best realised by spectroscopic calibration of BD properties (Teff, g and [M/H]) which, when combined with a measured luminosity and an evolutionary model can give BD mass and age relatively independent of BD atmosphere models. Such calibration requires an empirical understanding of how BD spectra are affected by variations in these properties, and thus the identification and study of "benchmark BDs" whose age and composition can be established independently. We identify the best sources of benchmark BDs as young open cluster members, moving group members, and wide (>1000AU) BD companions to both subgiant stars and high mass white dwarfs (WDs). We have used 2MASS to measure a wide L dwarf companion fraction of 2.7(+0.7/-0.5)%, which equates to a BD companion fraction of 34(+9/-6)% for an alpha~1 companion mass function. Using this value we simulate populations of wide BD binaries, and estimate that 80(+21/-14) subgiant--BD binaries, and 50(+13/-10) benchmark WD--BD binaries could be identified using current and new facilities. The WD--BD binaries should all be identifiable using the Large Area Survey component of UKIDSS combined with Sloan. Discovery of the subgiant--BD binaries will require a NIR imaging campaign around a large (~900) sample of Hipparcos subgiants. If identified, spectral studies of these benchmark brown dwarfs could reveal the spectral sensitivities across the Teff, g and [M/H] space probed by new surveys.

D. J. Pinfield; H. R. A. Jones; P. W. Lucas; T. R. Kendall; S. L. Folkes; A. C. Day-Jones; R. J. Chappelle; I. A. Steele

2006-03-13T23:59:59.000Z

378

ON THE FORMATION OF DOUBLE WHITE DWARFS THROUGH STABLE MASS TRANSFER AND A COMMON ENVELOPE  

SciTech Connect

Although several dozen double white dwarfs (DWDs) have been observed, for many the exact nature of the evolutionary channel(s) by which they form remains uncertain. The canonical explanation calls for the progenitor binary system to undergo two subsequent mass-transfer events, both of which are unstable and lead to a common envelope (CE). However, it has been shown that if both CE events obey the standard {alpha}{sub CE}-prescription (parameterizing energy loss), it is not possible to reproduce all of the observed systems. The {gamma}-prescription was proposed as an alternative to this description, instead parameterizing the fraction of angular momentum carried away in dynamical-timescale mass loss. However, this too has proven problematic, and does not provide a clear physical mechanism. In this paper, we consider in detail the first episode of mass transfer in binary systems with initially low companion masses, with a primary mass in the range 1.0-1.3 M{sub Sun} and an initial mass ratio between the secondary and primary stars of 0.83-0.92. In these systems, the first episode of dramatic mass loss may be stable, non-conservative mass transfer. This strips the donor's envelope and dramatically raises the mass ratio; the considered progenitor binary systems can then evolve into DWDs after passing through a single CE during the second episode of mass loss. We find that such a mechanism reproduces the properties of the observed DWD systems which have an older component with M {approx}< 0.46 M{sub Sun} and mass ratios between the younger and older WDs of q {>=} 1.

Woods, T. E.; Ivanova, N. [Department of Physics, University of Alberta, 11322-89 Ave., Edmonton, AB T6G 2E7 (Canada); Van der Sluys, M. V. [Department of Astrophysics, Radboud University Nijmegen, P.O. Box 9010, NL-6500 GL Nijmegen (Netherlands); Chaichenets, S. [Department of Mathematical and Statistical Sciences, University of Alberta, CAB, Edmonton, AB T6G 2G1 (Canada)

2012-01-01T23:59:59.000Z

379

FAILED-DETONATION SUPERNOVAE: SUBLUMINOUS LOW-VELOCITY Ia SUPERNOVAE AND THEIR KICKED REMNANT WHITE DWARFS WITH IRON-RICH CORES  

SciTech Connect

Type Ia supernovae (SNe Ia) originate from the thermonuclear explosions of carbon-oxygen (C-O) white dwarfs (WDs). The single-degenerate scenario is a well-explored model of SNe Ia where unstable thermonuclear burning initiates in an accreting, Chandrasekhar-mass WD and forms an advancing flame. By several proposed physical processes, the rising, burning material triggers a detonation, which subsequently consumes and unbinds the WD. However, if a detonation is not triggered and the deflagration is too weak to unbind the star, a completely different scenario unfolds. We explore the failure of the gravitationally confined detonation mechanism of SNe Ia, and demonstrate through two-dimensional and three-dimensional simulations the properties of failed-detonation SNe. We show that failed-detonation SNe expel a few 0.1 M{sub Sun} of burned and partially burned material and that a fraction of the material falls back onto the WD, polluting the remnant WD with intermediate-mass and iron-group elements that likely segregate to the core forming a WD whose core is iron rich. The remaining material is asymmetrically ejected at velocities comparable to the escape velocity from the WD, and in response, the WD is kicked to velocities of a few hundred km s{sup -1}. These kicks may unbind the binary and eject a runaway/hypervelocity WD. Although the energy and ejected mass of the failed-detonation SN are a fraction of typical thermonuclear SNe, they are likely to appear as subluminous low-velocity SNe Ia. Such failed detonations might therefore explain or are related to the observed branch of peculiar SNe Ia, such as the family of low-velocity subluminous SNe (SN 2002cx/SN 2008ha-like SNe).

Jordan, George C. IV; Van Rossum, Daniel R. [Center for Astrophysical Thermonuclear Flashes, University of Chicago, Chicago, IL 60637 (United States); Perets, Hagai B. [Physics Department, Technion, Israel Institute of Technology, Haifa 32000 (Israel); Fisher, Robert T. [Department of Physics, University of Massachusetts Dartmouth, 285 Old Westport Road, North Dartmouth, MA 02740 (United States)

2012-12-20T23:59:59.000Z

380

A COMPACT DEGENERATE PRIMARY-STAR PROGENITOR OF SN 2011fe  

Science Conference Proceedings (OSTI)

While a white dwarf (WD) is, from a theoretical perspective, the most plausible primary star of a Type Ia supernova (SN Ia), many other candidates have not been formally ruled out. Shock energy deposited in the envelope of any exploding primary contributes to the early SN brightness and, since this radiation energy is degraded by expansion after the explosion, the diffusive luminosity depends on the initial primary radius. We present a new non-detection limit of the nearby SN Ia 2011fe, obtained at a time that appears to be just 4 hr after explosion, allowing us to directly constrain the initial primary radius (R{sub p} ). Coupled with the non-detection of a quiescent X-ray counterpart and the inferred synthesized {sup 56}Ni mass, we show that R{sub p} {approx} 10{sup 4} g cm{sup -3}, and that the effective temperature must be less than a few Multiplication-Sign 10{sup 5} K. This rules out hydrogen-burning main-sequence stars and giants. Constructing the helium-burning and carbon-burning main sequences, we find that such objects are also excluded. By process of elimination, we find that only degeneracy-supported compact objects-WDs and neutron stars-are viable as the primary star of SN 2011fe. With few caveats, we also restrict the companion (secondary) star radius to R{sub c} {approx}< 0.1 R{sub Sun }, excluding Roche-lobe overflowing red giant and main-sequence companions to high significance.

Bloom, Joshua S.; Kasen, Daniel; Shen, Ken J.; Nugent, Peter E. [Department of Astronomy, University of California, Berkeley, Berkeley CA, 94720-3411 (United States); Butler, Nathaniel R. [School of Earth and Space Exploration, Arizona State University, P.O. Box 871404, Tempe, AZ 85287-1404 (United States); Graham, Melissa L.; Andrew Howell, D. [Las Cumbres Observatory Global Telescope Network, 6740 Cortona Dr., Suite 102, Goleta, CA 93117 (United States); Kolb, Ulrich; Holmes, Stefan; Haswell, Carole A. [Department of Physical Sciences, Open University, Walton Hall, Milton Keynes MK7 6AA (United Kingdom); Burwitz, Vadim [Max-Planck-Institut fuer extraterrestrische Physik, Giessenbachstrasse, 85748 Garching (Germany); Rodriguez, Juan [Observatori Astronomic de Mallorca, Cami de l'Observatori, 07144 Costitx, Mallorca (Spain); Sullivan, Mark, E-mail: jbloom@astro.berkeley.edu [Department of Physics (Astrophysics), University of Oxford, Keble Road, Oxford OX1 3RH (United Kingdom)

2012-01-10T23:59:59.000Z

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381

Properties of O VI Absorption in the Local Interstellar Medium  

E-Print Network (OSTI)

We report on the properties of LISM O VI absorption observed with 20 km/s resolution FUSE observations of 39 white dwarfs (WDs) ranging in distance from 37 to 230 pc with a median distance of 109 pc. LISM O VI is detected with >2sigma significance along 24 of 39 lines of sight. The column densities range from log N(O VI) = 12.38 to 13.60 with a median value of 13.10. The line of sight volume density, n(O VI) = N(O VI)/d exhibits a large dispersion ranging from (0.68 to 13.0)x10(-8) cm(-3) with an average value 3.6x10(-8) cm(-3) twice larger than found for more distant sight lines in the Galactic disk. The narrowest profiles are consistent with thermal Doppler broadening of O VI near its temperature of peak abundance, 2.8x10(5) K. Comparison of the average velocities of O VI and C II absorption reveals 10 cases where the O VI absorption is closely aligned with the C II absorption as expected if the O VI is formed in a condensing interface between the cool and warm absorption and a hot exterior gas. The comparison also reveals 13 cases where O VI absorption is displaced to positive velocity by 7 to 29 km/s from the average velocity of C II. The positive velocity O VI appears to be tracing the evaporative flow of O VI from a young interface between warm gas and a hot exterior medium. However, it is possible the positive velocity O VI is instead tracing cooling hot Local Bubble (LB) gas. The properties of the O VI absorption in the LISM are broadly consistent with the expectations of the theory of conductive interfaces caught in the old condensing phase and possibly in the young evaporative phase of their evolution.

Blair D. Savage; Nicholas Lehner

2005-09-15T23:59:59.000Z

382

An assessment and evaluation for recycle/reuse of contaminated process and metallurgical equipment at the DOE Rocky Flats Plant Site -- Building 865. Final report  

SciTech Connect

An economic analysis of the potential advantages of alternatives for recycling and reusing equipment now stored in Building 865 at the Rocky Flats Plant (RFP) in Colorado has been conducted. The inventory considered in this analysis consists primarily of metallurgical and process equipment used before January 1992, during development and production of nuclear weapons components at the site. The economic analysis consists of a thorough building inventory and cost comparisons for four equipment dispositions alternatives. The first is a baseline option of disposal at a Low Level Waste (LLW) landfill. The three alternatives investigated are metal recycling, reuse with the government sector, and release for unrestricted use. This report provides item-by-item estimates of value, disposal cost, and decontamination cost. The economic evaluation methods documented here, the simple cost comparisons presented, and the data provided as a supplement, should provide a foundation for D&D decisions for Building 865, as well as for similar D&D tasks at RFP and at other sites.

Not Available

1993-08-01T23:59:59.000Z

383

DOE/EIS-0283-SA-2: Supplement Analysis for Waste Solidification Building - Surplus Plutonium Program EIS (11/08)  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

I I ~ ~ I Y I ~ L ' I I I i f l 7 c r [ y S r ~ for (lon~lr~rclion (711d Operal~on of n IVa~tr Solrd~fi~trtron Burlding at the S(rvannn/z I ? I I . ~ I Srte DOEIEIS-0283-SA-2 SUPPLEMENT ANALYSIS WASTE SOLIDIFICATION BUILDING I N T R O D U C T I O N A N D PURPOSE The National Nuclear Security Administration (NNSA), a separately organized agency within the U.S. Department of Energy (DOE), is proposing to construct and operate a standalone Waste Solidification E3uilding1 (WSR) in F-Area at the Savannah River Site (SRS) near Aiken, South Carolina. Certain liquid low-level radioactive waste (LLW) and liquid transuranic (TRU) waste expected to be generated in the Mixed Oxide Fuel Fabrication Facility (MFFF) and Pit Disassembly and Conversion Facility (PDCF) as part of the U.S. Surplus Plutonium Disposition Program woi~ld be treated and

384

West Valley Demonstration Project Waste Management Environmental Impact Statement Supplement Analysis (DOE/EIS-0337-SA-01) (06/07/06)  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

3 3 7-SA-O1 West Valley Demonstration Project Waste Management Environmental Impact Statement Supplement Analysis Revised Final U.S. Department of Energy West Valley Demonstration Project West Valley, New York June 7, 2006 WVDP Waste Management US - Supplement Analysis Table of Contents 1.0 PURPOSE AND NEED FOR AGENCY ACTION 1 2.0 PROPOSED ACTIONS 1 3.0 WASTE TYPE DEFINITIONS 2 4.0 EXISTING NEPA ANALYSIS 3 5.0 NEW INFORMATION 3 6.0 IS A SUPPLEMENTAL EIS NEEDED~ 5 6.1 Glass Melter, CFMT, and MFHT 5 6.2 Increased LLW Volumes 11 7.0 CONCLUSION 17 8.0 DETERMINATION 177 9.0 REFERENCES 17 List of Tables Table 1. Radiation Doses for Involved and Noninvolved Workers Under Alternative A, Including the Glass Melter, CFMT, and MFHT 8 Table 2. Radiological Consequences of Accidents Using 50-Percent Atmospheric Conditions ...9 Table 3. Radiological Consequences of Accidents Using 95-Percent

385

Sk---  

Office of Legacy Management (LM)

. .* . .* . *' 1, c. l ( JJmKS.,"T +2 - Sk--- LCi = ~CU---.-T?~~ - ' _ I -Got& &ysp f= ,$QTg-J%ej & *j, at r-s* p? the c;t S=iw ' e -4 -7 T&a* J %h~k smey to &?'LcrsL!! +,'-H a&xlt CE c~-siz4-"' (WL'&W b--"-R; d-x43 - "MS , cc- 22 lLW JP .-. 2-Q L.2, l=AF, !y515) SkQQ c3 t& e$QT'3r,y* +' -'a-- 'ZS cw..tn;i. .-- Z!o cezU2?siataa kjc~s AA3 ks*~sti lffti S *Ab *T*,& tmld kv ;ia-eGd aa t;v ryrs d t:* -ticIs;: e c3 eaizw2-L &4?ia, x,qZ-' y s +.!-w~ * & & A& b L*z&=- b l A m iE3 &an z U/L& ,c,- 223 *Pb ' Sd YfZ' , w%b!.R LiZhE O+ZIBr -wi' Qe e* if,= ca' ,c, me *e83ia ~hl3 GK m*GLFs. s&s-?qyi* w =.,m -y s:* & km, -k tei;2&+ 3, J. ' Ybc!zb, -a i. 2. iY,kq& ' . \ cus s. '

386

Integrating Volume Reduction and Packaging Alternatives to Achieve Cost Savings for Low Level Waste Disposal at the Rocky Flats Environmental Technology Site  

Science Conference Proceedings (OSTI)

In order to reduce costs and achieve schedules for Closure of the Rocky Flats Environmental Technology Site (RFETS), the Waste Requirements Group has implemented a number of cost saving initiatives aimed at integrating waste volume reduction with the selection of compliant waste packaging methods for the disposal of RFETS low level radioactive waste (LLW). Waste Guidance Inventory and Shipping Forecasts indicate that over 200,000 m3 of low level waste will be shipped offsite between FY2002 and FY2006. Current projections indicate that the majority of this waste will be shipped offsite in an estimated 40,000 55-gallon drums, 10,000 metal and plywood boxes, and 5000 cargo containers. Currently, the projected cost for packaging, shipment, and disposal adds up to $80 million. With these waste volume and cost projections, the need for more efficient and cost effective packaging and transportation options were apparent in order to reduce costs and achieve future Site packaging a nd transportation needs. This paper presents some of the cost saving initiatives being implemented for waste packaging at the Rocky Flats Environmental Technology Site (the Site). There are many options for either volume reduction or alternative packaging. Each building and/or project may indicate different preferences and/or combinations of options.

Church, A.; Gordon, J.; Montrose, J. K.

2002-02-26T23:59:59.000Z

387

TRU waste acceptance criteria for the Waste Isolation Pilot Plant: Revision 3  

SciTech Connect

This document is intended to delineate the criteria by which unclassified waste will be accepted for emplacement at the Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico and describe the bases upon which these criteria were established. These criteria are not intended to be specifications but rather limits that will allow waste generating and shipping sites to develop their own procedures and specifications for preparation of TRU waste for shipment to the WIPP. These criteria will also allow waste generating sites to plan future facilities for waste preparation that will produce TRU waste forms compatible with WIPP waste emplacement and isolation requirements. These criteria only apply to contract-handled (CH) and remote-handled (RH) transuranic (TRU) waste forms and are not intended to apply to beta-gamma wastes, spent fuel, high-level waste (HLW), low-level waste (LLW), low specific activity (LSA) waste, or forms of radioactive waste for experimental purposes. Specifications for receipt of experimental waste forms will be prepared by the responsible projects in conjunction with the staff of the WIPP project at a later date. In addition, these criteria only apply to waste emplaced in bedded rock salt. Technical bases for these criteria may differ significantly from those for other host rocks. 25 refs. 4 figs., 1 tab.

1989-01-01T23:59:59.000Z

388

Waste management system alternatives for treatment of wastes from spent fuel reprocessing  

SciTech Connect

This study was performed to help identify a preferred TRU waste treatment alternative for reprocessing wastes with respect to waste form performance in a geologic repository, near-term waste management system risks, and minimum waste management system costs. The results were intended for use in developing TRU waste acceptance requirements that may be needed to meet regulatory requirements for disposal of TRU wastes in a geologic repository. The waste management system components included in this analysis are waste treatment and packaging, transportation, and disposal. The major features of the TRU waste treatment alternatives examined here include: (1) packaging (as-produced) without treatment (PWOT); (2) compaction of hulls and other compactable wastes; (3) incineration of combustibles with cementation of the ash plus compaction of hulls and filters; (4) melting of hulls and failed equipment plus incineration of combustibles with vitrification of the ash along with the HLW; (5a) decontamination of hulls and failed equipment to produce LLW plus incineration and incorporation of ash and other inert wastes into HLW glass; and (5b) variation of this fifth treatment alternative in which the incineration ash is incorporated into a separate TRU waste glass. The six alternative processing system concepts provide progressively increasing levels of TRU waste consolidation and TRU waste form integrity. Vitrification of HLW and intermediate-level liquid wastes (ILLW) was assumed in all cases.

McKee, R.W.; Swanson, J.L.; Daling, P.M.; Clark, L.L.; Craig, R.A.; Nesbitt, J.F.; McCarthy, D.; Franklin, A.L.; Hazelton, R.F.; Lundgren, R.A.

1986-09-01T23:59:59.000Z

389

THE PRODUCT CONSISTENCY TEST HOW AND WHY IT WAS DEVELOPED  

SciTech Connect

The Product Consistency Test (PCT), American Society for Testing Materials (ASTM) Standard C1285, is currently used world wide for testing glass and glass-ceramic waste forms for high level waste (HLW), low level waste (LLW), and hazardous wastes. Development of the PCT was initiated in 1986 because HLW glass waste forms required extensive characterization before actual production began and required continued characterization during production ({ge}25 years). Non-radioactive startup was in 1994 and radioactive startup was in 1996. The PCT underwent extensive development from 1986-1994 and became an ASTM consensus standard in 1994. During the extensive laboratory testing and inter- and intra-laboratory round robins using non-radioactive and radioactive glasses, the PCT was shown to be very reproducible, to yield reliable results rapidly, to distinguish between glasses of different durability and homogeneity, and to easily be performed in shielded cell facilities with radioactive samples. In 1997, the scope was broadened to include hazardous and mixed (radioactive and hazardous) waste glasses. In 2002, the scope was broadened to include glass-ceramic waste forms which are currently being recommended for second generation nuclear wastes yet to be generated in the nuclear renaissance. Since the PCT has proven useful for glass-ceramics with up to 75% ceramic component and has been used to evaluate Pu ceramic waste forms, the use of this test for other ceramic/mineral waste forms such as geopolymers, hydroceramics, and fluidized bed steam reformer mineralized product is under investigation.

Jantzen, C; Ned Bibler, N

2008-12-15T23:59:59.000Z

390

Radioactive Material Transportation Requirements for the Department of Energy  

Science Conference Proceedings (OSTI)

The Department of Energy (DOE) created the National Transportation Program (NTP) whose goal is to ensure the availability of safe, efficient, and timely transportation of DOE materials. The Integration and Planning Group of the NTP, assisted by Global Technologies Incorporated (GTI), was tasked to identify requirements associated with the transport of DOE Environmental Management (EM) radiological waste/material. A systems engineering approach was used to identify source documents, extract requirements, perform a functional analysis, and set up a transportation requirements management database in RDD-100. Functions and requirements for transporting the following DOE radioactive waste/material are contained in the database: high level radioactive waste (HLW), low-level radioactive waste (LLW), mixed low-level radioactive waste (MLLW), nuclear materials (NM), spent nuclear fuel (SNF), and transuranic waste (TRU waste). The requirements will be used in the development of standard transportation protocols for DOE shipping. The protocols will then be combined into a DOE Transportation Program Management Guide, which will be used to standardize DOE transportation processes.

John, Mark Earl; Fawcett, Ricky Lee; Bolander, Thane Weston

2000-07-01T23:59:59.000Z

391

Documented Safety Analysis for the Waste Storage Facilities March 2010  

SciTech Connect

This Documented Safety Analysis (DSA) for the Waste Storage Facilities was developed in accordance with 10 CFR 830, Subpart B, 'Safety Basis Requirements,' and utilizes the methodology outlined in DOE-STD-3009-94, Change Notice 3. The Waste Storage Facilities consist of Area 625 (A625) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area portion of the DWTF complex. These two areas are combined into a single DSA, as their functions as storage for radioactive and hazardous waste are essentially identical. The B695 Segment of DWTF is addressed under a separate DSA. This DSA provides a description of the Waste Storage Facilities and the operations conducted therein; identification of hazards; analyses of the hazards, including inventories, bounding releases, consequences, and conclusions; and programmatic elements that describe the current capacity for safe operations. The mission of the Waste Storage Facilities is to safely handle, store, and treat hazardous waste, transuranic (TRU) waste, low-level waste (LLW), mixed waste, combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL (as well as small amounts from other DOE facilities).

Laycak, D T

2010-03-05T23:59:59.000Z

392

Processing mixed-waste compressed-gas cylinders at the Oak Ridge Reservation  

Science Conference Proceedings (OSTI)

Until recently, several thousand kilograms of compressed gases were stored at the Oak Ridge Reservation (ORR), in Oak Ridge, Tennessee, because these cylinders could not be taken off-site in their state of configuration for disposal. Restrictions on the storage of old compressed-gas cylinders compelled the Waste Management Organization of Lockheed Martin Energy Systems, Inc. (LMES) to dispose of these materials. Furthermore, a milestone in the ORR Site Treatment Plan required repackaging and shipment off-site of 21 cylinders by September 30, 1997. A pilot project, coordinated by the Chemical Technology Division (CTD) at the Oak Ridge National Laboratory (ORNL), was undertaken to evaluate and recontainerize or neutralize these cylinders, which are mixed waste, to meet that milestone. Because the radiological component was considered to be confined to the exterior of the cylinder, the contents (once removed from the cylinder) could be handled as hazardous waste, and the cylinder could be handled as low-level waste (LLW). This pilot project to process 21 cylinders was important because of its potential impact. The successful completion of the project provides a newly demonstrated technology which can now be used to process the thousands of additional cylinders in inventory across the DOE complex. In this paper, many of the various aspects of implementing this project, including hurdles encountered and the lessons learned in overcoming them, are reported.

Morris, M.I.; Conley, T.B.; Osborne-Lee, I.W.

1998-05-01T23:59:59.000Z

393

Encapsulation of mixed radioactive and hazardous waste contaminated incinerator ash in modified sulfur cement  

Science Conference Proceedings (OSTI)

Some of the process waste streams incinerated at various Department of Energy (DOE) facilities contain traces of both low-level radioactive (LLW) and hazardous constituents, thus yielding ash residues that are classified as mixed waste. Work is currently being performed at Brookhaven National Laboratory (BNL) to develop new and innovative materials for encapsulation of DOE mixed wastes including incinerator ash. One such material under investigation is modified sulfur cement, a thermoplastic developed by the US Bureau of Mines. Monolithic waste forms containing as much as 55 wt % incinerator fly ash from Idaho national Engineering Laboratory (INEL) have been formulated with modified sulfur cement, whereas maximum waste loading for this waste in hydraulic cement is 16 wt %. Compressive strength of these waste forms exceeded 27.6 MPa. Wet chemical and solid phase waste characterization analyses performed on this fly ash revealed high concentrations of soluble metal salts including Pb and Cd, identified by the Environmental Protection Agency (EPA) as toxic metals. Leach testing of the ash according to the EPA Toxicity Characteristic Leaching Procedure (TCLP) resulted in concentrations of Pb and Cd above allowable limits. Encapsulation of INEL fly ash in modified sulfur cement with a small quantity of sodium sulfide added to enhance retention of soluble metal salts reduced TCLP leachate concentrations of Pb and Cd well below EPA concentration criteria for delisting as a toxic hazardous waste. 12 refs., 4 figs., 2 tabs.

Kalb, P.D.; Heiser, J.H. III; Colombo, P.

1990-01-01T23:59:59.000Z

394

Evaluation of selected ion exchangers for the removal of cesium from MVST W-25 supernate  

SciTech Connect

The goal of this batch-test equilibration study was to evaluate the effectiveness of certain ion exchangers for removing cesium from supernate taken from tank W-25 of the Melton Valley Storage Tank (MVST) Facility located at the Oak Ridge National Laboratory (ORNL). These exchangers were selective for removing cesium from alkaline supernatant solutions with high salt concentrations. Since the supernates of evaporator concentrates stored in tanks at the MVST facility have compositions similar to some of those stored in tanks at Hanford, the data generated in this study should prove useful in the overall evaluation of the ion exchangers for applications to Hanford and other US Department of Energy (USDOE) sites. A goal of the waste processing effort at Hanford is to remove enough cesium to ensure that the resulting LLW will meet the Nuclear Regulatory Commission (NRC) 10 CFR 61 class A limit for {sup 137}Cs (1 Ci/m{sup 3} or 1 {mu}Ci/mL). The separated cesium may be concentrated and vitrified for disposal in the high-level waste repository. The decontaminated effluent would be solidified for near-surface disposal.

Collins, J.L.; Egan, B.Z.; Anderson, K.K.; Chase, C.W.; Mrochek, J.E.; Bell, J.T.; Jernigan, G.E.

1995-04-01T23:59:59.000Z

395

Approach and issues toward development of risk-based release standards for radioactive scrap metal recycle and reuse  

Science Conference Proceedings (OSTI)

The decontamination and decommissioning of nuclear facilities is expected to generate large amounts of slightly radioactive scrap metal (RSM). It is likely that some of these materials will be suitable for recycling and reuse. The amount of scrap steel from DOE facilities, for instance, is estimated to be more than one million tons (Hertzler 1993). However, under current practice and without the establishment of acceptable recycling standards, the RSM would be disposed of primarily as radioactive low-level waste (LLW). In the United States, no specific standards have been developed for the unrestricted release of bulk contaminated materials. Although standards for unrestricted release of radioactive surface contamination (NRC 1974) have existed for about 20 years, the release of materials is not commonly practiced because of the lack of risk-based justifications. Recent guidance from international bodies (IAEA 1988) has established a basis for deriving risk-based release limits for radioactive materials. It is important, therefore, to evaluate the feasibility of recycling and associated issues necessary for the establishment of risk-based release limits for the radioactive metals.

Chen, S.Y.; Nieves, L.A.; Nabelssi, B.K.; LePoire, D.J.

1994-03-01T23:59:59.000Z

396

Demonstration of the UNEX Process for the Simultaneous Separation of Cesium, Strontium, and the Actinides from Actual INEEL Sodium-Bearing Waste  

SciTech Connect

A universal solvent extraction (UNEX) process for the simultaneous separation of cesium, strontium, and the actinides from actual radioactive acidic tank waste was demonstrated at the Idaho National Engineering and Environmental Laboratory. The waste solution used in the countercurrent flowsheet demonstration was obtained from tank WM-185. The UNEX process uses a tertiary solvent containing 0.08 M chlorinated cobalt dicarbollide, 0.5% polyethylene glycol-400 (PEG-400), and 0.02 M diphenyl-N,N-dibutylcarbamoyl phosphine oxide (Ph2Bu2CMPO) in a diluent consisting of phenyltrifluoromethyl sulfone (FS-13). The countercurrent flowsheet demonstration was performed in a shielded cell facility using 24 stages of 2-cm diameter centrifugal contactors. Removal efficiencies of 99.4%, 99.995%, and 99.96% were obtained for 137Cs, 90Sr, and total alpha, respectively. This is sufficient to reduce the activities of 137Cs, 90Sr, and actinides in the WM-185 waste to below NRC Class A LLW requirements. Flooding and/or precipitate formation were not observed during testing. Significant amounts of the Zr (87%), Ba (>99%), Pb (98.8%), Fe (8%), Ca (10%), Mo (32%), and K (28%) were also removed from the feed with the universal solvent extraction flowsheet. 99Tc, Al, Hg, and Na were essentially inextractable (<1% extracted).

Law, Jack Douglas; Herbst, Ronald Scott; Todd, Terry Allen; Romanovskiy, V.; Smirnov, I.; Babain, V.; Zaitsev, B.; Esimantovskiy, V.

1999-11-01T23:59:59.000Z

397

IMPROVING CONSISTENCY OF PERFORMANCE ASSESSMENTS IN THE DOE COMPLEX  

Science Conference Proceedings (OSTI)

The low-level waste (LLW) performance assessment (PA) process has been traditionally focused on disposal facilities at a few United States Department of Energy (USDOE) sites and commercial disposal facilities. In recent years, there has been a dramatic increase in the scope of the use of PA-like modeling approaches, involving multiple activities, facilities, contractors and regulators. The scope now includes, for example: (1) National Environmental Policy Act (NEPA) assessments, (2) CERCLA disposal cells, (3) Waste Determinations and High-Level Waste (HLW) Closure activities, (4) Potential on-site disposal of Transuranic (TRU) waste, and (5) In-situ decommissioning (including potential use of existing facilities for disposal). The dramatic increase in the variety of activities requiring more detailed modeling has resulted in a similar increase in the potential for inconsistency in approaches both at a site and complexwide scale. This paper includes a summary of USDOE Environmental Management (EM) sponsored initiatives and activities for improved consistency. New initiatives entitled the Performance Assessment Community of Practice and Performance Assessment Assistance Team are also introduced.

Seitz, R; Elmer Wilhite, E

2009-01-20T23:59:59.000Z

398

Site characterization handbook  

SciTech Connect

This Handbook discusses both management and technical elements that should be considered in developing a comprehensive site characterization program. Management elements typical of any project of a comparable magnitude and complexity are combined with a discussion of strategies specific to site characterization. Information specific to the technical elements involved in site characterization is based on guidance published by the Nuclear Regulatory Commission (NRC) with respect to licensing requirements for LLW disposal facilities. The objective of this Handbook is to provide a reference for both NRC Agreement States and non-Agreement States for use in developing a comprehensive site characterization program that meets the specific objectives of the State and/or site developer/licensee. Each site characterization program will vary depending on the objectives, licensing requirements, schedules/budgets, physical characteristics of the site, proposed facility design, and the specific concerns raised by government agencies and the public. Therefore, the Handbook is not a prescriptive guide to site characterization. 18 refs., 6 figs.

Not Available

1988-06-01T23:59:59.000Z

399

Seismic Characterization of Basalt Topography at Two Candidate Sites for the INL Remote-Handled Low-Level Waste Disposal Project  

Science Conference Proceedings (OSTI)

This report presents the seismic refraction results from the depth to bed rock surveys for two areas being considered for the Remote-Handled Low-Level Waste (RH-LLW) disposal facility at the Idaho National Laboratory. The first area (Site 5) surveyed is located southwest of the Advanced Test Reactor Complex and the second (Site 34) is located west of Lincoln Boulevard near the southwest corner of the Idaho Nuclear Technology and Engineering Center (INTEC). At Site 5, large area and smaller-scale detailed surveys were performed. At Site 34, a large area survey was performed. The purpose of the surveys was to define the topography of the interface between the surficial alluvium and underlying basalt. Seismic data were first collected and processed using seismic refraction tomographic inversion. Three-dimensional images for both sites were rendered from the data to image the depth and velocities of the subsurface layers. Based on the interpreted top of basalt data at Site 5, a more detailed survey was conducted to refine depth to basalt. This report briefly covers relevant issues in the collection, processing and inversion of the seismic refraction data and in the imaging process. Included are the parameters for inversion and result rendering and visualization such as the inclusion of physical features. Results from the processing effort presented in this report include fence diagrams of the earth model, for the large area surveys and iso-velocity surfaces and cross sections from the detailed survey.

Jeff Sondrup; Gail Heath; Trent Armstrong; Annette Shafer; Jesse Bennett; Clark Scott

2011-04-01T23:59:59.000Z

400

Site characterization and monitoring data from Area 5 Pilot Wells, Nevada Test Site, Nye County, Nevada  

SciTech Connect

The Special Projects Section (SPS) of Reynolds Electrical & Engineering Co., Inc. (REECO) is responsible for characterizing the subsurface geology and hydrology of the Area 5 Radioactive Waste Management Site (RWMS) at the Nevada Test Site (NTS) for the US Department of Energy, Nevada Operations Office (DOE/NV), Environmental Restoration and Waste Management Division, Waste Operations Branch. The three Pilot Wells that comprise the Pilot Well Project are an important part of the Area 5 Site Characterization Program designed to determine the suitability of the Area 5 RWMS for disposal of low-level waste (LLW), mixed waste (MW), and transuranic waste (TRU). The primary purpose of the Pilot Well Project is two-fold: first, to characterize important water quality and hydrologic properties of the uppermost aquifer; and second, to characterize the lithologic, stratigraphic, and hydrologic conditions which influence infiltration, redistribution, and percolation, and chemical transport through the thick vadose zone in the vicinity of the Area 5 RWMS. This report describes Pilot Well drilling and coring, geophysical logging, instrumentation and stemming, laboratory testing, and in situ testing and monitoring activities.

NONE

1994-02-01T23:59:59.000Z

Note: This page contains sample records for the topic "non-hlw wds llw" from the National Library of EnergyBeta (NLEBeta).
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401

Demonstration of the UNEX Process for the Simultaneous Separation of Cesium, Strontium, and the Actinides from Actual INEEL Tank Waste  

Science Conference Proceedings (OSTI)

A universal solvent extraction (UNEX) process for the simultaneous separation of cesium, strontium, and the actinides from actual radioactive acidic tank waste was demonstrated at the Idaho National Engineering and Environmental Laboratory. The waste solution used in the countercurrent flowsheet demonstration was obtained from tank WM-185. The UNEX process uses a tertiary solvent containing 0.08 M chlorinated cobalt dicarbollide, 0.5% polyethylene glycol-400 (PEG-400), and 0.02 M diphenyl-N,N-dibutylcarbamoyl phosphine oxide (Ph2Bu2CMPO) in a diluent consisting of phenyltrifluoromethyl sulfone (FS-13). The countercurrent flowsheet demonstration was performed in a shielded cell facility using 24 stages of 2-cm diameter centrifugal contactors. Removal efficiencies of 99.4%, 99.995%, and 99.96% were obtained for 137Cs, 90Sr, and total alpha, respectively. This is sufficient to reduce the activities of 137Cs, 90Sr, and actinides in the WM-185 waste to below NRC Class A LLW requirement s. Flooding and/or precipitate formation were not observed during testing. Significant amounts of the Zr (87%), Ba (>99%), Pb (98.8%), Fe (8%), Ca (10%), Mo (32%), and K (28%) were also removed from the feed with the universal solvent extraction flowsheet. 99Tc, Al, Hg, and Na were essentially inextractable (<1% extracted).

Law, J.D.; Herbst, R.S.; Todd, T.A. (INEEL); Romanovskiy, V.N.; Esimantovskiy, V.M.; Smirnov, I.V.; Babain, V.A.; Zaitsev, B.N. (V. G. Khlopin Radium Institute); Logunov, M.V. (MAYAK Production Association)

1999-10-01T23:59:59.000Z

402

Actinide partitioning from actual Idaho chemical processing plant acidic tank waste using centrifugal contactors  

Science Conference Proceedings (OSTI)

The TRUEX process is being evaluated at the Idaho Chemical Processing Plant (ICPP) for the separation of the actinides from acidic radioactive wastes stored at the ICPP. These efforts have culminated in a recent demonstration of the TRUEX process with actual tank waste. This demonstration was performed using 24 stages of 2-cm diameter centrifugal contactors installed in a shielded hot cell at the ICPP Remote Analytical Laboratory. An overall removal efficiency of 99.97% was obtained for the actinides. As a result, the activity of the actinides was reduced from 457 nCi/g in the feed to 0.12 nCi/g in the aqueous raffinate, which is well below the U.S. NRC Class A LLW requirement of 10 nCi/g for non-TRU waste. Iron was partially extracted by the TRUEX solvent, resulting in 23% of the Fe exiting in the strip product. Mercury was also extracted by the TRUEX solvent (76%) and stripped from the solvent in the 0.25 M Na{sub 2}CO{sub 3} wash section.

Law, J.D.; Brewer, K.N.; Todd, T.A.

1997-10-01T23:59:59.000Z

403

Demonstration of the SREX process for the removal of {sup 90}Sr from actual highly radioactive solutions in centrifugal contactors  

Science Conference Proceedings (OSTI)

The SREX process is being evaluated at the Idaho Chemical Processing Plant (ICPP) for the separation of {sup 90}Sr from acidic radioactive wastes stored at the ICPP. These efforts have culminated in a recent demonstration of the SREX process with actual tank waste. This demonstration was performed using 24 stages of 2-cm diameter centrifugal contactors installed in a shielded hot cell at the ICPP Remote Analytical Laboratory. An overall removal efficiency of 99.995% was obtained for {sup 90}Sr. As a result, the activity of {sup 90}Sr was reduced from 201 Ci/m{sup 3} in the feed solution of 0.0089 Ci/m{sup 3} in the aqueous raffinate, which is below the U.S. NRC Class A LLW limit of 0.04 Ci/m{sup 3} for {sup 90}Sr. Lead was extracted by the SREX solvent and successfully partitioned from the {sup 90}Sr using an ammonium citrate strip solution. Additionally, 94% of the total alpha activity, 1.9% of the {sup 241}Am, 99.94% of the {sup 238}Pu, 99.97% of the {sup 239}Pu, 36.4% of the K, 64% of the Ba, and >83% of the Zr were extracted by the SREX solvent. Cs, B, Cd, Ca, Cr, Fe, Mn, Ni, and Na were essentially inextractable. 10 refs., 2 figs., 3 tabs.

Law, J.D.; Wood, D.J.; Todd, T.A.; Olson, L.G.

1997-10-01T23:59:59.000Z

404

The Universal Solvent Exchange (UNEX) Process II: Flowsheet Development & Demonstration of the UNEX Process for the Separation of Cesium, Strontium, and Actinides from Actual Acidic Radioactive Waste  

Science Conference Proceedings (OSTI)

A novel solvent extraction process, the Universal Extraction (UNEX) process, has been developed for the simultaneous separation of cesium, strontium, and the actinides from acidic waste solutions. The UNEX process solvent consists of chlorinated cobalt dicarbollide for the extraction of 137Cs, polyethylene glycol for the extraction of 90Sr, and diphenyl-N,N-dibutylcarbamoyl phosphine oxide for the extraction of the actinides and lanthanides. A nonnitroaromatic polar diluent consisting of phenyltrifluoromethyl sulfone has been developed for this process. A UNEX flowsheet consisting of a single solvent extraction cycle has been developed as a part of a collaborative effort between the Khlopin Radium Institute (KRI) and the Idaho National Engineering and Environmental Laboratory (INEEL). This flowsheet has been demonstrated with actual acidic radioactive tank waste at the INEEL using 24 stages of 2-cm diameter centrifugal contactors installed in a shielded cell facility. The activities of 137Cs, 90Sr, and the actinides were reduced to levels at which a grout waste form would meet NRC Class A LLW requirements. The extraction of 99Tc and several nonradioactive metals by the UNEX solvent has also been evaluated.

Law, Jack Douglas; Herbst, Ronald Scott; Todd, Terry Allen; Romanovskiy, V. N.; Smirnov, I. V.; Esimantovskiy, V. M.; Zaitsev. B. N.; Babain, V. A.

2001-01-01T23:59:59.000Z

405

Pretreatment status report on the identification and evaluation of alternative processes. Milestone Report No. C064  

SciTech Connect

The purpose of this report is to support the development and demonstration of a pretreatment system that will (1) destroy organic materials and ferrocyanide in tank wastes so that the wastes can be stored safely, (2) separate the high-activity and low-activity fractions, (3) remove radionuclides and remove or destroy hazardous chemicals in LLW as necessary to meet waste form feed requirements, (4) support development and demonstration of vitrification technology by providing representative feeds to the bench-scale glass melter, (5) support full-scale HLW vitrification operations, including near-term operation, by providing feed that meets specifications, and (6) design and develop pretreatment processes that accomplish the above objectives and ensure compliance with environmental regulations. This report is a presentation of candidate technologies for pretreatment of Hanford Site tank waste. Included are descriptions of studies by the Pacific Northwest Laboratory of Battelle Memorial Institute; Science Applications International Corporation, an independent consultant; BNFL, Inc. representing British technologies; Numatec, representing French technologies; and brief accounts of other relevant activities.

Sutherland, D.G. [Westinghouse Hanford Co., Richland, WA (United States); Brothers, A.J. [Pacific Northwest Lab., Richland, WA (United States); Beary, M.M.; Nicholson, G.A. [Science Applications International Corp., San Diego, CA (United States)

1993-09-01T23:59:59.000Z

406

Regulatory Closure Options for the Residue in the Hanford Site Single-Shell Tanks  

SciTech Connect

Liquid, mixed, high-level radioactive waste (HLW) has been stored in 149 single-shell tanks (SSTS) located in tank farms on the U.S. Department of Energy's (DOE's) Hanford Site. The DOE is developing technologies to retrieve as much remaining HLW as technically possible prior to physically closing the tank farms. In support of the Hanford Tanks Initiative, Sandia National Laboratories has addressed the requirements for the regulatory closure of the radioactive component of any SST residue that may remain after physical closure. There is significant uncertainty about the end state of each of the 149 SSTS; that is, the nature and amount of wastes remaining in the SSTS after retrieval is uncertain. As a means of proceeding in the face of these uncertainties, this report links possible end-states with associated closure options. Requirements for disposal of HLW and low-level radioactive waste (LLW) are reviewed in detail. Incidental waste, which is radioactive waste produced incidental to the further processing of HLW, is then discussed. If the low activity waste (LAW) fraction from the further processing of HLW is determined to be incidental waste, then DOE can dispose of that incidental waste onsite without a license from the U.S. Nuclear Regulatory Commissions (NRC). The NRC has proposed three Incidental Waste Criteria for determining if a LAW fraction is incidental waste. One of the three Criteria is that the LAW fraction should not exceed the NRC's Class C limits.

Cochran, J.R. Shyr, L.J.

1998-10-05T23:59:59.000Z

407

Closure Plan for the Area 5 Radioactive Waste Management Site at the Nevada Test Site  

SciTech Connect

The Area 5 Radioactive Waste Management Site (RMWS) at the Nevada Test Site (NTS) is managed and operated by National Security Technologies, LLC (NSTec), for the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO). This document is the first update of the preliminary closure plan for the Area 5 RWMS at the NTS that was presented in the Integrated Closure and Monitoring Plan (DOE, 2005a). The major updates to the plan include a new closure schedule, updated closure inventory, updated site and facility characterization data, the Title II engineering cover design, and the closure process for the 92-Acre Area of the RWMS. The format and content of this site-specific plan follows the Format and Content Guide for U.S. Department of Energy Low-Level Waste Disposal Facility Closure Plans (DOE, 1999a). This interim closure plan meets closure and post-closure monitoring requirements of the order DOE O 435.1, manual DOE M 435.1-1, Title 40 Code of Federal Regulations (CFR) Part 191, 40 CFR 265, Nevada Administrative Code (NAC) 444.743, and Resource Conservation and Recovery Act (RCRA) requirements as incorporated into NAC 444.8632. The Area 5 RWMS accepts primarily packaged low-level waste (LLW), low-level mixed waste (LLMW), and asbestiform low-level waste (ALLW) for disposal in excavated disposal cells.

NSTec Environmental Management

2008-09-01T23:59:59.000Z

408

Composite Analysis for the Area 5 Radioactive Waste Management Site at the Nevada Test Site, Nye County, Nevada  

SciTech Connect

This report summarizes the results of a Composite Analysis (CA) for the Area 5 Radioactive Waste Management Site (RWMS). The Area 5 RWMS is a US Department of Energy (DOE)-operated low-level radioactive waste (LLW) management site located in northern Frenchman Flat on the Nevada Test Site (NTS). The Area 5 RWMS has disposed of low-level radioactive waste in shallow unlined pits and trenches since 1960. Transuranic waste (TRU) and high-specific activity waste was disposed in Greater Confinement Disposal (GCD) boreholes from 1983 to 1989. The purpose of this CA is to determine if continuing operation of the Area 5 RWMS poses an acceptable or unacceptable risk to the public considering the total waste inventory and all other interacting sources of radioactive material in the vicinity. Continuing operation of the Area 5 RWMS will be considered acceptable if the total effective dose equivalent (TEDE) is less than 100 mrem in a year. If the TEDE exceeds 30 mrem in a year, a cost-benefit options analysis must be performed to determine if cost-effective management options exist to reduce the dose further. If the TEDE is found to be less than 30 mrem in a year, an analysis may be performed if warranted to determine if doses are as low as reasonably achievable (ALARA).

V. Yucel

2001-09-01T23:59:59.000Z

409

SOLID WASTE INTEGRATED FORECAST TECHNICAL (SWIFT) REPORT FY2005 THRU FY2035 2005.0 VOLUME 2  

Science Conference Proceedings (OSTI)

This report provides up-to-date life cycle information about the radioactive solid waste expected to be managed by Hanford's Waste Management (WM) Project from onsite and offsite generators. It includes: (1) an overview of Hanford-wide solid waste to be managed by the WM Project; (2) multi-level and waste class-specific estimates; (3) background information on waste sources; and (4) comparisons to previous forecasts and other national data sources. The focus of this report is low-level waste (LLW), mixed low-level waste (MLLW), and transuranic waste, both non-mixed and mixed (TRU(M)). Some details on hazardous waste are also provided, however, this information is not considered comprehensive. This report includes data requested in December, 2004 with updates through March 31,2005. The data represent a life cycle forecast covering all reported activities from FY2005 through the end of each program's life cycle and are an update of the previous FY2004.1 data version.

BARCOT, R.A.

2005-08-17T23:59:59.000Z

410

LLNL Site plan for a MOX fuel lead assembly mission in support of surplus plutonium disposition  

SciTech Connect

The principal facilities that LLNL would use to support a MOX Fuel Lead Assembly Mission are Building 332 and Building 334. Both of these buildings are within the security boundary known as the LLNL Superblock. Building 332 is the LLNL Plutonium Facility. As an operational plutonium facility, it has all the infrastructure and support services required for plutonium operations. The LLNL Plutonium Facility routinely handles kilogram quantities of plutonium and uranium. Currently, the building is limited to a plutonium inventory of 700 kilograms and a uranium inventory of 300 kilograms. Process rooms (excluding the vaults) are limited to an inventory of 20 kilograms per room. Ongoing operations include: receiving SSTS, material receipt, storage, metal machining and casting, welding, metal-to-oxide conversion, purification, molten salt operations, chlorination, oxide calcination, cold pressing and sintering, vitrification, encapsulation, chemical analysis, metallography and microprobe analysis, waste material processing, material accountability measurements, packaging, and material shipping. Building 334 is the Hardened Engineering Test Building. This building supports environmental and radiation measurements on encapsulated plutonium and uranium components. Other existing facilities that would be used to support a MOX Fuel Lead Assembly Mission include Building 335 for hardware receiving and storage and TRU and LLW waste storage and shipping facilities, and Building 331 or Building 241 for storage of depleted uranium.

Bronson, M.C.

1997-10-01T23:59:59.000Z

411

Mixed Waste Management Options: 1995 Update. National Low-Level Waste Management Program  

SciTech Connect

In the original mixed Waste Management Options (DOE/LLW-134) issued in December 1991, the question was posed, ``Can mixed waste be managed out of existence?`` That study found that most, but not all, of the Nation`s mixed waste can theoretically be managed out of existence. Four years later, the Nation is still faced with a lack of disposal options for commercially generated mixed waste. However, since publication of the original Mixed Waste Management Options report in 1991, limited disposal capacity and new technologies to treat mixed waste have become available. A more detailed estimate of the Nation`s mixed waste also became available when the US Environmental Protection Agency (EPA) and the US Nuclear Regulatory Commission (NRC) published their comprehensive assessment, titled National Profile on Commercially Generated Low-Level Radioactive Mixed Waste (National Profile). These advancements in our knowledge about mixed waste inventories and generation, coupled with greater treatment and disposal options, lead to a more applied question posed for this updated report: ``Which mixed waste has no treatment option?`` Beyond estimating the volume of mixed waste requiring jointly regulated disposal, this report also provides a general background on the Atomic Energy Act (AEA) and the Resource Conservation and Recovery Act (RCRA). It also presents a methodical approach for generators to use when deciding how to manage their mixed waste. The volume of mixed waste that may require land disposal in a jointly regulated facility each year was estimated through the application of this methodology.

Kirner, N.; Kelly, J.; Faison, G.; Johnson, D. [Foster Wheeler Environmental Corp. (United States)

1995-05-01T23:59:59.000Z

412

Certification Plan, Radioactive Mixed Waste Hazardous Waste Handling Facility  

SciTech Connect

The purpose of this plan is to describe the organization and methodology for the certification of radioactive mixed waste (RMW) handled in the Hazardous Waste Handling Facility at Lawrence Berkeley Laboratory (LBL). RMW is low-level radioactive waste (LLW) or transuranic (TRU) waste that is co-contaminated with dangerous waste as defined in the Westinghouse Hanford Company (WHC) Solid Waste Acceptance Criteria (WAC) and the Washington State Dangerous Waste Regulations, 173-303-040 (18). This waste is to be transferred to the Hanford Site Central Waste Complex and Burial Grounds in Hanford, Washington. This plan incorporates the applicable elements of waste reduction, which include both up-front minimization and end-product treatment to reduce the volume and toxicity of the waste; segregation of the waste as it applies to certification; an executive summary of the Waste Management Quality Assurance Implementing Management Plan (QAIMP) for the HWHF (Section 4); and a list of the current and planned implementing procedures used in waste certification.

Albert, R.

1992-06-30T23:59:59.000Z

413

Documented Safety Analysis for the Waste Storage Facilities  

Science Conference Proceedings (OSTI)

This documented safety analysis (DSA) for the Waste Storage Facilities was developed in accordance with 10 CFR 830, Subpart B, 'Safety Basis Requirements', and utilizes the methodology outlined in DOE-STD-3009-94, Change Notice 3. The Waste Storage Facilities consist of Area 625 (A625) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area portion of the DWTF complex. These two areas are combined into a single DSA, as their functions as storage for radioactive and hazardous waste are essentially identical. The B695 Segment of DWTF is addressed under a separate DSA. This DSA provides a description of the Waste Storage Facilities and the operations conducted therein; identification of hazards; analyses of the hazards, including inventories, bounding releases, consequences, and conclusions; and programmatic elements that describe the current capacity for safe operations. The mission of the Waste Storage Facilities is to safely handle, store, and treat hazardous waste, transuranic (TRU) waste, low-level waste (LLW), mixed waste, combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL (as well as small amounts from other DOE facilities).

Laycak, D

2008-06-16T23:59:59.000Z

414

RCRA Facility Investigation report for Waste Area Grouping 6 at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Volume 1, Sections 1 through 3: Environmental Restoration Program  

Science Conference Proceedings (OSTI)

WAG 6 comprises a shallow land burial facility used for disposal of low-level radioactive wastes (LLW) and, until recently, chemical wastes. As such, the site is subject to regulation under RCRA and the Comprehensive Environmental Response Compensation and Liability Act (CERCLA). To comply with these regulations, DOE, in conjunction with the Environmental Protection Agency (EPA) and the Tennessee Department of Environment and Conservation (TDEC), developed a strategy for closure and remediation of WAG 6 by 1997. A key component of this strategy was to complete an RFI by September 1991. The primary objectives of the RFI were to evaluate the site`s potential human health and environmental impacts and to develop a preliminary list of alternatives to mitigate these impacts. The WAG 6 one of three solid waste management units evaluated Oak Ridge National Laboratory (ORNL) existing waste disposal records and sampling data and performed the additional sampling and analysis necessary to: describe the nature and extent of contamination; characterize key contaminant transport pathways; and assess potential risks to human health and the environment by developing and evaluating hypothetical receptor scenarios. Estimated excess lifetime cancer risks as a result for exposure to radionuclides and chemicals were quantified for each hypothetical human receptor. For environmental receptors, potential impacts were qualitatively assessed. Taking into account regulatory requirements and base line risk assessment results, preliminary site closure and remediation objectives were identified, and a preliminary list of alternatives for site closure and remediation was developed.

Not Available

1991-09-01T23:59:59.000Z

415

RCRA Facility Investigation report for Waste Area Grouping 6 at Oak Ridge National Laboratory, Oak Ridge, Tennessee  

Science Conference Proceedings (OSTI)

WAG 6 comprises a shallow land burial facility used for disposal of low-level radioactive wastes (LLW) and, until recently, chemical wastes. As such, the site is subject to regulation under RCRA and the Comprehensive Environmental Response Compensation and Liability Act (CERCLA). To comply with these regulations, DOE, in conjunction with the Environmental Protection Agency (EPA) and the Tennessee Department of Environment and Conservation (TDEC), developed a strategy for closure and remediation of WAG 6 by 1997. A key component of this strategy was to complete an RFI by September 1991. The primary objectives of the RFI were to evaluate the site's potential human health and environmental impacts and to develop a preliminary list of alternatives to mitigate these impacts. The WAG 6 one of three solid waste management units evaluated Oak Ridge National Laboratory (ORNL) existing waste disposal records and sampling data and performed the additional sampling and analysis necessary to: describe the nature and extent of contamination; characterize key contaminant transport pathways; and assess potential risks to human health and the environment by developing and evaluating hypothetical receptor scenarios. Estimated excess lifetime cancer risks as a result for exposure to radionuclides and chemicals were quantified for each hypothetical human receptor. For environmental receptors, potential impacts were qualitatively assessed. Taking into account regulatory requirements and base line risk assessment results, preliminary site closure and remediation objectives were identified, and a preliminary list of alternatives for site closure and remediation was developed.

Not Available

1991-09-01T23:59:59.000Z

416

Groundwater quality assessment report for Solid Waste Storage Area 6 at Oak Ridge National Laboratory, Oak Ridge, Tennessee  

Science Conference Proceedings (OSTI)

Solid Waste Storage Area (SWSA) 6, located at the US Department of Energy (DOE) Oak Ridge National Laboratory (ORNL) facility, is a shallow land burial site for low-level radioactive waste (LLW) and other waste types. Wastes were disposed of in unlined trenches and auger holes from 1969 until May 1986, when it was determined that Resource Conservation and Recovery Act (RCRA) regulated wastes were being disposed of there. DOE closed SWSA 6 until changes in operating procedures prevented the disposal of RCRA wastes at SWSA 6. The site, which reopened for waste disposal activities in July 1986, is the only currently operated disposal area for low-level radioactive waste at ORNL. This report provides the results of the 1998 RCRA groundwater assessment monitoring. The monitoring was performed in accordance with the proposed routine monitoring plan recommended in the 1996 EMP. Section 2 provides pertinent background on SWSA 6. Section 3 presents the 1998 monitoring results and discusses the results in terms of any significant changes from previous monitoring efforts. Section 4 provides recommendations for changes in monitoring based on the 1998 results. References are provided in Section 5. Appendix A provides the 1998 RCRA Sampling Data and Appendix B provides a summary of 1998 Quality Assurance results.

NONE

1998-12-31T23:59:59.000Z

417

Greater-Than-Class C Low-Level Radioactive Waste Transportation Strategy report and institutional plan  

SciTech Connect

This document contains two parts. Part I, Greater-Than-Class-C Low-Level Radioactive Waste Transportation Strategy, addresses the requirements, responsibilities, and strategy to transport and receive these wastes. The strategy covers (a) transportation packaging, which includes shipping casks and waste containers; (b) transportation operations relating to the five facilities involved in transportation, i.e., waste originator, interim storage, dedicated storage, treatment, and disposal; (c) system safety and risk analysis; (d) routes; (e) emergency preparedness and response; and (o safeguards and security. A summary of strategic actions is provided at the conclusion of Part 1. Part II, Institutional Plan for Greater-Than-Class C Low-Level Radioactive Waste Packaging and Transportation, addresses the assumptions, requirements, and institutional plan elements and actions. As documented in the Strategy and Institutional Plan, the most challenging issues facing the GTCC LLW Program shipping campaign are institutional issues closely related to the strategy. How the Program addresses those issues and demonstrates to the states, local governments, and private citizens that the shipments can and will be made safely will strongly affect the success or failure of the campaign.

Schmitt, R.C.; Tyacke, M.J.

1995-01-01T23:59:59.000Z

418

Analysis of accident sequences and source terms at treatment and storage facilities for waste generated by US Department of Energy waste management operations  

SciTech Connect

This report documents the methodology, computational framework, and results of facility accident analyses performed for the US Department of Energy (DOE) Waste Management Programmatic Environmental Impact Statement (WM PEIS). The accident sequences potentially important to human health risk are specified, their frequencies assessed, and the resultant radiological and chemical source terms evaluated. A personal-computer-based computational framework and database have been developed that provide these results as input to the WM PEIS for the calculation of human health risk impacts. The WM PEIS addresses management of five waste streams in the DOE complex: low-level waste (LLW), hazardous waste (HW), high-level waste (HLW), low-level mixed waste (LLMW), and transuranic waste (TRUW). Currently projected waste generation rates, storage inventories, and treatment process throughputs have been calculated for each of the waste streams. This report summarizes the accident analyses and aggregates the key results for each of the waste streams. Source terms are estimated, and results are presented for each of the major DOE sites and facilities by WM PEIS alternative for each waste stream. Key assumptions in the development of the source terms are identified. The appendices identify the potential atmospheric release of each toxic chemical or radionuclide for each accident scenario studied. They also discuss specific accident analysis data and guidance used or consulted in this report.

Mueller, C.; Nabelssi, B.; Roglans-Ribas, J.; Folga, S.; Policastro, A.; Freeman, W.; Jackson, R.; Mishima, J.; Turner, S.

1996-12-01T23:59:59.000Z

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Radionuclide Retention in Concrete Wasteforms  

SciTech Connect

Assessing long-term performance of Category 3 waste cement grouts for radionuclide encasement requires knowledge of the radionuclide-cement interactions and mechanisms of retention (i.e., sorption or precipitation); the mechanism of contaminant release; the significance of contaminant release pathways; how wasteform performance is affected by the full range of environmental conditions within the disposal facility; the process of wasteform aging under conditions that are representative of processes occurring in response to changing environmental conditions within the disposal facility; the effect of wasteform aging on chemical, physical, and radiological properties; and the associated impact on contaminant release. This knowledge will enable accurate prediction of radionuclide fate when the wasteforms come in contact with groundwater. Data collected throughout the course of this work will be used to quantify the efficacy of concrete wasteforms, similar to those used in the disposal of LLW and MLLW, for the immobilization of key radionuclides (i.e., uranium, technetium, and iodine). Data collected will also be used to quantify the physical and chemical properties of the concrete affecting radionuclide retention.

Wellman, Dawn M.; Jansik, Danielle P.; Golovich, Elizabeth C.; Cordova, Elsa A.

2012-09-24T23:59:59.000Z

420

INTEC High-Level Waste Studies Universal Solvent Extraction Feasibility Study  

SciTech Connect

This report summarizes a feasibility study that has been conducted on the Universal Solvent Extraction (UNEX) Process for treatment and disposal of 4.3 million liters of INEEL sodium-bearing waste located at the Idaho Nuclear Technology and Engineering Center. This feasibility study covers two scenarios of treatment. The first, the UNEX Process, partitions the Cs/Sr from the SBW and creates remote-handled LLW and contact-handled TRU waste forms. Phase one of this study, covered in the 30% review documents, dealt with defining the processes and defining the major unit operations. The second phase of the project, contained in the 60% review, expanded on the application of the UNEX processes and included facility requirements and definitions. Two facility options were investigated for the UNEX process, resulting in a 2 x 2 matrix of process/facility scenarios as follows: Option A, UNEX at Greenfield Facility, Option B, Modified UNEX at Greenfield Facility, Option C, UNEX at NWCF, th is document, covers life-cycle costs for all options presented along with results and conclusions determined from the study.

J. Banaee; C. M. Barnes; T. Battisti (ANL-W) [ANL-W; S. Herrmann (ANL-W) [ANL-W; S. J. Losinski; S. McBride (ANL-W) [ANL-W

2000-09-01T23:59:59.000Z

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