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1

The Challenge Now: Completion of the Legacy TRU Waste Mission 20 Years Early  

SciTech Connect (OSTI)

The Department of Energy's (DOE) Waste Isolation Pilot Plant (WIPP) opened on March 26, 1999, becoming the nation's first deep geologic repository for the permanent disposal of defense generated transuranic (TRU) waste. This waste is currently retrievably stored at 27 sites across the country. Since its opening, approximately 10,000 m3 of TRU waste have been safely characterized, transported, and disposed in the WIPP. The DOE has achieved and surpassed the original goal of sending 17 waste shipments per week to WIPP. The National TRU Program (NTP) has implemented significant operational efficiencies, regulatory changes, and management initiatives, but the program cannot rest on its past achievements. The initial program schedule shows completion of TRU waste disposal in 2034 at an estimated life-cycle cost of $16 billion. The Carlsbad Field Office (CBFO) and the 27 TRU waste generator sites have developed a comprehensive plan that will allow completion of the legacy TRU waste mission 20 years ahead of the initial schedule.

Triay, I.; Wu, C.

2003-02-25T23:59:59.000Z

2

The Nevada Test Site Legacy TRU Waste - The WIPP Central Characterization Project  

SciTech Connect (OSTI)

This paper discusses the Central Characterization Project (CCP) designed by the Waste Isolation Pilot Plant (WIPP) to aid sites, especially those sites with small quantities of transuranic (TRU) waste streams, in disposing of legacy waste at their facility. Because of the high cost of contracting vendors with the characterization capabilities necessary to meet the WIPP Waste Acceptance Criteria, utilizing the CCP is meant to simplify the process for small quantity sites. The paper will describe the process of mobilization of the vendors through CCP, the current production milestones that have been met, and the on-site lessons learned.

Norton, J. F.; Lahoud, R. G.; Foster, B. D.; VanMeighem, J.

2003-02-25T23:59:59.000Z

3

Transuranic Waste Processing Center (TWPC) Legacy Tank RH-TRU Sludge Processing and Compliance Strategy - 13255  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE) needs to safely and efficiently treat its 'legacy' transuranic (TRU) waste and mixed low-level waste (LLW) from past research and defense activities at the Oak Ridge National Laboratory (ORNL) so that the waste is prepared for safe and secure disposal. The TWPC operates an Environmental Management (EM) waste processing facility on the Oak Ridge Reservation (ORR). The TWPC is classified as a Hazard Category 2, non-reactor nuclear facility. This facility receives, treats, and packages low-level waste and TRU waste stored at various facilities on the ORR for eventual off-site disposal at various DOE sites and commercial facilities. The Remote Handled TRU Waste Sludge held in the Melton Valley Storage Tanks (MVSTs) was produced as a result of the collection, treatment, and storage of liquid radioactive waste originating from the ORNL radiochemical processing and radioisotope production programs. The MVSTs contain most of the associated waste from the Gunite and Associated Tanks (GAAT) in the ORNL's Tank Farms in Bethel Valley and the sludge (SL) and associated waste from the Old Hydro-fracture Facility tanks and other Federal Facility Agreement (FFA) tanks. The SL Processing Facility Build-outs (SL-PFB) Project is integral to the EM cleanup mission at ORNL and is being accelerated by DOE to meet updated regulatory commitments in the Site Treatment Plan. To meet these commitments a Baseline (BL) Change Proposal (BCP) is being submitted to provide continued spending authority as the project re-initiation extends across fiscal year 2012 (FY2012) into fiscal year 2013. Future waste from the ORNL Building 3019 U-233 Disposition project, in the form of U-233 dissolved in nitric acid and water, down-blended with depleted uranyl nitrate solution is also expected to be transferred to the 7856 MVST Annex Facility (formally the Capacity Increase Project (CIP) Tanks) for co-processing with the SL. The SL-PFB project will construct and install the necessary integrated systems to process the accumulated MVST Facilities SL inventory at the TWPC thus enabling safe and effective disposal of the waste. This BCP does not include work to support current MVST Facility Surveillance and Maintenance programs or the ORNL Building 3019 U-233 Disposition project, since they are not currently part of the TWPC prime contract. The purpose of the environmental compliance strategy is to identify the environmental permits and other required regulatory documents necessary for the construction and operation of the SL- PFB at the TWPC, Oak Ridge, TN. The permits and other regulatory documents identified are necessary to comply with the environmental laws and regulations of DOE Orders, and other requirements documented in the SL-PFB, Safety Design Strategy (SDS), SL-A-AD-002, R0 draft, and the Systems, Function and Requirements Document (SFRD), SL-X-AD-002, R1 draft. This compliance strategy is considered a 'living strategy' and it is anticipated that it will be revised as design progresses and more detail is known. The design basis on which this environmental permitting and compliance strategy is based is the Wastren Advantage, Inc., (WAI), TWPC, SL-PFB (WAI-BL-B.01.06) baseline. (authors)

Rogers, Ben C.; Heacker, Fred K.; Shannon, Christopher [Wastren Advantage, Inc., Transuranic Waste Processing Center, 100 WIPP Road, Lenoir City, Tennessee 37771 (United States)] [Wastren Advantage, Inc., Transuranic Waste Processing Center, 100 WIPP Road, Lenoir City, Tennessee 37771 (United States); and others

2013-07-01T23:59:59.000Z

4

Transuranic (TRU) Waste | Department of Energy  

Office of Environmental Management (EM)

Transuranic (TRU) Waste Transuranic (TRU) Waste Transuranic (TRU) Waste Defined by the WIPP Land Withdrawal Act as "waste containing more than 100 nanocuries of alpha-emitting...

5

Optimizing the National TRU waste system transportation program.  

SciTech Connect (OSTI)

The goal of the National TRU Waste Program (NTP) is to operate the system safely and cost-effectively, in compliance with applicable regulations and agreements, and at full capacity in a fully integrated mode. One of the objectives of the Department of Energy's Carlsbad Field Office (DOE/CBFO) is to complete the current Waste Isolation Pilot Plant (WIPP) mission for the disposal of the nation's legacy transuranic (TRU) waste at least IO years earlier thus saving approximately %7B. The National TRU Waste Optimization Plan (1) recommends changes to accomplish this. This paper discusses the optimization of the National TRU Waste System Transportation Program.

Lott, S. A. (Sheila A.); Countiss, S. (Sue)

2002-01-01T23:59:59.000Z

6

Progress Update: TRU Waste Shipping  

SciTech Connect (OSTI)

A progress update at the Savannah River Site. A continued effort on shipping TRU waste to WIPP in Carlsbad, New Mexico.

Cody, Tom

2010-01-01T23:59:59.000Z

7

Progress Update: TRU Waste Shipping  

ScienceCinema (OSTI)

A progress update at the Savannah River Site. A continued effort on shipping TRU waste to WIPP in Carlsbad, New Mexico.

Cody, Tom

2012-06-14T23:59:59.000Z

8

On Going TRU Waste Disposition  

SciTech Connect (OSTI)

The ongoing effort to contain dangerous, radioactive TRU waste. Under the Recovery Act, the Savannah River Site is able to safely test and transport these items to WIPP in Carlsbad, New Mexico.

Cody, Tom

2010-01-01T23:59:59.000Z

9

On Going TRU Waste Disposition  

ScienceCinema (OSTI)

The ongoing effort to contain dangerous, radioactive TRU waste. Under the Recovery Act, the Savannah River Site is able to safely test and transport these items to WIPP in Carlsbad, New Mexico.

Cody, Tom

2012-06-14T23:59:59.000Z

10

A Novel and Cost Effective Approach to the Decommissioning and Decontamination of Legacy Glove Boxes - Minimizing TRU Waste and Maximizing LLW Waste - 13634  

SciTech Connect (OSTI)

This paper describes the process of decommissioning two gloveboxes at the Argonne National Laboratory (ANL) that were employed for work with plutonium and other radioactive materials. The decommissioning process involved an initial phase of clearing tools and materials from the glove boxes and disconnecting them from the laboratory infrastructure. The removed materials, assessed as Transuranic (TRU) waste, were packaged into 55 gallon (200 litre) drums and prepared for ultimate disposal at the Waste Isolation Pilot Plant (WIPP) at Carlsbad New Mexico. The boxes were then sampled to determine the radioactive contents by means of smears that were counted with alpha and beta detectors to determine the residual surface contamination, especially in terms of alpha particle emitters that are an indicator of TRU activity. Paint chip samples were also collected and sent for laboratory analysis in order to ascertain the radioactive contamination contributing to the TRU activity as a fixed contamination. The investigations predicted that it may be feasible to reduce the residual surface contamination and render the glovebox structure low level waste (LLW) for disposal. In order to reduce the TRU activity a comprehensive decontamination process was initiated using chemical compounds that are particularly effective for lifting and dissolving radionuclides that adhere to the inner surfaces of the gloveboxes. The result of the decontamination process was a reduction in the TRU surface activity on the inner surfaces of the gloveboxes by four orders of magnitude in terms of disintegrations per unit area (DPA). The next phase of the process involved a comprehensive assay of the gloveboxes using a combination of passive neutron and gamma ray scintillation detectors and a shielded and collimated high purity Germanium (HPGe) gamma ray detector. The HPGe detector was used to obtain gamma ray spectra for a variety of measurement positions within the glovebox. The spectra were used to determine the TRU content of the boxes by assessing the activity of Am-241 (59 keV) and Pu-241 (414 keV). Using the data generated it was possible for qualified subject matter experts (SME) to assess that the gloveboxes could be consigned for disposition as LLW and not as TRU. Once this determination was assessed and accepted the gloveboxes were prepared for final disposition to the Nevada National Security Site (NNSS) - formerly the Nevada Test Site (NTS). This preparation involved fixing any remaining radioactive contamination within the gloveboxes by filling them with a foam compound, prior to transportation. Once the remaining contamination was fixed the gloveboxes were removed from the laboratory and prepared for transported by road to NNSS. This successful glovebox decontamination and decommissioning process illustrates the means by which TRU waste generation has been minimized, LLW generation has been maximized, and risk has been effectively managed. The process minimizes the volume of TRU waste and reduced the decommissioning time with significant cost savings as the result. (authors)

Pancake, Daniel; Rock, Cynthia M.; Creed, Richard [Argonne National Laboratory, 9700 South Cass Avenue, Lemont, IL 60439 (United States)] [Argonne National Laboratory, 9700 South Cass Avenue, Lemont, IL 60439 (United States); Donohoue, Tom; Martin, E. Ray; Mason, John A. [ANTECH Corporation 9050 Marshall Court, Westminster, CO, 80031 (United States)] [ANTECH Corporation 9050 Marshall Court, Westminster, CO, 80031 (United States); Norton, Christopher J.; Crosby, Daniel [Environmental Alternatives, Inc., 149 Emerald Street, Suite R, Keene, NH 03431 (United States)] [Environmental Alternatives, Inc., 149 Emerald Street, Suite R, Keene, NH 03431 (United States); Nachtman, Thomas J. [InstaCote, Inc., 160 C. Lavoy Road, Erie, MI, 48133 (United States)] [InstaCote, Inc., 160 C. Lavoy Road, Erie, MI, 48133 (United States)

2013-07-01T23:59:59.000Z

11

EA-1962: Analysis for Below Grade Suspect Transuranic (TRU) Waste at Technical Area (TA)-54  

Broader source: Energy.gov [DOE]

DOE is preparing an EA to evaluate the legacy suspect transuranic (TRU) waste at Area G for the purposes of reclassification of waste type and determination of a final disposal path. Per DOE Order 435.1, Change 1, Radioactive Waste Management, and its associated guide, legacy waste at Los Alamos National Laboratory that contained TRU waste was stored and managed as TRU waste. The waste was given an interim classification for the purposes of applying the most restrictive standard until the waste could be adequately characterized and a final determination on the disposition classification was made.

12

Technological enhancements in TRU waste management.  

SciTech Connect (OSTI)

On March 26, 1999, the Waste Isolation Pilot Plant (WIPP) received its first shipment of transuranic (TRU) waste. On November 26, 1999, the Hazardous Waste Facility Permit (HWFP) to receive mixed TRU waste at WIPP became effective. Having achieved these two milestones, facilitating and supporting the characterization, transportation, and disposal of TRU waste became the major challenges for the National TRU Waste Program. After the WIPP began receiving waste, it was evident that, at the rate at which TRU waste was being shipped to and received at WIPP, the facility was not being used to its full potential, nor would it be unless improvements to the TRU waste management system were made. This paper describes some of the efforts to optimize (to make as functional as possible) characterization, transportation, and disposal of TRU waste; some of the technological enhancements necessary to achieve an optimized national transuranic waste system (1); and the interplay between regulatory change and technology development

Elkins, N. Z. (Ned Z.); Moody, D. C. (David C.)

2002-01-01T23:59:59.000Z

13

Hanford Site Transuranic (TRU) Waste Certification Plan  

SciTech Connect (OSTI)

As a generator of transuranic (TRU) and TRU mixed waste destined for disposal at the Waste Isolation Pilot Plant (WIPP), the Hanford Site must ensure that its TRU waste meets the requirements of US. Department of Energy (DOE) 0 435.1, ''Radioactive Waste Management,'' and the Contact-Handled (CH) Transuranic Waste Acceptance Criteria for the Waste Isolation Pilot Plant (WIPP-WAC). WIPP-WAC requirements are derived from the WIPP Technical Safety Requirements, WIPP Safety Analysis Report, TRUPACT-II SARP, WIPP Land Withdrawal Act, WIPP Hazardous Waste Facility Permit, and Title 40 Code of Federal Regulations (CFR) 191/194 Compliance Certification Decision. The WIPP-WAC establishes the specific physical, chemical, radiological, and packaging criteria for acceptance of defense TRU waste shipments at WIPP. The WPP-WAC also requires that participating DOE TRU waste generator/treatment/storage sites produce site-specific documents, including a certification plan, that describe their program for managing TRU waste and TRU waste shipments before transferring waste to WIPP. Waste characterization activities provide much of the data upon which certification decisions are based. Waste characterization requirements for TRU waste and TRU mixed waste that contains constituents regulated under the Resource Conservation and Recovery Act (RCRA) are established in the WIPP Hazardous Waste Facility Permit Waste Analysis Plan (WAP). The Hanford Site Quality Assurance Project Plan (QAPjP) (HNF-2599) implements the applicable requirements in the WAP and includes the qualitative and quantitative criteria for making hazardous waste determinations. The Hanford Site must also ensure that its TRU waste destined for disposal at WPP meets requirements for transport in the Transuranic Package Transporter-11 (TRUPACT-11). The US. Nuclear Regulatory Commission (NRC) establishes the TRUPACT-11 requirements in the Safety Analysis Report for the TRUPACT-II Shipping Package (TRUPACT-11 SARP). In addition, a TRU waste is eligible for disposal at WIPP only if it has been generated in whole or in part by one or more of the activities listed in Section 10101(3) of the Nuclear Waste Policy Act. DOE sites must determine that each waste stream to be disposed of at WIPP is ''defense'' TRU waste. (See also the definition of ''defense'' TRU waste.). Only CH TRU wastes meeting the requirements of the QAPjP, WIPP-WAP, WPP-WAC, and other requirements documents described above will be accepted for transportation and disposal at WIPP.

GREAGER, T.M.

2000-12-06T23:59:59.000Z

14

Hanford Site Transuranic (TRU) Waste Certification Plan  

SciTech Connect (OSTI)

As a generator of transuranic (TRU) and TRU mixed waste destined for disposal at the Waste Isolation Pilot Plant (WIPP), the Hanford Site must ensure that its TRU waste meets the requirements of US. Department of Energy (DOE) 0 435.1, ''Radioactive Waste Management,'' and the Contact-Handled (CH) Transuranic Waste Acceptance Criteria for the Waste Isolation Pilot Plant (WIPP-WAC). WIPP-WAC requirements are derived from the WIPP Technical Safety Requirements, WIPP Safety Analysis Report, TRUPACT-II SARP, WIPP Land Withdrawal Act, WIPP Hazardous Waste Facility Permit, and Title 40 Code of Federal Regulations (CFR) 191/194 Compliance Certification Decision. The WIPP-WAC establishes the specific physical, chemical, radiological, and packaging criteria for acceptance of defense TRU waste shipments at WIPP. The WPP-WAC also requires that participating DOE TRU waste generator/treatment/storage sites produce site-specific documents, including a certification plan, that describe their program for managing TRU waste and TRU waste shipments before transferring waste to WIPP. Waste characterization activities provide much of the data upon which certification decisions are based. Waste characterization requirements for TRU waste and TRU mixed waste that contains constituents regulated under the Resource Conservation and Recovery Act (RCRA) are established in the WIPP Hazardous Waste Facility Permit Waste Analysis Plan (WAP). The Hanford Site Quality Assurance Project Plan (QAPjP) (HNF-2599) implements the applicable requirements in the WAP and includes the qualitative and quantitative criteria for making hazardous waste determinations. The Hanford Site must also ensure that its TRU waste destined for disposal at WPP meets requirements for transport in the Transuranic Package Transporter-11 (TRUPACT-11). The US. Nuclear Regulatory Commission (NRC) establishes the TRUPACT-11 requirements in the Safety Analysis Report for the TRUPACT-II Shipping Package (TRUPACT-11 SARP). In addition, a TRU waste is eligible for disposal at WIPP only if it has been generated in whole or in part by one or more of the activities listed in Section 10101(3) of the Nuclear Waste Policy Act. DOE sites must determine that each waste stream to be disposed of at WIPP is ''defense'' TRU waste. (See also the definition of ''defense'' TRU waste.). Only CH TRU wastes meeting the requirements of the QAPjP, WIPP-WAP, WPP-WAC, and other requirements documents described above will be accepted for transportation and disposal at WIPP.

GREAGER, T.M.

2000-12-01T23:59:59.000Z

15

Design of a TRU Waste Repackaging System  

SciTech Connect (OSTI)

This paper addresses the work that SRTC is performing in the design, fabrication, assembly, and testing of the TRU-Waste Repackaging Module.

Fogle, R.F.

2000-07-27T23:59:59.000Z

16

TRU waste-sampling program  

SciTech Connect (OSTI)

As part of a TRU waste-sampling program, Los Alamos National Laboratory retrieved and examined 44 drums of /sup 238/Pu- and /sup 239/Pu-contaminated waste. The drums ranged in age from 8 months to 9 years. The majority of drums were tested for pressure, and gas samples withdrawn from the drums were analyzed by a mass spectrometer. Real-time radiography and visual examination were used to determine both void volumes and waste content. Drum walls were measured for deterioration, and selected drum contents were reassayed for comparison with original assays and WIPP criteria. Each drum tested at atmospheric pressure. Mass spectrometry revealed no problem with /sup 239/Pu-contaminated waste, but three 8-month-old drums of /sup 238/Pu-contaminated waste contained a potentially hazardous gas mixture. Void volumes fell within the 81 to 97% range. Measurements of drum walls showed no significant corrosion or deterioration. All reassayed contents were within WIPP waste acceptance criteria. Five of the drums opened and examined (15%) could not be certified as packaged. Three contained free liquids, one had corrosive materials, and one had too much unstabilized particulate. Eleven drums had the wrong (or not the most appropriate) waste code. In many cases, disposal volumes had been inefficiently used. 2 refs., 23 figs., 7 tabs.

Warren, J.L.; Zerwekh, A.

1985-08-01T23:59:59.000Z

17

Hanford Site Transuranic (TRU) Waste Certification Plan  

SciTech Connect (OSTI)

The Hanford Site Transuranic Waste Certification Plan establishes the programmatic framework and criteria with in which the Hanford Site ensures that contract-handled TRU wastes can be certified as compliant with the WIPP WAC and TRUPACT-II SARP.

GREAGER, T.M.

1999-12-14T23:59:59.000Z

18

Hanford Site Transuranic (TRU) Waste Certification Plan  

SciTech Connect (OSTI)

The Hanford Site Transuranic Waste Certification Plan establishes the programmatic framework and criteria within which the Hanford Site ensures that contract-handled TRU wastes can be certified as compliant with the WIPP WAC and TRUPACT-II SARP.

GREAGER, T.M.

1999-09-09T23:59:59.000Z

19

RH-TRU Waste Content Codes  

SciTech Connect (OSTI)

The Remote-Handled Transuranic (RH-TRU) Content Codes (RH-TRUCON) document describes the inventory of RH-TRU waste within the transportation parameters specified by the Remote-Handled Transuranic Waste Authorized Methods for Payload Control (RH-TRAMPAC).1 The RH-TRAMPAC defines the allowable payload for the RH-TRU 72-B. This document is a catalog of RH-TRU 72-B authorized contents by site. A content code is defined by the following components: • A two-letter site abbreviation that designates the physical location of the generated/stored waste (e.g., ID for Idaho National Laboratory [INL]). The site-specific letter designations for each of the sites are provided in Table 1. • A three-digit code that designates the physical and chemical form of the waste (e.g., content code 317 denotes TRU Metal Waste). For RH-TRU waste to be transported in the RH-TRU 72-B, the first number of this three-digit code is “3.” The second and third numbers of the three-digit code describe the physical and chemical form of the waste. Table 2 provides a brief description of each generic code. Content codes are further defined as subcodes by an alpha trailer after the three-digit code to allow segregation of wastes that differ in one or more parameter(s). For example, the alpha trailers of the subcodes ID 322A and ID 322B may be used to differentiate between waste packaging configurations. As detailed in the RH-TRAMPAC, compliance with flammable gas limits may be demonstrated through the evaluation of compliance with either a decay heat limit or flammable gas generation rate (FGGR) limit per container specified in approved content codes. As applicable, if a container meets the watt*year criteria specified by the RH-TRAMPAC, the decay heat limits based on the dose-dependent G value may be used as specified in an approved content code. If a site implements the administrative controls outlined in the RH-TRAMPAC and Appendix 2.4 of the RH-TRU Payload Appendices, the decay heat or FGGR limits based on a 10-day shipping period (rather than the standard 60-day shipping period) may be used as specified in an approved content code. Requests for new or revised content codes may be submitted to the WIPP RH-TRU Payload Engineer for review and approval, provided all RH-TRAMPAC requirements are met.

Washington TRU Solutions

2007-07-01T23:59:59.000Z

20

Transuranic (TRU) Waste Phase I Retrieval Plan  

SciTech Connect (OSTI)

From 1970 to 1987, TRU and suspect TRU wastes at Hanford were placed in the SWBG. At the time of placement in the SWBG these wastes were not regulated under existing Resource Conservation and Recovery Act (RCRA) regulations, since they were generated and disposed of prior to the effective date of RCRA at the Hanford Site (1987). From the standpoint of DOE Order 5820.2A1, the TRU wastes are considered retrievably stored, and current plans are to retrieve these wastes for shipment to WIPP for disposal. This plan provides a strategy for the Phase I retrieval that meets the intent of TPA milestone M-91 and Project W-113, and incorporates the lessons learned during TRU retrieval campaigns at Hanford, LANL, and SRS. As in the original Project W-113 plans, the current plan calls for examination of approximately 10,000 suspect-TRU drums located in the 218-W-4C burial ground followed by the retrieval of those drums verified to contain TRU waste. Unlike the older plan, however, this plan proposes an open-air retrieval scenario similar to those used for TRU drum retrieval at LANL and SRS. Phase I retrieval consists of the activities associated with the assessment of approximately 10,000 55-gallon drums of suspect TRU-waste in burial ground 218-W-4C and the retrieval of those drums verified to contain TRU waste. Four of the trenches in 218-W-4C (Trenches 1, 4, 20, and 29) are prime candidates for Phase I retrieval because they contain large numbers of suspect TRU drums, stacked from 2 to 5 drums high, on an asphalt pad. In fact, three of the trenches (Trenches 1 , 20, and 29) contain waste that has not been covered with soil, and about 1500 drums can be retrieved without excavation. The other three trenches in 218-W-4C (Trenches 7, 19, and 24) are not candidates for Phase I retrieval because they contain significant numbers of boxes. Drums will be retrieved from the four candidate trenches, checked for structural integrity, overpacked, if necessary, and assayed at the burial ground. A mobile assay system will be used to determine if the drum is LLW (Le., contains <100 nCi/g). LLW will remain disposed of in the 218-W-4C Burial Ground. TRU waste will be retrieved and staged in the burial ground until it can be shipped to the CWC. The TRU drums will be stored at the CWC until they can be moved to WRAP. The WRAP facility will prepare the waste for shipment to WIPP for final disposal. For planning purposes, approximately 50% of the 10,000 drums have been estimated to contain LLW.

MCDONALD, K.M.

2000-09-28T23:59:59.000Z

Note: This page contains sample records for the topic "legacy tru waste" 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

Thermal processing systems for TRU mixed waste  

SciTech Connect (OSTI)

This paper presents preliminary ex situ thermal processing system concepts and related processing considerations for remediation of transuranic (TRU)-contaminated wastes (TRUW) buried at the Radioactive Waste Management Complex (RWMC) of the Idaho National Engineering Laboratory (INEL). Anticipated waste stream components and problems are considered. Thermal processing conditions required to obtain a high-integrity, low-leachability glass/ceramic final waste form are considered. Five practical thermal process system designs are compared. Thermal processing of mixed waste and soils with essentially no presorting and using incineration followed by high temperature melting is recommended. Applied research and development necessary for demonstration is also recommended.

Eddy, T.L.; Raivo, B.D.; Anderson, G.L.

1992-01-01T23:59:59.000Z

22

Thermal processing systems for TRU mixed waste  

SciTech Connect (OSTI)

This paper presents preliminary ex situ thermal processing system concepts and related processing considerations for remediation of transuranic (TRU)-contaminated wastes (TRUW) buried at the Radioactive Waste Management Complex (RWMC) of the Idaho National Engineering Laboratory (INEL). Anticipated waste stream components and problems are considered. Thermal processing conditions required to obtain a high-integrity, low-leachability glass/ceramic final waste form are considered. Five practical thermal process system designs are compared. Thermal processing of mixed waste and soils with essentially no presorting and using incineration followed by high temperature melting is recommended. Applied research and development necessary for demonstration is also recommended.

Eddy, T.L.; Raivo, B.D.; Anderson, G.L.

1992-08-01T23:59:59.000Z

23

Waste Examination Assay Facility operations: TRU waste certification  

SciTech Connect (OSTI)

The ORNL Waste Examination Assay Facility (WEAF) was established to nondestructively assay (NDA) transuranic (TRU) waste generated at Oak Ridge National Laboratory (ORNL). The present facility charter encompasses the NDA and nondestructive examination (NDE) of both TRU and low-level wastes (LLW). Presently, equipment includes a Neutron Assay System (NAS), a Segmented Gamma Scanner (SGS), a drum-sized Real-Time Radiography (RTR) system, and a Neutron Slab Detector (NSD). The first three instruments are computer interfaced. Approximately 2300 TRU waste drums have been assayed with the NAS and the SGS. Another 3000 TRU and LLW drums have been examined with the RTR unit. Computer data bases have been developed to collate the large amount of data generated during the assays and examinations. 6 refs., 1 tab.

Schultz, F.J.; Caylor, B.A.; Coffey, D.E.; Phoenix, L.B.

1987-01-01T23:59:59.000Z

24

Transuranic (TRU) Waste Phase I Retrieval Plan  

SciTech Connect (OSTI)

Phase I retrieval of post-1970 TRU wastes from burial ground 218-W-4C can be done in a safe, efficient, and cost-effective manner. Initiating TRU retrieval by retrieving uncovered drums from Trenches 1, 20, and 29, will allow retrieval to begin under the current SWBG safety authorization basis. The retrieval of buried drums from Trenches 1, 4, 20, and 29, which will require excavation, will commence once the uncovered drum are retrieved. This phased approach allows safety analysis for drum venting and drum module excavation to be completed and approved before the excavation proceeds. In addition, the lessons learned and the operational experience gained from the retrieval of uncovered drums can be applied to the more complicated retrieval of the buried drums. Precedents that have been set at SRS and LANL to perform retrieval without a trench cover, in the open air, should be followed. Open-air retrieval will result in significant cost savings over the original plans for Phase I retrieval (Project W-113). Based on LANL and SRS experience, open-air retrieval will have no adverse impacts to the environment or to the health and safety of workers or the public. Assaying the waste in the SWBG using a mobile assay system, will result in additional cost savings. It is expected that up to 50% of the suspect-TRU wastes will assay as LLW, allowing those waste to remain disposed of in the SWBG. Further processing, with its associated costs, will only occur to the portion of the waste that is verified to be TRU. Retrieval should be done, to the extent possible, under the current SWBG safety authorization basis as a normal part of SWBG operations. The use of existing personnel and existing procedures should be optimized. By working retrieval campaigns, typically during the slow months, it is easier to coordinate the availability of necessary operations personnel, and it is easier to coordinate the availability of a mobile assay vendor.

MCDONALD, K.M.

1999-08-27T23:59:59.000Z

25

CH-TRU Waste Content Codes  

SciTech Connect (OSTI)

The CH-TRU Waste Content Codes (CH-TRUCON) document describes the inventory of the U.S. Department of Energy (DOE) CH-TRU waste within the transportation parameters specified by the Contact-Handled Transuranic Waste Authorized Methods for Payload Control (CH-TRAMPAC). The CH-TRAMPAC defines the allowable payload for the Transuranic Package Transporter-II (TRUPACT-II) and HalfPACT packagings. This document is a catalog of TRUPACT-II and HalfPACT authorized contents and a description of the methods utilized to demonstrate compliance with the CH-TRAMPAC. A summary of currently approved content codes by site is presented in Table 1. The CH-TRAMPAC describes "shipping categories" that are assigned to each payload container. Multiple shipping categories may be assigned to a single content code. A summary of approved content codes and corresponding shipping categories is provided in Table 2, which consists of Tables 2A, 2B, and 2C. Table 2A provides a summary of approved content codes and corresponding shipping categories for the "General Case," which reflects the assumption of a 60-day shipping period as described in the CH-TRAMPAC and Appendix 3.4 of the CH-TRU Payload Appendices. For shipments to be completed within an approximately 1,000-mile radius, a shorter shipping period of 20 days is applicable as described in the CH-TRAMPAC and Appendix 3.5 of the CH-TRU Payload Appendices. For shipments to WIPP from Los Alamos National Laboratory (LANL), Nevada Test Site, and Rocky Flats Environmental Technology Site, a 20-day shipping period is applicable. Table 2B provides a summary of approved content codes and corresponding shipping categories for "Close-Proximity Shipments" (20-day shipping period). For shipments implementing the controls specified in the CH-TRAMPAC and Appendix 3.6 of the CH-TRU Payload Appendices, a 10-day shipping period is applicable. Table 2C provides a summary of approved content codes and corresponding shipping categories for "Controlled Shipments" (10-day shipping period).

Washington TRU Solutions LLC

2008-01-16T23:59:59.000Z

26

Repackaging SRS Black Box TRU Waste  

SciTech Connect (OSTI)

Historically, large items of TRU Waste, which were too large to be packaged in drums for disposal have been packaged in various sizes of custom made plywood boxes at the Savannah River Site (SRS), for many years. These boxes were subsequently packaged into large steel ''Black Boxes'' for storage at SRS, pending availability of Characterization and Certification capability, to facilitate disposal of larger items of TRU Waste. There are approximately 107 Black Boxes in inventory at SRS, each measuring some 18' x 12' x 7', and weighing up to 45,000 lbs. These Black Boxes have been stored since the early 1980s. The project to repackage this waste into Standard Large Boxes (SLBs), Standard Waste Boxes (SWB) and Ten Drum Overpacks (TDOP), for subsequent characterization and WIPP disposal, commenced in FY04. To date, 10 Black Boxes have been repackaged, resulting in 40 SLB-2's, and 37 B25 overpack boxes, these B25's will be overpacked in SLB-2's prior to shipping to WIPP. This paper will describe experience to date from this project.

Swale, D. J.; Stone, K.A.; Milner, T. N.

2006-01-09T23:59:59.000Z

27

TRU Waste Sampling Program: Volume I. Waste characterization  

SciTech Connect (OSTI)

Volume I of the TRU Waste Sampling Program report presents the waste characterization information obtained from sampling and characterizing various aged transuranic waste retrieved from storage at the Idaho National Engineering Laboratory and the Los Alamos National Laboratory. The data contained in this report include the results of gas sampling and gas generation, radiographic examinations, waste visual examination results, and waste compliance with the Waste Isolation Pilot Plant-Waste Acceptance Criteria (WIPP-WAC). A separate report, Volume II, contains data from the gas generation studies.

Clements, T.L. Jr.; Kudera, D.E.

1985-09-01T23:59:59.000Z

28

Multi-Year Work Plan to De-Inventory TRU Waste Stored at LANL - 12121  

SciTech Connect (OSTI)

The Los Alamos National Laboratory (LANL) continues to accelerate disposition of transuranic (TRU) waste stored at its Technical Area 54 (TA-54) Area G waste management facility. The current focus is on complete removal of all non-cemented above-grade Legacy and newly-generated TRU waste that was in storage on October 1, 2011, by no later than June 30, 2014. This inventory of above-grade TRU is defined as 3,706 m{sup 3} of material. Legacy TRU waste containers were placed into storage up to 40 years ago, and most of the older containers must be remediated to address compliance issues before the waste can be characterized, certified as meeting the Waste Isolation Pilot Plant (WIPP) Waste Acceptance Criteria (WAC), and shipped for disposition. More than half of the remaining TRU waste volume stored above grade is contained within oversize boxes that contain waste items that must be repackaged or size reduced. Facilities and major types of equipment needed to remediate and characterize the TRU waste inventory are largely in place, but two additional oversize box processing lines are being implemented in 2012. Multiple work shifts are planned for most remediation lines in 2013. An integrated risk-based project management schedule for all disposition activities has been developed that is based on a 'Solution Package' approach. Inventories of containers that have issues in common were compiled into about 15 waste categories and about 70 'Solution Packages' that identify all of the activities needed to disposition the inventory of TRU waste in storage. Scheduled activities include all precursor activities to begin remediation, remediation processing, characterization and certification to the WIPP WAC, and shipping of containers to WIPP. Processing of the 3,706 m{sup 3} is projected to result in about 4,500 55-gallon (208 L) drums and 1,000 standard waste boxes that will be shipped to WIPP. About 385 shipments from LANL to WIPP are projected before June 30, 2014, to ship these containers, at a rate of 5 to 6 shipments a week. (authors)

Johns-Hughes, K.W.; Clemmons, J.S.; Hargis, K.M.; Christensen, D.V.; Shepard, M.D. [Los Alamos National Laboratory, P.O. Box 1663, Los Alamos, New Mexico 87545 (United States); Bishop, M.L. [U.S. Department of Energy, National Nuclear Security Administration, Los Alamos Site Office, 3747 W. Jemez Road, Los Alamos, NM 87545 (United States)

2012-07-01T23:59:59.000Z

29

Final Hanford Site Transuranic (TRU) Waste Characterization QA Project Plan  

SciTech Connect (OSTI)

The Quality Assurance Project Plan (QAPjP) has been prepared for waste characterization activities to be conducted by the Transuranic (TRU) Project at the Hanford Site to meet requirements set forth in the Waste Isolation Pilot Plan (WIPP) Hazardous Waste Facility Permit, 4890139088-TSDF, Attachment B, including Attachments B1 through B6 (WAP) (DOE, 1999a). The QAPjP describes the waste characterization requirements and includes test methods, details of planned waste sampling and analysis, and a description of the waste characterization and verification process. In addition, the QAPjP includes a description of the quality assurance/quality control (QA/QC) requirements for the waste characterization program. Before TRU waste is shipped to the WIPP site by the TRU Project, all applicable requirements of the QAPjP shall be implemented. Additional requirements necessary for transportation to waste disposal at WIPP can be found in the ''Quality Assurance Program Document'' (DOE 1999b) and HNF-2600, ''Hanford Site Transuranic Waste Certification Plan.'' TRU mixed waste contains both TRU radioactive and hazardous components, as defined in the WLPP-WAP. The waste is designated and separately packaged as either contact-handled (CH) or remote-handled (RH), based on the radiological dose rate at the surface of the waste container. RH TRU wastes are not currently shipped to the WIPP facility.

GREAGER, T.M.

2000-12-06T23:59:59.000Z

30

It Just Keeps Getting Better-Tru Waste Inventory  

SciTech Connect (OSTI)

The Waste Isolation Pilot Plant (WIPP) opened on March 26, 1999, becoming the nation's first deep geologic repository for the permanent disposal of defense-generated transuranic (TRU) waste. In May 1998, the U. S. Environmental Protection Agency (EPA) certified WIPP and re-certified WIPP in March 2006. The knowledge of TRU waste inventory is fundamental to packaging, transportation, disposal strategies, resource allocation, and is also imperative when working in a regulatory framework. TRU waste inventory data are used to define the waste that will fill the WIPP repository in terms of volume, radionuclides, waste material parameters, other chemical components, and to model the impact of the waste on the performance of the WIPP over a 10,000-year evolution. The data that pertain to TRU waste is defined in the WIPP Land Withdrawal Act (LWA), as '..waste containing more that 100 nanocuries of alpha-emitting transuranic isotopes per gram of waste, with half-lives greater than 20 years..' Defining TRU waste further, the wastes are classified as either contact-handled (CH) or remote-handled (RH) TRU waste, depending on the dose rate at the surface of the waste container. CH TRU wastes are packaged with an external surface dose rate not greater than 200 milli-rem (mrem) per hour, while RH TRU wastes are packaged with an external surface dose rate of 200 mrem per hour or greater. The Los Alamos National Laboratory-Carlsbad Operations (LANL-CO) Inventory Team has developed a powerful new database, the Comprehensive Inventory Database (CID), to maintain the TRU waste inventory information. The CID is intended to replace the Transuranic Waste Baseline Inventory Database (TWBID), Revision 2.1, as the central inventory information repository for tracking all existing and potential (TRU) waste generated across the Department of Energy (DOE) TRU waste complex. It is also the source for information submitted for the Annual TRU Waste Inventory Reports some of which will be used in future Compliance Re-certification Applications (CRAs) for the WIPP. Currently, the DOE is preparing for the second re-certification, CRA-2009. The CID contains comprehensive TRU waste inventory that is consistent, relevant, and easily accessible to support DOE needs, not only the CRAs and performance assessments, but also waste management planning activities and other regulatory needs (e.g., National Environmental Policy Act (NEPA) analyses). The comprehensive inventory contains information obtained via inventory updates and approved acceptable knowledge (AK) characterization information to ensure inventory data integrity is maintained and the inventory is current. The TRU waste inventory is maintained in the CID under configuration management as defined in the LANL-CO Quality Assurance Program. The CID was developed using Microsoft{sup TM} Access Data Project{sup TM} (ADP) technology with a Microsoft SQL Server{sup TM} back end. The CID is user friendly, contains more fields, provides for easy upload of data, and has the capability to generate fully qualified data reports. To go along with the new database, the LANL-CO Inventory Team has developed an improved data collection/screening process and has excellent communications with the TRU waste site personnel. WIPP has now received over 6,000 shipments, emplaced over 50,000 cubic meters of CH waste, and successfully completed one re-certification. With a new robust qualified database, the CID, to maintain the inventory information, the TRU waste inventory information is continuously improving in quality, accuracy, and usability (better). (authors)

Lott, S.; Crawford, B.; McInroy, W.; Van Soest, G.; McTaggart, J.; Guerin, D. [Los Alamos National Laboratory-Carlsbad Operations, Carlsbad, NM (United States); Patterson, R. [U.S. Department of Energy Carlsbad, Field Office, Carlsbad, NM (United States)

2008-07-01T23:59:59.000Z

31

Terminating Safeguards on Excess Special Nuclear Material: Defense TRU Waste Clean-up and Nonproliferation - 12426  

SciTech Connect (OSTI)

The Department of Energy (DOE) and the National Nuclear Security Administration (NNSA) manages defense nuclear material that has been determined to be excess to programmatic needs and declared waste. When these wastes contain plutonium, they almost always meet the definition of defense transuranic (TRU) waste and are thus eligible for disposal at the Waste Isolation Pilot Plant (WIPP). The DOE operates the WIPP in a manner that physical protections for attractiveness level D or higher special nuclear material (SNM) are not the normal operating condition. Therefore, there is currently a requirement to terminate safeguards before disposal of these wastes at the WIPP. Presented are the processes used to terminate safeguards, lessons learned during the termination process, and how these approaches might be useful for future defense TRU waste needing safeguards termination prior to shipment and disposal at the WIPP. Also described is a new criticality control container, which will increase the amount of fissile material that can be loaded per container, and how it will save significant taxpayer dollars. Retrieval, compliant packaging and shipment of retrievably stored legacy TRU waste has dominated disposal operations at WIPP since it began operations 12 years ago. But because most of this legacy waste has successfully been emplaced in WIPP, the TRU waste clean-up focus is turning to newly-generated TRU materials. A major component will be transuranic SNM, currently managed in safeguards-protected vaults around the weapons complex. As DOE and NNSA continue to consolidate and shrink the weapons complex footprint, it is expected that significant quantities of transuranic SNM will be declared surplus to the nation's needs. Safeguards termination of SNM varies due to the wide range of attractiveness level of the potential material that may be directly discarded as waste. To enhance the efficiency of shipping waste with high TRU fissile content to WIPP, DOE designed an over-pack container, similar to the pipe component, called the criticality control over-pack, which will significantly enhance the efficiency of disposal. Hundreds of shipments of transuranic SNM, suitably packaged to meet WIPP waste acceptance criteria and with safeguards terminated have been successfully emplaced at WIPP (primarily from the Rocky Flats site clean-up) since WIPP opened. DOE expects that thousands more may eventually result from SNM consolidation efforts throughout the weapons complex. (authors)

Hayes, Timothy [Los Alamos National Laboratory, Carlsbad Operations Group (United States); Nelson, Roger [Department Of Energy, Carlsbad Operations Office (United States)

2012-07-01T23:59:59.000Z

32

Transuranic (TRU) Waste Repackaging at the Nevada Test Site  

SciTech Connect (OSTI)

This paper describes the activities required to modify a facility and the process of characterizing, repackaging, and preparing for shipment the Nevada Test Site’s (NTS) legacy transuranic (TRU) waste in 58 oversize boxes (OSB). The waste, generated at other U.S. Department of Energy (DOE) sites and shipped to the NTS between 1974 and 1990, requires size-reduction for off-site shipment and disposal. The waste processing approach was tailored to reduce the volume of TRU waste by employing decontamination and non-destructive assay. As a result, the low-level waste (LLW) generated by this process was packaged, with minimal size reduction, in large sea-land containers for disposal at the NTS Area 5 Radioactive Waste Management Complex (RWMC). The remaining TRU waste was repackaged and sent to the Idaho National Laboratory Consolidation Site for additional characterization in preparation for disposal at the Waste Isolation Pilot Plant (WIPP), near Carlsbad, New Mexico. The DOE National Nuclear Security Administration Nevada Site Office and the NTS Management and Operating (M&O) contractor, NSTec, successfully partnered to modify and upgrade an existing facility, the Visual Examination and Repackaging Building (VERB). The VERB modifications, including a new ventilation system and modified containment structure, required an approved Preliminary Documented Safety Analysis prior to project procurement and construction. Upgrade of the VERB from a radiological facility to a Hazard Category 3 Nuclear Facility required new rigor in the design and construction areas and was executed on an aggressive schedule. The facility Documented Safety Analysis required that OSBs be vented prior to introduction into the VERB. Box venting was safely completed after developing and implementing two types of custom venting systems for the heavy gauge box construction. A remotely operated punching process was used on boxes with wall thickness of up to 3.05 mm (0.120 in) to insert aluminum bronze filters and sample ports to prevent sparking during penetration. A remotely operated cold-drilling process with self-drilling, self-tapping titanium coated spark-resistant filters was used for boxes with wall thickness of up to 6.35 mm (0.25 in). The box headspace was sampled for the presence of flammable gases. To further accelerate the project schedule, an innovative treatment process was used. Several of the OSBs were re-assayed and determined to be mixed low-level waste (MLLW) which allowed treatment, followed by disposal in the Mixed Waste Disposal Unit at the NTS Area 5 Radioactive Waste Management Complex (RWMC). The MLLW boxes were certified using real-time radiography and overpacked into custom-built polyethylene-lined macroencapsulation containers. The polyethylene-lined lid was welded to the poly-lined box using automatically controlled resistance heating through embedded wiring in the lid. The work was performed under the existing Documented Safety Analysis since plastic welding is accomplished at low temperature and does not introduce the risks of other macroencapsulation processes, such as welding stainless steel containers. The macroencapsulation process for MLLW not only accelerated the schedule by reducing the number of boxes requiring size reduction, but it also resulted in significantly improved safety with as low as reasonable achievable levels of exposure to workers plus reduced cost by eliminating the need to perform repackaging in the VERB.

E.F. Di Sanza; G. Pyles; J. Ciucci; P. Arnold

2009-03-01T23:59:59.000Z

33

Centralized processing of contact-handled TRU waste feasibility analysis  

SciTech Connect (OSTI)

This report presents work for the feasibility study of central processing of contact-handled TRU waste. Discussion of scenarios, transportation options, summary of cost estimates, and institutional issues are a few of the subjects discussed. (JDL)

Not Available

1986-12-01T23:59:59.000Z

34

Safety Enhancements for TRU Waste Handling - 12258  

SciTech Connect (OSTI)

For years, proper Health Physics practices and 'As Low As Reasonably Achievable' (ALARA) principles have fostered the use of glove boxes or other methods of handling (without direct contact) high activities of radioactive material. The physical limitations of using glove boxes on certain containers have resulted in high-activity wastes being held in storage awaiting a path forward. Highly contaminated glove boxes and other remote handling equipment no longer in use have also been added to the growing list of items held for storage with no efficient method of preparation for proper disposal without creating exposure risks to personnel. This is especially true for wastes containing alpha-emitting radionuclides such as Plutonium and Americium that pose significant health risks to personnel if these Transuranic (TRU) wastes are not controlled effectively. Like any good safety program or root cause investigation PFNW has found that the identification of the cause of a negative change, if stopped, can result in a near miss and lessons learned. If this is done in the world of safety, it is considered a success story and is to be shared with others to protect the workers. PFNW believes that the tools, equipment and resources have improved over the past number of years but that the use of them has not progressed at the same rate. If we use our tools to timely identify the effect on the work environment and immediately following or possibly even simultaneously identify the cause or some of the causal factors, we may have the ability to continue to work rather than succumb to the start and stop-work mentality trap that is not beneficial in waste minimization, production efficiency or ALARA. (authors)

Cannon, Curt N. [Perma-Fix Northwest Richland, Inc., Richland, WA 99354 (United States)

2012-07-01T23:59:59.000Z

35

Guidelines for developing certification programs for newly generated TRU waste  

SciTech Connect (OSTI)

These guidelines were prepared with direction from the US Department of Energy (DOE) Transuranic (TRU) Waste Management Program in support of the DOE effort to certify that newly generated TRU wastes meet the Waste Isolation Pilot Plant (WIPP) Waste Acceptance Criteria. The guidelines provide instructions for generic Certification Program preparation for TRU-waste generators preparing site-specific Certification Programs in response to WIPP requirements. The guidelines address all major aspects of a Certification Program that are necessary to satisfy the WIPP Waste Acceptance Criteria and their associated Compliance Requirements and Certification Quality Assurance Requirements. The details of the major element of a Certification Program, namely, the Certification Plan, are described. The Certification Plan relies on supporting data and control documentation to provide a traceable, auditable account of certification activities. Examples of specific parts of the Certification Plan illustrate the recommended degree of detail. Also, a brief description of generic waste processes related to certification activities is included.

Whitty, W.J.; Ostenak, C.A.; Pillay, K.K.S.; Geoffrion, R.R.

1983-05-01T23:59:59.000Z

36

The Advantages of Fixed Facilities in Characterizing TRU Wastes  

SciTech Connect (OSTI)

In May 1998 the Hanford Site started developing a program for characterization of transuranic (TRU) waste for shipment to the Waste Isolation Pilot Plant (WIPP) in New Mexico. After less than two years, Hanford will have a program certified by the Carlsbad Area Office (CAO). By picking a simple waste stream, taking advantage of lessons learned at the other sites, as well as communicating effectively with the CAO, Hanford was able to achieve certification in record time. This effort was further simplified by having a centralized program centered on the Waste Receiving and Processing (WRAP) Facility that contains most of the equipment required to characterize TRU waste. The use of fixed facilities for the characterization of TRU waste at sites with a long-term clean-up mission can be cost effective for several reasons. These include the ability to control the environment in which sensitive instrumentation is required to operate and ensuring that calibrations and maintenance activities are scheduled and performed as an operating routine. Other factors contributing to cost effectiveness include providing approved procedures and facilities for handling hazardous materials and anticipated contingencies and performing essential evolutions, and regulating and smoothing the work load and environmental conditions to provide maximal efficiency and productivity. Another advantage is the ability to efficiently provide characterization services to other sites in the Department of Energy (DOE) Complex that do not have the same capabilities. The Waste Receiving and Processing (WRAP) Facility is a state-of-the-art facility designed to consolidate the operations necessary to inspect, process and ship waste to facilitate verification of contents for certification to established waste acceptance criteria. The WRAP facility inspects, characterizes, treats, and certifies transuranic (TRU), low-level and mixed waste at the Hanford Site in Washington state. Fluor Hanford operates the $89 million facility under the Project Hanford Management Contract. This paper describes the operating experiences and results obtained during the first year of full operations at WRAP. Interested audiences include personnel involved in TRU waste characterization activities, TRU waste treatment and disposal facilities and TRU waste certification. The conclusions of this paper are that WRAP has proven itself to be a valuable asset for low-level and TRU waste management.

FRENCH, M.S.

2000-02-08T23:59:59.000Z

37

RH-TRU Waste Content Codes (RH-TRUCON)  

SciTech Connect (OSTI)

The Remote-Handled Transuranic (RH-TRU) Content Codes (RH-TRUCON) document describes the inventory of RH-TRU waste within the transportation parameters specified by the Remote-Handled Transuranic Waste Authorized Methods for Payload Control (RH-TRAMPAC).1 The RH-TRAMPAC defines the allowable payload for the RH-TRU 72-B. This document is a catalog of RH-TRU 72-B authorized contents by site. A content code is defined by the following components: • A two-letter site abbreviation that designates the physical location of the generated/stored waste (e.g., ID for Idaho National Laboratory [INL]). The site-specific letter designations for each of the sites are provided in Table 1. • A three-digit code that designates the physical and chemical form of the waste (e.g., content code 317 denotes TRU Metal Waste). For RH-TRU waste to be transported in the RH-TRU 72-B, the first number of this three-digit code is “3.” The second and third numbers of the three-digit code describe the physical and chemical form of the waste. Table 2 provides a brief description of each generic code. Content codes are further defined as subcodes by an alpha trailer after the three-digit code to allow segregation of wastes that differ in one or more parameter(s). For example, the alpha trailers of the subcodes ID 322A and ID 322B may be used to differentiate between waste packaging configurations. As detailed in the RH-TRAMPAC, compliance with flammable gas limits may be demonstrated through the evaluation of compliance with either a decay heat limit or flammable gas generation rate (FGGR) limit per container specified in approved content codes. As applicable, if a container meets the watt*year criteria specified by the RH-TRAMPAC, the decay heat limits based on the dose-dependent G value may be used as specified in an approved content code. If a site implements the administrative controls outlined in the RH-TRAMPAC and Appendix 2.4 of the RH-TRU Payload Appendices, the decay heat or FGGR limits based on a 10-day shipping period (rather than the standard 60-day shipping period) may be used as specified in an approved content code. Requests for new or revised content codes may be submitted to the WIPP RH-TRU Payload Engineer for review and approval, provided all RH-TRAMPAC requirements are met.

Washington TRU Solutions LLC

2007-08-01T23:59:59.000Z

38

RH-TRU Waste Content Codes (RH-TRUCON)  

SciTech Connect (OSTI)

The Remote-Handled Transuranic (RH-TRU) Content Codes (RH-TRUCON) document describes the inventory of RH-TRU waste within the transportation parameters specified by the Remote-Handled Transuranic Waste Authorized Methods for Payload Control (RH-TRAMPAC).1 The RH-TRAMPAC defines the allowable payload for the RH-TRU 72-B. This document is a catalog of RH-TRU 72-B authorized contents by site. A content code is defined by the following components: • A two-letter site abbreviation that designates the physical location of the generated/stored waste (e.g., ID for Idaho National Laboratory [INL]). The site-specific letter designations for each of the sites are provided in Table 1. • A three-digit code that designates the physical and chemical form of the waste (e.g., content code 317 denotes TRU Metal Waste). For RH-TRU waste to be transported in the RH-TRU 72-B, the first number of this three-digit code is “3.” The second and third numbers of the three-digit code describe the physical and chemical form of the waste. Table 2 provides a brief description of each generic code. Content codes are further defined as subcodes by an alpha trailer after the three-digit code to allow segregation of wastes that differ in one or more parameter(s). For example, the alpha trailers of the subcodes ID 322A and ID 322B may be used to differentiate between waste packaging configurations. As detailed in the RH-TRAMPAC, compliance with flammable gas limits may be demonstrated through the evaluation of compliance with either a decay heat limit or flammable gas generation rate (FGGR) limit per container specified in approved content codes. As applicable, if a container meets the watt*year criteria specified by the RH-TRAMPAC, the decay heat limits based on the dose-dependent G value may be used as specified in an approved content code. If a site implements the administrative controls outlined in the RH-TRAMPAC and Appendix 2.4 of the RH-TRU Payload Appendices, the decay heat or FGGR limits based on a 10-day shipping period (rather than the standard 60-day shipping period) may be used as specified in an approved content code. Requests for new or revised content codes may be submitted to the WIPP RH-TRU Payload Engineer for review and approval, provided all RH-TRAMPAC requirements are met.

Washington TRU Solutions

2007-05-30T23:59:59.000Z

39

RH-TRU Waste Inventory Characterization by AK and Proposed WIPP RH-TRU Waste Characterization Objectives  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE)-Carlsbad Field Office (CBFO) has developed draft documentation to present the proposed Waste Isolation Pilot Plant (WIPP) remote-handled (RH-) transuranic (TRU) waste characterization program to its regulators, the U.S. Environmental Protection Agency and the New Mexico Environment Department. Compliance with Title 40, Code of Federal Regulations, Parts 191 and 194; the WIPP Land Withdrawal Act (PL 102-579); and the WIPP Hazardous Waste Facility Permit, as well as the Certificates of Compliance for the 72-B and 10-160B Casks, requires that specific waste parameter limits be imposed on DOE sites disposing of TRU waste at WIPP. The DOE-CBFO must control the sites' compliance with the limits by specifying allowable characterization methods. As with the established WIPP contact handled TRU waste characterization program, the DOE-CBFO has proposed a Remote-Handled TRU Waste Acceptance Criteria (RH-WAC) document consolidating the requirements from various regulatory drivers and proposed allowable characterization methods. These criteria are consistent with the recommendation of a recent National Academy Sciences/National Research Council to develop an RH-TRU waste characterization approach that removes current self imposed requirements that lack a legal or safety basis. As proposed in the draft RH-WAC and other preliminary documents, the DOE-CBFO RH-TRU waste characterization program proposes the use of acceptable knowledge (AK) as the primary method for obtaining required characterization information. The use of AK involves applying knowledge of the waste in light of the materials or processes used to generate the waste. Documentation, records, or processes providing information about various attributes of a waste stream, such as chemical, physical, and radiological properties, may be used as AK and may be applied to individual waste containers either independently or in conjunction with radiography, visual examination, assay, and other sampling and analytical data. RH-TRU waste cannot be shipped to WIPP on the basis of AK alone if documentation demonstrating that all of the prescribed limits in the RH-WAC are met is not available, discrepancies exist among AK source documents describing the same waste stream and the most conservative assumptions regarding those documents indicates that a limit will not be met, or all required data are not available for a given waste stream.

Most, W. A.; Kehrman, R.; Gist, C.; Biedscheid, J.; Devarakonda, J.; Whitworth, J.

2002-02-26T23:59:59.000Z

40

RH-TRU Waste Content Codes (RH TRUCON)  

SciTech Connect (OSTI)

The Remote-Handled Transuranic (RH-TRU) Content Codes (RH-TRUCON) document describes the inventory of RH-TRU waste within the transportation parameters specified by the Remote-Handled Transuranic Waste Authorized Methods for Payload Control (RH-TRAMPAC).1 The RH-TRAMPAC defines the allowable payload for the RH-TRU 72-B. This document is a catalog of RH-TRU 72-B authorized contents by site. A content code is defined by the following components: • A two-letter site abbreviation that designates the physical location of the generated/stored waste (e.g., ID for Idaho National Laboratory [INL]). The site-specific letter designations for each of the sites are provided in Table 1. • A three-digit code that designates the physical and chemical form of the waste (e.g., content code 317 denotes TRU Metal Waste). For RH-TRU waste to be transported in the RH-TRU 72-B, the first number of this three-digit code is “3.” The second and third numbers of the three-digit code describe the physical and chemical form of the waste. Table 2 provides a brief description of each generic code. Content codes are further defined as subcodes by an alpha trailer after the three-digit code to allow segregation of wastes that differ in one or more parameter(s). For example, the alpha trailers of the subcodes ID 322A and ID 322B may be used to differentiate between waste packaging configurations. As detailed in the RH-TRAMPAC, compliance with flammable gas limits may be demonstrated through the evaluation of compliance with either a decay heat limit or flammable gas generation rate (FGGR) limit per container specified in approved content codes. As applicable, if a container meets the watt*year criteria specified by the RH-TRAMPAC, the decay heat limits based on the dose-dependent G value may be used as specified in an approved content code. If a site implements the administrative controls outlined in the RH-TRAMPAC and Appendix 2.4 of the RH-TRU Payload Appendices, the decay heat or FGGR limits based on a 10-day shipping period (rather than the standard 60-day shipping period) may be used as specified in an approved content code.

Washington TRU Solutions

2007-05-01T23:59:59.000Z

Note: This page contains sample records for the topic "legacy tru waste" 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

TRU waste certification and TRUPACT-2 payload verification  

SciTech Connect (OSTI)

The Waste Isolation Pilot Plant (WIPP) established a policy that requires each waste shipper to verify that all waste shipments meet the requirements of the Waste Acceptance Criteria (WAC) prior to being shipped. This verification provides assurance that transuranic (TRU) wastes meet the criteria while still retained in a facility where discrepancies can be immediately corrected. Each Department of Energy (DOE) TRU waste facility planning to ship waste to the Waste Isolation Pilot Plant (WIPP) is required to develop and implement a specific program including Quality Assurance (QA) provisions to verify that waste is in full compliance with WIPP's WAC. This program is audited by a composite DOE and contractor audit team prior to granting the facility permission to certify waste. During interaction with the Nuclear Regulatory Commission (NRC) on payload verification for shipping in TRUPACT-II, a similar system was established by DOE. The TRUPACT-II Safety Analysis Report (SAR) contains the technical requirements and physical and chemical limits that payloads must meet (like the WAC). All shippers must plan and implement a payload control program including independent QA provisions. A similar composite audit team will conduct preshipment audits, frequent subsequent audits, and operations inspections to verify that all TRU waste shipments in TRUPACT-II meet the requirements of the Certificate of Compliance issued by the NRC which invokes the SAR requirements. 1 fig.

Hunter, E.K. (USDOE Albuquerque Operations Office, Carlsbad, NM (USA). Waste Isolation Pilot Plant Project Office); Johnson, J.E. (Westinghouse Electric Corp., Carlsbad, NM (USA). Waste Isolation Div.)

1990-01-01T23:59:59.000Z

42

The Road to Re-certification: WIPP TRU Waste Inventory  

SciTech Connect (OSTI)

The Waste Isolation Pilot Plant (WIPP), located near Carlsbad, New Mexico, is a deep geologic repository for the disposal of transuranic (TRU) wastes generated by atomic energy defense activities. The WIPP Land Withdrawal Act (LWA) [1] requires the U.S. Department of Energy (DOE) to submit documentation to the U.S. Environmental Protection Agency (EPA) that demonstrates WIPP's continuing compliance with the disposal regulations in Title 40 of the Code of Federal Regulations (CFR) Part 191 Subparts B and C, not later than five years after initial receipt of waste for disposal at the repository, and every five years thereafter until the decommissioning of the facility is completed. On May 18, 1998, after review of the Compliance Certification Application (CCA) (63 FR 27405), the EPA certified that the WIPP did comply with the final disposal regulations and criteria of 40 CFR parts 191 and 194. On March 26, 1999, the first receipt of contact-handled (CH) TRU waste was received at WIPP thus initiating the 5-year countdown to the first re-certification. Five years after the first receipt of waste at WIPP, on March 26, 2004, the DOE submitted a Compliance Re-certification Application (CRA) [2]. The CRA includes TRU waste inventory as a key factor. The TRU waste inventory defines what is expected to be emplaced in the repository; and, therefore, how the performance of the repository will be affected. Performance of the WIPP is determined via the Performance Assessment (PA), a set of complex algorithms used to model the long-term performance of the repository. The TRU waste inventory data that are important to this assessment include: 1) volumes of stored, projected and emplaced waste; 2) radionuclide activity concentrations; 3) waste material parameter densities; 4) estimates of the masses of chelating agents; 5) estimates of the oxyanions; 6) estimates of expected cement masses; and 7) estimates of the types and amounts of materials that will be used to emplace the waste. The data that are collected and maintained as the TRU waste inventory provide the waste source term used in the PA to model long-term repository performance. (authors)

Crawford, B.A.; Lott, S.A.; Sparks, L.D.; Van Soest, G.; Mclnroy, B. [Los Alamos National Laboratory -Carlsbad Operations, 115 N. Main St., Carlsbad, NM 88220 (United States)

2006-07-01T23:59:59.000Z

43

Repackaging of High Fissile TRU Waste at the Transuranic Waste Processing Center - 13240  

SciTech Connect (OSTI)

Twenty-six drums of high fissile transuranic (TRU) waste from Oak Ridge National Laboratory (ORNL) operations were declared waste in the mid-1980's and placed in storage with the legacy TRU waste inventory for future treatment and disposal at the Waste Isolation Pilot Plant (WIPP). Repackaging and treatment of the waste at the TRU Waste Packaging Center (TWPC) will require the installation of additional equipment and capabilities to address the hazards for handling and repackaging the waste compared to typical Contact Handled (CH) TRU waste that is processed at the TWPC, including potential hydrogen accumulation in legacy 6M/2R packaging configurations, potential presence of reactive plutonium hydrides, and significant low energy gamma radiation dose rates. All of the waste is anticipated to be repackaged at the TWPC and certified for disposal at WIPP. The waste is currently packaged in multiple layers of containers which presents additional challenges for repackaging activities due to the potential for the accumulation of hydrogen gas in the container headspace in quantities than could exceed the Lower Flammability Limit (LFL). The outer container for each waste package is a stainless steel 0.21 m{sup 3} (55-gal) drum which contains either a 0.04 m{sup 3} or 0.06 m{sup 3} (10-gal or 15-gal) 6M drum. The inner 2R container in each 6M drum is ?12 cm (5 in) outside diameter x 30-36 cm (12-14 in) long and is considered to be a > 4 liter sealed container relative to TRU waste packaging criteria. Inside the 2R containers are multiple configurations of food pack cans, pipe nipples, and welded capsules. The waste contains significant quantities of high burn-up plutonium oxides and metals with a heavy weight percentage of higher atomic mass isotopes and the subsequent in-growth of significant quantities of americium. Significant low energy gamma radiation is expected to be present due to the americium in-growth. Radiation dose rates on inner containers are estimated to be 1-3 mSv/hr (100-300 mrem/hr) with an unshielded dose rate on the waste itself of over 10 mSv/hr (1 rem/hr). Additional equipment to be installed at the TWPC will include a new perma-con enclosure and a shielded/inert glovebox in the process building to repackage and stabilize the waste. All of the waste will be repackaged into Standard Pipe Overpacks. Most of the waste (21 of the 26 drums) is expected to be repackaged at the food-pack can level (i.e. the food-pack cans will not be opened). Five of the incoming waste containers are expected to be repackaged at the primary waste level. Three of the containers exceed the 200 gram Pu-239 Fissile Gram Equivalent (FGE) limit for the Standard Pipe Overpack. These three containers will be repackaged down to the primary waste level and divided into eight Standard Pipe Overpacks for shipment to WIPP. Two containers must be stabilized to eliminate any reactive plutonium hydrides that may be present. These containers will be opened in the inert, shielded glovebox, and the remaining corroded plutonium metal converted to a stable oxide form by using a 600 deg. C tube furnace with controlled oxygen feed in a helium carrier gas. The stabilized waste will then be packaged into two Standard Pipe Overpacks. Design and build out activities for the additional repackaging capabilities at the TWPC are scheduled to begin in Fiscal Year 2013 with repackaging, stabilization, and certification activities scheduled to begin in Fiscal Year 2014. Following repackaging and stabilization activities, the Standard Pipe Overpacks will be certified for disposal at WIPP utilizing Non-Destructive Examination (NDE) to verify the absence of prohibited items and Non-Destructive Assay (NDA) to verify the isotopic content under the TWPC WIPP certification program implemented by the Central Characterization Project (CCP). (authors)

Oakley, Brian; Heacker, Fred [WAI, TRU Waste Processing Center, 100 WIPP Road Lenoir City, TN 37771 (United States)] [WAI, TRU Waste Processing Center, 100 WIPP Road Lenoir City, TN 37771 (United States); McMillan, Bill [DOE, Oak Ridge Operations, Bldg. 2714, Oak Ridge, TN 37830 (United States)] [DOE, Oak Ridge Operations, Bldg. 2714, Oak Ridge, TN 37830 (United States)

2013-07-01T23:59:59.000Z

44

Test Plan: WIPP bin-scale CH TRU waste tests  

SciTech Connect (OSTI)

This WIPP Bin-Scale CH TRU Waste Test program described herein will provide relevant composition and kinetic rate data on gas generation and consumption resulting from TRU waste degradation, as impacted by synergistic interactions due to multiple degradation modes, waste form preparation, long-term repository environmental effects, engineered barrier materials, and, possibly, engineered modifications to be developed. Similar data on waste-brine leachate compositions and potentially hazardous volatile organic compounds released by the wastes will also be provided. The quantitative data output from these tests and associated technical expertise are required by the WIPP Performance Assessment (PA) program studies, and for the scientific benefit of the overall WIPP project. This Test Plan describes the necessary scientific and technical aspects, justifications, and rational for successfully initiating and conducting the WIPP Bin-Scale CH TRU Waste Test program. This Test Plan is the controlling scientific design definition and overall requirements document for this WIPP in situ test, as defined by Sandia National Laboratories (SNL), scientific advisor to the US Department of Energy, WIPP Project Office (DOE/WPO). 55 refs., 16 figs., 19 tabs.

Molecke, M.A.

1990-08-01T23:59:59.000Z

45

TRU waste inventory collection and work off plans for the centralization of TRU waste characterization/certification at INL - on your mark - get set - 9410  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE) amended the Record of Decision (ROD) for the Waste Management Program: Treatment and Storage of Transuranic Waste to centralize transuranic (TRU) waste characterization/certification from fourteen TRU waste sites. This centralization will allow for treatment, characterization and certification ofTRU waste from the fourteen sites, thirteen of which are sites with small quantities ofTRU waste, at the Idaho National Laboratory (INL) prior to shipping the waste to the Waste Isolation Pilot Plant (WIPP) for disposal. Centralization of this TRU waste will avoid the cost of building treatment, characterization, certification, and shipping capabilities at each of the small quantity sites that currently do not have existing facilities. Advanced Mixed Waste Treatment Project (AMWTP) and Idaho Nuclear Technology and Engineering Center (INTEC) will provide centralized shipping facilities, to WIPP, for all of the small quantity sites. Hanford, the one large quantity site identified in the ROD, has a large number of waste in containers that are overpacked into larger containers which are inefficient for shipment to and disposal at WIPP. The AMWTF at the INL will reduce the volume of much of the CH waste and make it much more efficient to ship and dispose of at WIPP. In addition, the INTEC has a certified remote handled (RH) TRU waste characterization/certification program at INL to disposition TRU waste from the sites identified in the ROD.

Mctaggert, Jerri Lynne [Los Alamos National Laboratory; Lott, Sheila A [Los Alamos National Laboratory; Gadbury, Casey [CBFO

2008-01-01T23:59:59.000Z

46

TRU waste inventory collection and work-off plans for the centralization of TRU waste characterization at INL - on your mark - get set - 9410  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE) amended the Record of Decision (ROD) for the Waste Management Program: Treatment and Storage ofTransuranic Waste to centralize transuranic (TRU) waste characterization/certification from fourteen TRU waste sites. This centralization will allow for treatment, characterization and certification ofTRU waste from the fourteen sites, thirteen of which are sites with small quantities ofTRU waste, at the Idaho National Laboratory (INL) prior to shipping the waste to the Waste Isolation Pilot Plant (WIPP) for disposal. Centralization ofthis TRU waste will avoid the cost ofbuilding treatment, characterization, certification, and shipping capabilities at each ofthe small quantity sites that currently do not have existing facilities. Advanced Mixed Waste Treatment Project (AMWTP) and Idaho Nuclear Technology and Engineering Center (INTEC) will provide centralized shipping facilities, to WIPP, for all ofthe small quantity sites. Hanford, the one large quantity site identified in the ROD, has a large number ofwaste in containers that are overpacked into larger containers which are inefficient for shipment to and disposal at WIPP. The AMWTP at the INL will reduce the volume ofmuch of the CH waste and make it much more efficient to ship and dispose of at WIPP. In addition, the INTEC has a certified remote handled (RH) TRU waste characterization/certification program at INL to disposition TRU waste from the sites identified in the ROD.

Mctaggert, Jerri Lynne [Los Alamos National Laboratory; Lott, Sheila [Los Alamos National Laboratory; Gadbury, Casey [CBFO

2009-01-01T23:59:59.000Z

47

TRU Waste Management Program. Cost/schedule optimization analysis  

SciTech Connect (OSTI)

This Current Year Work Plan presents in detail a description of the activities to be performed by the Joint Integration Office Rockwell International (JIO/RI) during FY86. It breaks down the activities into two major work areas: Program Management and Program Analysis. Program Management is performed by the JIO/RI by providing technical planning and guidance for the development of advanced TRU waste management capabilities. This includes equipment/facility design, engineering, construction, and operations. These functions are integrated to allow transition from interim storage to final disposition. JIO/RI tasks include program requirements identification, long-range technical planning, budget development, program planning document preparation, task guidance development, task monitoring, task progress information gathering and reporting to DOE, interfacing with other agencies and DOE lead programs, integrating public involvement with program efforts, and preparation of reports for DOE detailing program status. Program Analysis is performed by the JIO/RI to support identification and assessment of alternatives, and development of long-term TRU waste program capabilities. These analyses include short-term analyses in response to DOE information requests, along with performing an RH Cost/Schedule Optimization report. Systems models will be developed, updated, and upgraded as needed to enhance JIO/RI's capability to evaluate the adequacy of program efforts in various fields. A TRU program data base will be maintained and updated to provide DOE with timely responses to inventory related questions.

Detamore, J.A.; Raudenbush, M.H.; Wolaver, R.W.; Hastings, G.A.

1985-10-01T23:59:59.000Z

48

Facility Utilization and Risk Analysis for Remediation of Legacy Transuranic Waste at the Savannah River Site - 13572  

SciTech Connect (OSTI)

Savannah River Nuclear Solutions (SRNS) completed the Accelerated TRU Project for remediating legacy waste at the Savannah River Site with significant cost and schedule efficiencies due to early identification of resources and utilization of risk matrices. Initial project planning included identification of existing facilities that could be modified to meet the technical requirements needed for repackaging and remediating the waste. The project schedule was then optimized by utilization of risk matrices that identified alternate strategies and parallel processing paths which drove the overall success of the project. Early completion of the Accelerated TRU Project allowed SRNS to pursue stretch goals associated with remediating very difficult TRU waste such as concrete casks from the hot cells in the Savannah River National Laboratory. Project planning for stretch goals also utilized existing facilities and the risk matrices. The Accelerated TRU project and stretch goals were funded under the American Recovery and Reinvestment Act (ARRA). (authors)

Gilles, Michael L.; Gilmour, John C. [Savannah River Nuclear Solutions, LLC (United States)] [Savannah River Nuclear Solutions, LLC (United States)

2013-07-01T23:59:59.000Z

49

Expert System for Building TRU Waste Payloads - 13554  

SciTech Connect (OSTI)

The process for grouping TRU waste drums into payloads for shipment to the Waste Isolation Pilot Plant (WIPP) for disposal is a very complex process. Transportation and regulatory requirements must be met, along with striving for the goals of shipment efficiency: maximize the number of waste drums in a shipment and minimize the use of empty drums which take up precious underground storage space. The restrictions on payloads range from weight restrictions, to limitations on flammable gas in the headspace, to minimum TRU alpha activity concentration requirements. The Overpack and Payload Assistant Tool (OPAT) has been developed as a mixed-initiative intelligent system within the WIPP Waste Data System (WDS) to guide the construction of multiple acceptable payloads. OPAT saves the user time while at the same time maximizes the efficiency of shipments for the given drum population. The tool provides the user with the flexibility to tune critical factors that guide OPAT's operation based on real-time feedback concerning the results of the execution. This feedback complements the user's external knowledge of the drum population (such as location of drums, known challenges, internal shipment goals). This work demonstrates how software can be utilized to complement the unique domain knowledge of the users. The mixed-initiative approach combines the insight and intuition of the human expert with the proficiency of automated computational algorithms. The result is the ability to thoroughly and efficiently explore the search space of possible solutions and derive the best waste management decision. (authors)

Bruemmer, Heather; Slater, Bryant [Information Systems Laboratories, 2235 East 25th Street, Suite 100, Idaho Falls, ID 83404 (United States)] [Information Systems Laboratories, 2235 East 25th Street, Suite 100, Idaho Falls, ID 83404 (United States)

2013-07-01T23:59:59.000Z

50

TRU Waste Management Program cost/schedule optimization analysis  

SciTech Connect (OSTI)

The cost/schedule optimization task is a necessary function to insure that program goals and plans are optimized from a cost and schedule aspect. Results of this study will offer DOE information with which it can establish, within institutional constraints, the most efficient program for the long-term management and disposal of contact handled transuranic waste (CH-TRU). To this end, a comprehensive review of program cost/schedule tradeoffs has been made, to identify any major cost saving opportunities that may be realized by modification of current program plans. It was decided that all promising scenarios would be explored, and institutional limitations to implementation would be described. Since a virtually limitless number of possible scenarios can be envisioned, it was necessary to distill these possibilities into a manageable number of alternatives. The resultant scenarios were described in the cost/schedule strategy and work plan document. Each scenario was compared with the base case: waste processing at the originating site; transport of CH-TRU wastes in TRUPACT; shipment of drums in 6-Packs; 25 year stored waste workoff; WIPP operational 10/88, with all sites shipping to WIPP beginning 10/88; and no processing at WIPP. Major savings were identified in two alternate scenarios: centralize waste processing at INEL and eliminate rail shipment of TRUPACT. No attempt was made to calculate savings due to combination of scenarios. 1 ref., 5 figs., 1 tab. (MHB)

Detamore, J.A. (Rockwell International Corp., Albuquerque, NM (United States). Joint Integration Office); Raudenbush, M.H.; Wolaver, R.W.; Hastings, G.A. (Stoller (S.M.) Corp., Boulder, CO (United States))

1985-10-01T23:59:59.000Z

51

CH-TRU Waste Content Codes (CH-TRUCON)  

SciTech Connect (OSTI)

The CH-TRU Waste Content Codes (CH-TRUCON) document describes the inventory of the U.S. Department of Energy (DOE) CH-TRU waste within the transportation parameters specified by the Contact-Handled Transuranic Waste Authorized Methods for Payload Control (CH-TRAMPAC). The CH-TRAMPAC defines the allowable payload for the Transuranic Package Transporter-II (TRUPACT-II) and HalfPACT packagings. This document is a catalog of TRUPACT-II and HalfPACT authorized contents and a description of the methods utilized to demonstrate compliance with the CH-TRAMPAC. A summary of currently approved content codes by site is presented in Table 1. The CH-TRAMPAC describes "shipping categories" that are assigned to each payload container. Multiple shipping categories may be assigned to a single content code. A summary of approved content codes and corresponding shipping categories is provided in Table 2, which consists of Tables 2A, 2B, and 2C. Table 2A provides a summary of approved content codes and corresponding shipping categories for the "General Case," which reflects the assumption of a 60-day shipping period as described in the CH-TRAMPAC and Appendix 3.4 of the CH-TRU Payload Appendices. For shipments to be completed within an approximately 1,000-mile radius, a shorter shipping period of 20 days is applicable as described in the CH-TRAMPAC and Appendix 3.5 of the CH-TRU Payload Appendices. For shipments to WIPP from Los Alamos National Laboratory (LANL), Nevada Test Site, and Rocky Flats Environmental Technology Site, a 20-day shipping period is applicable. Table 2B provides a summary of approved content codes and corresponding shipping categories for "Close-Proximity Shipments" (20-day shipping period). For shipments implementing the controls specified in the CH-TRAMPAC and Appendix 3.6 of the CH-TRU Payload Appendices, a 10-day shipping period is applicable. Table 2C provides a summary of approved content codes and corresponding shipping categories for "Controlled Shipments" (10-day shipping period).

Washington TRU Solutions LLC

2004-10-01T23:59:59.000Z

52

CH-TRU Waste Content Codes (CH-TRUCON)  

SciTech Connect (OSTI)

The CH-TRU Waste Content Codes (CH-TRUCON) document describes the inventory of the U.S. Department of Energy (DOE) CH-TRU waste within the transportation parameters specified by the Contact-Handled Transuranic Waste Authorized Methods for Payload Control (CH-TRAMPAC). The CH-TRAMPAC defines the allowable payload for the Transuranic Package Transporter-II (TRUPACT-II) and HalfPACT packagings. This document is a catalog of TRUPACT-II and HalfPACT authorized contents and a description of the methods utilized to demonstrate compliance with the CH-TRAMPAC. A summary of currently approved content codes by site is presented in Table 1. The CH-TRAMPAC describes "shipping categories" that are assigned to each payload container. Multiple shipping categories may be assigned to a single content code. A summary of approved content codes and corresponding shipping categories is provided in Table 2, which consists of Tables 2A, 2B, and 2C. Table 2A provides a summary of approved content codes and corresponding shipping categories for the "General Case," which reflects the assumption of a 60-day shipping period as described in the CH-TRAMPAC and Appendix 3.4 of the CH-TRU Payload Appendices. For shipments to be completed within an approximately 1,000-mile radius, a shorter shipping period of 20 days is applicable as described in the CH-TRAMPAC and Appendix 3.5 of the CH-TRU Payload Appendices. For shipments to WIPP from Los Alamos National Laboratory (LANL), Nevada Test Site, and Rocky Flats Environmental Technology Site, a 20-day shipping period is applicable. Table 2B provides a summary of approved content codes and corresponding shipping categories for "Close-Proximity Shipments" (20-day shipping period). For shipments implementing the controls specified in the CH-TRAMPAC and Appendix 3.6 of the CH-TRU Payload Appendices, a 10-day shipping period is applicable. Table 2C provides a summary of approved content codes and corresponding shipping categories for "Controlled Shipments" (10-day shipping period).

Washington TRU Solutions LLC

2005-03-15T23:59:59.000Z

53

CH-TRU Waste Content Codes (CH-TRUCON)  

SciTech Connect (OSTI)

The CH-TRU Waste Content Codes (CH-TRUCON) document describes the inventory of the U.S. Department of Energy (DOE) CH-TRU waste within the transportation parameters specified by the Contact-Handled Transuranic Waste Authorized Methods for Payload Control (CH-TRAMPAC). The CH-TRAMPAC defines the allowable payload for the Transuranic Package Transporter-II (TRUPACT-II) and HalfPACT packagings. This document is a catalog of TRUPACT-II and HalfPACT authorized contents and a description of the methods utilized to demonstrate compliance with the CH-TRAMPAC. A summary of currently approved content codes by site is presented in Table 1. The CH-TRAMPAC describes "shipping categories" that are assigned to each payload container. Multiple shipping categories may be assigned to a single content code. A summary of approved content codes and corresponding shipping categories is provided in Table 2, which consists of Tables 2A, 2B, and 2C. Table 2A provides a summary of approved content codes and corresponding shipping categories for the "General Case," which reflects the assumption of a 60-day shipping period as described in the CH-TRAMPAC and Appendix 3.4 of the CH-TRU Payload Appendices. For shipments to be completed within an approximately 1,000-mile radius, a shorter shipping period of 20 days is applicable as described in the CH-TRAMPAC and Appendix 3.5 of the CH-TRU Payload Appendices. For shipments to WIPP from Los Alamos National Laboratory (LANL), Nevada Test Site, and Rocky Flats Environmental Technology Site, a 20-day shipping period is applicable. Table 2B provides a summary of approved content codes and corresponding shipping categories for "Close-Proximity Shipments" (20-day shipping period). For shipments implementing the controls specified in the CH-TRAMPAC and Appendix 3.6 of the CH-TRU Payload Appendices, a 10-day shipping period is applicable. Table 2C provides a summary of approved content codes and corresponding shipping categories for "Controlled Shipments" (10-day shipping period).

Washington TRU Solutions LLC

2005-01-30T23:59:59.000Z

54

CH-TRU Waste Content Codes (CH-TRUCON)  

SciTech Connect (OSTI)

The CH-TRU Waste Content Codes (CH-TRUCON) document describes the inventory of the U.S. Department of Energy (DOE) CH-TRU waste within the transportation parameters specified by the Contact-Handled Transuranic Waste Authorized Methods for Payload Control (CH-TRAMPAC). The CH-TRAMPAC defines the allowable payload for the Transuranic Package Transporter-II (TRUPACT-II) and HalfPACT packagings. This document is a catalog of TRUPACT-II and HalfPACT authorized contents and a description of the methods utilized to demonstrate compliance with the CH-TRAMPAC. A summary of currently approved content codes by site is presented in Table 1. The CH-TRAMPAC describes "shipping categories" that are assigned to each payload container. Multiple shipping categories may be assigned to a single content code. A summary of approved content codes and corresponding shipping categories is provided in Table 2, which consists of Tables 2A, 2B, and 2C. Table 2A provides a summary of approved content codes and corresponding shipping categories for the "General Case," which reflects the assumption of a 60-day shipping period as described in the CH-TRAMPAC and Appendix 3.4 of the CH-TRU Payload Appendices. For shipments to be completed within an approximately 1,000-mile radius, a shorter shipping period of 20 days is applicable as described in the CH-TRAMPAC and Appendix 3.5 of the CH-TRU Payload Appendices. For shipments to WIPP from Los Alamos National Laboratory (LANL), Nevada Test Site, and Rocky Flats Environmental Technology Site, a 20-day shipping period is applicable. Table 2B provides a summary of approved content codes and corresponding shipping categories for "Close-Proximity Shipments" (20-day shipping period). For shipments implementing the controls specified in the CH-TRAMPAC and Appendix 3.6 of the CH-TRU Payload Appendices, a 10-day shipping period is applicable. Table 2C provides a summary of approved content codesand corresponding shipping categories for "Controlled Shipments" (10-day shipping period).

Washington TRU Solutions LLC

2005-01-15T23:59:59.000Z

55

CH-TRU Waste Content Codes (CH-TRUCON)  

SciTech Connect (OSTI)

The CH-TRU Waste Content Codes (CH-TRUCON) document describes the inventory of the U.S. Department of Energy (DOE) CH-TRU waste within the transportation parameters specified by the Contact-Handled Transuranic Waste Authorized Methods for Payload Control (CH-TRAMPAC). The CH-TRAMPAC defines the allowable payload for the Transuranic Package Transporter-II (TRUPACT-II) and HalfPACT packagings. This document is a catalog of TRUPACT-II and HalfPACT authorized contents and a description of the methods utilized to demonstrate compliance with the CH-TRAMPAC. A summary of currently approved content codes by site is presented in Table 1. The CH-TRAMPAC describes "shipping categories" that are assigned to each payload container. Multiple shipping categories may be assigned to a single content code. A summary of approved content codes and corresponding shipping categories is provided in Table 2, which consists of Tables 2A, 2B, and 2C. Table 2A provides a summary of approved content codes and corresponding shipping categories for the "General Case," which reflects the assumption of a 60-day shipping period as described in the CH-TRAMPAC and Appendix 3.4 of the CH-TRU Payload Appendices. For shipments to be completed within an approximately 1,000-mile radius, a shorter shipping period of 20 days is applicable as described in the CH-TRAMPAC and Appendix 3.5 of the CH-TRU Payload Appendices. For shipments to WIPP from Los Alamos National Laboratory (LANL), Nevada Test Site, and Rocky Flats Environmental Technology Site, a 20-day shipping period is applicable. Table 2B provides a summary of approved content codes and corresponding shipping categories for "Close-Proximity Shipments" (20-day shipping period). For shipments implementing the controls specified in the CH-TRAMPAC and Appendix 3.6 of the CH-TRU Payload Appendices, a 10-day shipping period is applicable. Table 2C provides a summary of approved content codes and corresponding shipping categories for "Controlled Shipments" (10-day shipping period).

Washington TRU Solutions LLC

2005-11-20T23:59:59.000Z

56

CH-TRU Waste Content Codes (CH-TRUCON)  

SciTech Connect (OSTI)

The CH-TRU Waste Content Codes (CH-TRUCON) document describes the inventory of the U.S. Department of Energy (DOE) CH-TRU waste within the transportation parameters specified by the Contact-Handled Transuranic Waste Authorized Methods for Payload Control (CH-TRAMPAC). The CH-TRAMPAC defines the allowable payload for the Transuranic Package Transporter-II (TRUPACT-II) and HalfPACT packagings. This document is a catalog of TRUPACT-II and HalfPACT authorized contents and a description of the methods utilized to demonstrate compliance with the CH-TRAMPAC. A summary of currently approved content codes by site is presented in Table 1. The CH-TRAMPAC describes "shipping categories" that are assigned to each payload container. Multiple shipping categories may be assigned to a single content code. A summary of approved content codes and corresponding shipping categories is provided in Table 2, which consists of Tables 2A, 2B, and 2C. Table 2A provides a summary of approved content codes and corresponding shipping categories for the "General Case," which reflects the assumption of a 60-day shipping period as described in the CH-TRAMPAC and Appendix 3.4 of the CH-TRU Payload Appendices. For shipments to be completed within an approximately 1,000-mile radius, a shorter shipping period of 20 days is applicable as described in the CH-TRAMPAC and Appendix 3.5 of the CH-TRU Payload Appendices. For shipments to WIPP from Los Alamos National Laboratory (LANL), Nevada Test Site, and Rocky Flats Environmental Technology Site, a 20-day shipping period is applicable. Table 2B provides a summary of approved content codes and corresponding shipping categories for "Close-Proximity Shipments" (20-day shipping period). For shipments implementing the controls specified in the CH-TRAMPAC and Appendix 3.6 of the CH-TRU Payload Appendices, a 10-day shipping period is applicable. Table 2C provides a summary of approved content codes and corresponding shipping categories for "Controlled Shipments" (10-day shipping period).

Washington TRU Solutions LLC

2006-08-15T23:59:59.000Z

57

CH-TRU Waste Content Codes (CH-TRUCON)  

SciTech Connect (OSTI)

The CH-TRU Waste Content Codes (CH-TRUCON) document describes the inventory of the U.S. Department of Energy (DOE) CH-TRU waste within the transportation parameters specified by the Contact-Handled Transuranic Waste Authorized Methods for Payload Control (CH-TRAMPAC). The CH-TRAMPAC defines the allowable payload for the Transuranic Package Transporter-II (TRUPACT-II) and HalfPACT packagings. This document is a catalog of TRUPACT-II and HalfPACT authorized contents and a description of the methods utilized to demonstrate compliance with the CH-TRAMPAC. A summary of currently approved content codes by site is presented in Table 1. The CH-TRAMPAC describes "shipping categories" that are assigned to each payload container. Multiple shipping categories may be assigned to a single content code. A summary of approved content codes and corresponding shipping categories is provided in Table 2, which consists of Tables 2A, 2B, and 2C. Table 2A provides a summary of approved content codes and corresponding shipping categories for the "General Case," which reflects the assumption of a 60-day shipping period as described in the CH-TRAMPAC and Appendix 3.4 of the CH-TRU Payload Appendices. For shipments to be completed within an approximately 1,000-mile radius, a shorter shipping period of 20 days is applicable as described in the CH-TRAMPAC and Appendix 3.5 of the CH-TRU Payload Appendices. For shipments to WIPP from Los Alamos National Laboratory (LANL), Nevada Test Site, and Rocky Flats Environmental Technology Site, a 20-day shipping period is applicable. Table 2B provides a summary of approved content codes and corresponding shipping categories for "Close-Proximity Shipments" (20-day shipping period). For shipments implementing the controls specified in the CH-TRAMPAC and Appendix 3.6 of the CH-TRU Payload Appendices, a 10-day shipping period is applicable. Table 2C provides a summary of approved content codes and corresponding shipping categories for "Controlled Shipments" (10-day shipping period).

Washington TRU Solutions LLC

2006-01-18T23:59:59.000Z

58

CH-TRU Waste Content Codes (CH-TRUCON)  

SciTech Connect (OSTI)

The CH-TRU Waste Content Codes (CH-TRUCON) document describes the inventory of the U.S. Department of Energy (DOE) CH-TRU waste within the transportation parameters specified by the Contact-Handled Transuranic Waste Authorized Methods for Payload Control (CH-TRAMPAC). The CH-TRAMPAC defines the allowable payload for the Transuranic Package Transporter-II (TRUPACT-II) and HalfPACT packagings. This document is a catalog of TRUPACT-II and HalfPACT authorized contents and a description of the methods utilized to demonstrate compliance with the CH-TRAMPAC. A summary of currently approved content codes by site is presented in Table 1. The CH-TRAMPAC describes "shipping categories" that are assigned to each payload container. Multiple shipping categories may be assigned to a single content code. A summary of approved content codes and corresponding shipping categories is provided in Table 2, which consists of Tables 2A, 2B, and 2C. Table 2A provides a summary of approved content codes and corresponding shipping categories for the "General Case," which reflects the assumption of a 60-day shipping period as described in the CH-TRAMPAC and Appendix 3.4 of the CH-TRU Payload Appendices. For shipments to be completed within an approximately 1,000-mile radius, a shorter shipping period of 20 days is applicable as described in the CH-TRAMPAC and Appendix 3.5 of the CH-TRU Payload Appendices. For shipments to WIPP from Los Alamos National Laboratory (LANL), Nevada Test Site, and Rocky Flats Environmental Technology Site, a 20-day shipping period is applicable. Table 2B provides a summary of approved content codes and corresponding shipping categories for "Close-Proximity Shipments" (20-day shipping period). For shipments implementing the controls specified in the CH-TRAMPAC and Appendix 3.6 of the CH-TRU Payload Appendices, a 10-day shipping period is applicable. Table 2C provides a summary of approved content codes and corresponding shipping categories for "Controlled Shipments" (10-day shipping period).

Washington TRU Solutions LLC

2005-05-01T23:59:59.000Z

59

CH-TRU Waste Content Codes (CH-TRUCON)  

SciTech Connect (OSTI)

The CH-TRU Waste Content Codes (CH-TRUCON) document describes the inventory of the U.S. Department of Energy (DOE) CH-TRU waste within the transportation parameters specified by the Contact-Handled Transuranic Waste Authorized Methods for Payload Control (CH-TRAMPAC). The CH-TRAMPAC defines the allowable payload for the Transuranic Package Transporter-II (TRUPACT-II) and HalfPACT packagings. This document is a catalog of TRUPACT-II and HalfPACT authorized contents and a description of the methods utilized to demonstrate compliance with the CH-TRAMPAC. A summary of currently approved content codes by site is presented in Table 1. The CH-TRAMPAC describes "shipping categories" that are assigned to each payload container. Multiple shipping categories may be assigned to a single content code. A summary of approved content codes and corresponding shipping categories is provided in Table 2, which consists of Tables 2A, 2B, and 2C. Table 2A provides a summary of approved content codes and corresponding shipping categories for the "General Case," which reflects the assumption of a 60-day shipping period as described in the CH-TRAMPAC and Appendix 3.4 of the CH-TRU Payload Appendices. For shipments to be completed within an approximately 1,000-mile radius, a shorter shipping period of 20 days is applicable as described in the CH-TRAMPAC and Appendix 3.5 of the CH-TRU Payload Appendices. For shipments to WIPP from Los Alamos National Laboratory (LANL), Nevada Test Site, and Rocky Flats Environmental Technology Site, a 20-day shipping period is applicable. Table 2B provides a summary of approved content codes and corresponding shipping categories for "Close-Proximity Shipments" (20-day shipping period). For shipments implementing the controls specified in the CH-TRAMPAC and Appendix 3.6 of the CH-TRU Payload Appendices, a 10-day shipping period is applicable. Table 2C provides a summary of approved content codes and corresponding shipping categories for "Controlled Shipments" (10-day shipping period).

Washington TRU Solutions LLC

2007-09-20T23:59:59.000Z

60

CH-TRU Waste Content Codes (CH-TRUCON)  

SciTech Connect (OSTI)

The CH-TRU Waste Content Codes (CH-TRUCON) document describes the inventory of the U.S. Department of Energy (DOE) CH-TRU waste within the transportation parameters specified by the Contact-Handled Transuranic Waste Authorized Methods for Payload Control (CH-TRAMPAC). The CH-TRAMPAC defines the allowable payload for the Transuranic Package Transporter-II (TRUPACT-II) and HalfPACT packagings. This document is a catalog of TRUPACT-II and HalfPACT authorized contents and a description of the methods utilized to demonstrate compliance with the CH-TRAMPAC. A summary of currently approved content codes by site is presented in Table 1. The CH-TRAMPAC describes "shipping categories" that are assigned to each payload container. Multiple shipping categories may be assigned to a single content code. A summary of approved content codes and corresponding shipping categories is provided in Table 2, which consists of Tables 2A, 2B, and 2C. Table 2A provides a summary of approved content codes and corresponding shipping categories for the "General Case," which reflects the assumption of a 60-day shipping period as described in the CH-TRAMPAC and Appendix 3.4 of the CH-TRU Payload Appendices. For shipments to be completed within an approximately 1,000-mile radius, a shorter shipping period of 20 days is applicable as described in the CH-TRAMPAC and Appendix 3.5 of the CH-TRU Payload Appendices. For shipments to WIPP from Los Alamos National Laboratory (LANL), Nevada Test Site, and Rocky Flats Environmental Technology Site, a 20-day shipping period is applicable. Table 2B provides a summary of approved content codes and corresponding shipping categories for "Close-Proximity Shipments" (20-day shipping period). For shipments implementing the controls specified in the CH-TRAMPAC and Appendix 3.6 of the CH-TRU Payload Appendices, a 10-day shipping period is applicable. Table 2C provides a summary of approved content codes and corresponding shipping categories for "Controlled Shipments" (10-day shipping period).

Washington TRU Solutions LLC

2005-12-15T23:59:59.000Z

Note: This page contains sample records for the topic "legacy tru waste" 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

CH-TRU Waste Content Codes (CH-TRUCON)  

SciTech Connect (OSTI)

The CH-TRU Waste Content Codes (CH-TRUCON) document describes the inventory of the U.S. Department of Energy (DOE) CH-TRU waste within the transportation parameters specified by the Contact-Handled Transuranic Waste Authorized Methods for Payload Control (CH-TRAMPAC). The CH-TRAMPAC defines the allowable payload for the Transuranic Package Transporter-II (TRUPACT-II) and HalfPACT packagings. This document is a catalog of TRUPACT-II and HalfPACT authorized contents and a description of the methods utilized to demonstrate compliance with the CH-TRAMPAC. A summary of currently approved content codes by site is presented in Table 1. The CH-TRAMPAC describes "shipping categories" that are assigned to each payload container. Multiple shipping categories may be assigned to a single content code. A summary of approved content codes and corresponding shipping categories is provided in Table 2, which consists of Tables 2A, 2B, and 2C. Table 2A provides a summary of approved content codes and corresponding shipping categories for the "General Case," which reflects the assumption of a 60-day shipping period as described in the CH-TRAMPAC and Appendix 3.4 of the CH-TRU Payload Appendices. For shipments to be completed within an approximately 1,000-mile radius, a shorter shipping period of 20 days is applicable as described in the CH-TRAMPAC and Appendix 3.5 of the CH-TRU Payload Appendices. For shipments to WIPP from Los Alamos National Laboratory (LANL), Nevada Test Site, and Rocky Flats Environmental Technology Site, a 20-day shipping period is applicable. Table 2B provides a summary of approved content codes and corresponding shipping categories for "Close-Proximity Shipments" (20-day shipping period). For shipments implementing the controls specified in the CH-TRAMPAC and Appendix 3.6 of the CH-TRU Payload Appendices, a 10-day shipping period is applicable. Table 2C provides a summary of approved content codes and corresponding shipping categories for "Controlled Shipments" (10-day shipping period).

Washington TRU Solutions LLC

2006-09-15T23:59:59.000Z

62

CH-TRU Waste Content Codes (CH-TRUCON)  

SciTech Connect (OSTI)

The CH-TRU Waste Content Codes (CH-TRUCON) document describes the inventory of the U.S. Department of Energy (DOE) CH-TRU waste within the transportation parameters specified by the Contact-Handled Transuranic Waste Authorized Methods for Payload Control (CH-TRAMPAC). The CH-TRAMPAC defines the allowable payload for the Transuranic Package Transporter-II (TRUPACT-II) and HalfPACT packagings. This document is a catalog of TRUPACT-II and HalfPACT authorized contents and a description of the methods utilized to demonstrate compliance with the CH-TRAMPAC. A summary of currently approved content codes by site is presented in Table 1. The CH-TRAMPAC describes "shipping categories" that are assigned to each payload container. Multiple shipping categories may be assigned to a single content code. A summary of approved content codes and corresponding shipping categories is provided in Table 2, which consists of Tables 2A, 2B, and 2C. Table 2A provides a summary of approved content codes and corresponding shipping categories for the "General Case," which reflects the assumption of a 60-day shipping period as described in the CH-TRAMPAC and Appendix 3.4 of the CH-TRU Payload Appendices. For shipments to be completed within an approximately 1,000-mile radius, a shorter shipping period of 20 days is applicable as described in the CH-TRAMPAC and Appendix 3.5 of the CH-TRU Payload Appendices. For shipments to WIPP from Los Alamos National Laboratory (LANL), Nevada Test Site, and Rocky Flats Environmental Technology Site, a 20-day shipping period is applicable. Table 2B provides a summary of approved content codes and corresponding shipping categories for "Close-Proximity Shipments" (20-day shipping period). For shipments implementing the controls specified in the CH-TRAMPAC and Appendix 3.6 of the CH-TRU Payload Appendices, a 10-day shipping period is applicable. Table 2C provides a summary of approved content codes and corresponding shipping categories for "Controlled Shipments" (10-day shipping period).

Washington TRU Solutions LLC

2005-06-20T23:59:59.000Z

63

CH-TRU Waste Content Codes (CH-TRUCON)  

SciTech Connect (OSTI)

The CH-TRU Waste Content Codes (CH-TRUCON) document describes the inventory of the U.S. Department of Energy (DOE) CH-TRU waste within the transportation parameters specified by the Contact-Handled Transuranic Waste Authorized Methods for Payload Control (CH-TRAMPAC). The CH-TRAMPAC defines the allowable payload for the Transuranic Package Transporter-II (TRUPACT-II) and HalfPACT packagings. This document is a catalog of TRUPACT-II and HalfPACT authorized contents and a description of the methods utilized to demonstrate compliance with the CH-TRAMPAC. A summary of currently approved content codes by site is presented in Table 1. The CH-TRAMPAC describes "shipping categories" that are assigned to each payload container. Multiple shipping categories may be assigned to a single content code. A summary of approved content codes and corresponding shipping categories is provided in Table 2, which consists of Tables 2A, 2B, and 2C. Table 2A provides a summary of approved content codes and corresponding shipping categories for the "General Case," which reflects the assumption of a 60-day shipping period as described in the CH-TRAMPAC and Appendix 3.4 of the CH-TRU Payload Appendices. For shipments to be completed within an approximately 1,000-mile radius, a shorter shipping period of 20 days is applicable as described in the CH-TRAMPAC and Appendix 3.5 of the CH-TRU Payload Appendices. For shipments to WIPP from Los Alamos National Laboratory (LANL), Nevada Test Site, and Rocky Flats Environmental Technology Site, a 20-day shipping period is applicable. Table 2B provides a summary of approved content codes and corresponding shipping categories for "Close-Proximity Shipments" (20-day shipping period). For shipments implementing the controls specified in the CH-TRAMPAC and Appendix 3.6 of the CH-TRU Payload Appendices, a 10-day shipping period is applicable. Table 2C provides a summary of approved content codes and corresponding shipping categories for "Controlled Shipments" (10-day shipping period).

Washington TRU Solutions LLC

2006-06-20T23:59:59.000Z

64

CH-TRU Waste Content Codes (CH-TRUCON)  

SciTech Connect (OSTI)

The CH-TRU Waste Content Codes (CH-TRUCON) document describes the inventory of the U.S. Department of Energy (DOE) CH-TRU waste within the transportation parameters specified by the Contact-Handled Transuranic Waste Authorized Methods for Payload Control (CH-TRAMPAC). The CH-TRAMPAC defines the allowable payload for the Transuranic Package Transporter-II (TRUPACT-II) and HalfPACT packagings. This document is a catalog of TRUPACT-II and HalfPACT authorized contents and a description of the methods utilized to demonstrate compliance with the CH-TRAMPAC. A summary of currently approved content codes by site is presented in Table 1. The CH-TRAMPAC describes "shipping categories" that are assigned to each payload container. Multiple shipping categories may be assigned to a single content code. A summary of approved content codes and corresponding shipping categories is provided in Table 2, which consists of Tables 2A, 2B, and 2C. Table 2A provides a summary of approved content codes and corresponding shipping categories for the "General Case," which reflects the assumption of a 60-day shipping period as described in the CH-TRAMPAC and Appendix 3.4 of the CH-TRU Payload Appendices. For shipments to be completed within an approximately 1,000-mile radius, a shorter shipping period of 20 days is applicable as described in the CH-TRAMPAC and Appendix 3.5 of the CH-TRU Payload Appendices. For shipments to WIPP from Los Alamos National Laboratory (LANL), Nevada Test Site, and Rocky Flats Environmental Technology Site, a 20-day shipping period is applicable. Table 2B provides a summary of approved content codes and corresponding shipping categories for "Close-Proximity Shipments" (20-day shipping period). For shipments implementing the controls specified in the CH-TRAMPAC and Appendix 3.6 of the CH-TRU Payload Appendices, a 10-day shipping period is applicable. Table 2C provides a summary of approved content codes and corresponding shipping categories for "Controlled Shipments" (10-day shipping period).

Washington TRU Solutions LLC

2007-06-15T23:59:59.000Z

65

CH-TRU Waste Content Codes (CH-TRUCON)  

SciTech Connect (OSTI)

The CH-TRU Waste Content Codes (CH-TRUCON) document describes the inventory of the U.S. Department of Energy (DOE) CH-TRU waste within the transportation parameters specified by the Contact-Handled Transuranic Waste Authorized Methods for Payload Control (CH-TRAMPAC). The CH-TRAMPAC defines the allowable payload for the Transuranic Package Transporter-II (TRUPACT-II) and HalfPACT packagings. This document is a catalog of TRUPACT-II and HalfPACT authorized contents and a description of the methods utilized to demonstrate compliance with the CH-TRAMPAC. A summary of currently approved content codes by site is presented in Table 1. The CH-TRAMPAC describes "shipping categories" that are assigned to each payload container. Multiple shipping categories may be assigned to a single content code. A summary of approved content codes and corresponding shipping categories is provided in Table 2, which consists of Tables 2A, 2B, and 2C. Table 2A provides a summary of approved content codes and corresponding shipping categories for the "General Case," which reflects the assumption of a 60-day shipping period as described in the CH-TRAMPAC and Appendix 3.4 of the CH-TRU Payload Appendices. For shipments to be completed within an approximately 1,000-mile radius, a shorter shipping period of 20 days is applicable as described in the CH-TRAMPAC and Appendix 3.5 of the CH-TRU Payload Appendices. For shipments to WIPP from Los Alamos National Laboratory (LANL), Nevada Test Site, and Rocky Flats Environmental Technology Site, a 20-day shipping period is applicable. Table 2B provides a summary of approved content codes and corresponding shipping categories for "Close-Proximity Shipments" (20-day shipping period). For shipments implementing the controls specified in the CH-TRAMPAC and Appendix 3.6 of the CH-TRU Payload Appendices, a 10-day shipping period is applicable. Table 2C provides a summary of approved content codes and corresponding shipping categories for "Controlled Shipments" (10-day shipping period).

Washington TRU Solutions LLC

2006-12-20T23:59:59.000Z

66

CH-TRU Waste Content Codes (CH-TRUCON)  

SciTech Connect (OSTI)

The CH-TRU Waste Content Codes (CH-TRUCON) document describes the inventory of the U.S. Department of Energy (DOE) CH-TRU waste within the transportation parameters specified by the Contact-Handled Transuranic Waste Authorized Methods for Payload Control (CH-TRAMPAC). The CH-TRAMPAC defines the allowable payload for the Transuranic Package Transporter-II (TRUPACT-II) and HalfPACT packagings. This document is a catalog of TRUPACT-II and HalfPACT authorized contents and a description of the methods utilized to demonstrate compliance with the CH-TRAMPAC. A summary of currently approved content codes by site is presented in Table 1. The CH-TRAMPAC describes "shipping categories" that are assigned to each payload container. Multiple shipping categories may be assigned to a single content code. A summary of approved content codes and corresponding shipping categories is provided in Table 2, which consists of Tables 2A, 2B, and 2C. Table 2A provides a summary of approved content codes and corresponding shipping categories for the "General Case," which reflects the assumption of a 60-day shipping period as described in the CH-TRAMPAC and Appendix 3.4 of the CH-TRU Payload Appendices. For shipments to be completed within an approximately 1,000-mile radius, a shorter shipping period of 20 days is applicable as described in the CH-TRAMPAC and Appendix 3.5 of the CH-TRU Payload Appendices. For shipments to WIPP from Los Alamos National Laboratory (LANL), Nevada Test Site, and Rocky Flats Environmental Technology Site, a 20-day shipping period is applicable. Table 2B provides a summary of approved content codes and corresponding shipping categories for "Close-Proximity Shipments" (20-day shipping period). For shipments implementing the controls specified in the CH-TRAMPAC and Appendix 3.6 of the CH-TRU Payload Appendices, a 10-day shipping period is applicable. Table 2C provides a summary of approved content codes and corresponding shipping categories for "Controlled Shipments" (10-day shipping period).

Washington TRU Solutions LLC

2007-08-15T23:59:59.000Z

67

CH-TRU Waste Content Codes (CH-TRUCON)  

SciTech Connect (OSTI)

The CH-TRU Waste Content Codes (CH-TRUCON) document describes the inventory of the U.S. Department of Energy (DOE) CH-TRU waste within the transportation parameters specified by the Contact-Handled Transuranic Waste Authorized Methods for Payload Control (CH-TRAMPAC). The CH-TRAMPAC defines the allowable payload for the Transuranic Package Transporter-II (TRUPACT-II) and HalfPACT packagings. This document is a catalog of TRUPACT-II and HalfPACT authorized contents and a description of the methods utilized to demonstrate compliance with the CH-TRAMPAC. A summary of currently approved content codes by site is presented in Table 1. The CH-TRAMPAC describes "shipping categories" that are assigned to each payload container. Multiple shipping categories may be assigned to a single content code. A summary of approved content codes and corresponding shipping categories is provided in Table 2, which consists of Tables 2A, 2B, and 2C. Table 2A provides a summary of approved content codes and corresponding shipping categories for the "General Case," which reflects the assumption of a 60-day shipping period as described in the CH-TRAMPAC and Appendix 3.4 of the CH-TRU Payload Appendices. For shipments to be completed within an approximately 1,000-mile radius, a shorter shipping period of 20 days is applicable as described in the CH-TRAMPAC and Appendix 3.5 of the CH-TRU Payload Appendices. For shipments to WIPP from Los Alamos National Laboratory (LANL), Nevada Test Site, and Rocky Flats Environmental Technology Site, a 20-day shipping period is applicable. Table 2B provides a summary of approved content codes and corresponding shipping categories for "Close-Proximity Shipments" (20-day shipping period). For shipments implementing the controls specified in the CH-TRAMPAC and Appendix 3.6 of the CH-TRU Payload Appendices, a 10-day shipping period is applicable. Table 2C provides a summary of approved content codes and corresponding shipping categories for "Controlled Shipments" (10-day shipping period).

Washington TRU Solutions LLC

2005-08-15T23:59:59.000Z

68

CH-TRU Waste Content Codes (CH-TRUCON)  

SciTech Connect (OSTI)

The CH-TRU Waste Content Codes (CH-TRUCON) document describes the inventory of the U.S. Department of Energy (DOE) CH-TRU waste within the transportation parameters specified by the Contact-Handled Transuranic Waste Authorized Methods for Payload Control (CH-TRAMPAC). The CH-TRAMPAC defines the allowable payload for the Transuranic Package Transporter-II (TRUPACT-II) and HalfPACT packagings. This document is a catalog of TRUPACT-II and HalfPACT authorized contents and a description of the methods utilized to demonstrate compliance with the CH-TRAMPAC. A summary of currently approved content codes by site is presented in Table 1. The CH-TRAMPAC describes "shipping categories" that are assigned to each payload container. Multiple shipping categories may be assigned to a single content code. A summary of approved content codes and corresponding shipping categories is provided in Table 2, which consists of Tables 2A, 2B, and 2C. Table 2A provides a summary of approved content codes and corresponding shipping categories for the "General Case," which reflects the assumption of a 60-day shipping period as described in the CH-TRAMPAC and Appendix 3.4 of the CH-TRU Payload Appendices. For shipments to be completed within an approximately 1,000-mile radius, a shorter shipping period of 20 days is applicable as described in the CH-TRAMPAC and Appendix 3.5 of the CH-TRU Payload Appendices. For shipments to WIPP from Los Alamos National Laboratory (LANL), Nevada Test Site, and Rocky Flats Environmental Technology Site, a 20-day shipping period is applicable. Table 2B provides a summary of approved content codes and corresponding shipping categories for "Close-Proximity Shipments" (20-day shipping period). For shipments implementing the controls specified in the CH-TRAMPAC and Appendix 3.6 of the CH-TRU Payload Appendices, a 10-day shipping period is applicable. Table 2C provides a summary of approved content codes and corresponding shipping categories for "Controlled Shipments" (10-day shipping period).

Washington TRU Solutions LLC

2007-02-15T23:59:59.000Z

69

CH-TRU Waste Content Codes (CH TRUCON)  

SciTech Connect (OSTI)

The CH-TRU Waste Content Codes (CH-TRUCON) document describes the inventory of the U.S. Department of Energy (DOE) CH-TRU waste within the transportation parameters specified by the Contact-Handled Transuranic Waste Authorized Methods for Payload Control (CH-TRAMPAC). The CH-TRAMPAC defines the allowable payload for the Transuranic Package Transporter-II (TRUPACT-II) and HalfPACT packagings. This document is a catalog of TRUPACT-II and HalfPACT authorized contents and a description of the methods utilized to demonstrate compliance with the CH-TRAMPAC. A summary of currently approved content codes by site is presented in Table 1. The CH-TRAMPAC describes "shipping categories" that are assigned to each payload container. Multiple shipping categories may be assigned to a single content code. A summary of approved content codes and corresponding shipping categories is provided in Table 2, which consists of Tables 2A, 2B, and 2C. Table 2A provides a summary of approved content codes and corresponding shipping categories for the "General Case," which reflects the assumption of a 60-day shipping period as described in the CH-TRAMPAC and Appendix 3.4 of the CH-TRU Payload Appendices. For shipments to be completed within an approximately 1,000-mile radius, a shorter shipping period of 20 days is applicable as described in the CH-TRAMPAC and Appendix 3.5 of the CH-TRU Payload Appendices. For shipments to WIPP from Los Alamos National Laboratory (LANL), Nevada Test Site, and Rocky Flats Environmental Technology Site, a 20-day shipping period is applicable. Table 2B provides a summary of approved content codes and corresponding shipping categories for "Close-Proximity Shipments" (20-day shipping period). For shipments implementing the controls specified in the CH-TRAMPAC and Appendix 3.6 of the CH-TRU Payload Appendices, a 10-day shipping period is applicable. Table 2C provides a summary of approved content codes and corresponding shipping categories for "Controlled Shipments" (10-day shipping period).

Washington TRU Solutions LLC

2004-12-01T23:59:59.000Z

70

HANFORD SITE RIVER PROTECTION PROJECT (RPP) TRANSURANIC (TRU) TANK WASTE IDENTIFICATION & PLANNING FOR REVRIEVAL TREATMENT & EVENTUAL DISPOSAL AT WIPP  

SciTech Connect (OSTI)

The CH2M HILL Manford Group, Inc. (CHG) conducts business to achieve the goals of the Office of River Protection (ORP) at Hanford. As an employee owned company, CHG employees have a strong motivation to develop innovative solutions to enhance project and company performance while ensuring protection of human health and the environment. CHG is responsible to manage and perform work required to safely store, enhance readiness for waste feed delivery, and prepare for treated waste receipts for the approximately 53 million gallons of legacy mixed radioactive waste currently at the Hanford Site tank farms. Safety and environmental awareness is integrated into all activities and work is accomplished in a manner that achieves high levels of quality while protecting the environment and the safety and health of workers and the public. This paper focuses on the innovative strategy to identify, retrieve, treat, and dispose of Hanford Transuranic (TRU) tank waste at the Waste Isolation Pilot Plant (WIPP).

KRISTOFZSKI, J.G.; TEDESCHI, R.; JOHNSON, M.E.; JENNINGS, M

2006-01-18T23:59:59.000Z

71

Waste Isolation Pilot Plant simulated RH TRU waste experiments: Data and interpretation pilot  

SciTech Connect (OSTI)

The simulated, i.e., nonradioactive remote-handled transuranic waste (RH TRU) experiments being conducted underground in the Waste Isolation Pilot Plant (WIPP) were emplaced in mid-1986 and have been in heated test operation since 9/23/86. These experiments involve the in situ, waste package performance testing of eight full-size, reference RH TRU containers emplaced in horizontal, unlined test holes in the rock salt ribs (walls) of WIPP Room T. All of the test containers have internal electrical heaters; four of the test emplacements were filled with bentonite and silica sand backfill materials. We designed test conditions to be ``near-reference`` with respect to anticipated thermal outputs of RH TRU canisters and their geometrical spacing or layout in WIPP repository rooms, with RH TRU waste reference conditions current as of the start date of this test program. We also conducted some thermal overtest evaluations. This paper provides a: detailed test overview; comprehensive data update for the first 5 years of test operations; summary of experiment observations; initial data interpretations; and, several status; experimental objectives -- how these tests support WIPP TRU waste acceptance, performance assessment studies, underground operations, and the overall WIPP mission; and, in situ performance evaluations of RH TRU waste package materials plus design details and options. We provide instrument data and results for in situ waste container and borehole temperatures, pressures exerted on test containers through the backfill materials, and vertical and horizontal borehole-closure measurements and rates. The effects of heat on borehole closure, fracturing, and near-field materials (metals, backfills, rock salt, and intruding brine) interactions were closely monitored and are summarized, as are assorted test observations. Predictive 3-dimensional thermal and structural modeling studies of borehole and room closures and temperature fields were also performed.

Molecke, M.A.; Argueello, G.J.; Beraun, R.

1993-04-01T23:59:59.000Z

72

Remote Handled TRU Waste Status and Activities and Challenges at the Hanford Site  

SciTech Connect (OSTI)

A significant portion of the Department of Energy's forecast volume of remote-handled (RH) transuranic (TRU) waste will originate from the Hanford Site. The forecasted Hanford RH-TRU waste volume of over 2000 cubic meters may constitute over one-third of the forecast inventory of RH-TRU destined for disposal at the Waste Isolation Pilot Plant (WIPP). To date, the Hanford TRU waste program has focused on the retrieval, treatment and certification of the contact-handled transuranic (CH-TRU) wastes. This near-term focus on CH-TRU is consistent with the National TRU Program plans and capabilities. The first shipment of CH-TRU waste from Hanford to the WIPP is scheduled early in Calendar Year 2000. Shipments of RH-TRU from Hanford to the WIPP are scheduled to begin in Fiscal Year 2006 per the National TRU Waste Management Plan. This schedule has been incorporated into milestones within the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement). These Tri-Party milestones (designated the ''M-91'' series of milestones) relate to development of project management plans, completion of design efforts, construction and contracting schedules, and initiation of process operations. The milestone allows for modification of an existing facility, construction of a new facility, and/or commercial contracting to provide the capabilities for processing and certification of RH-TRU wastes for disposal at the WIPP. The development of a Project Management Plan (PMP) for TRU waste is the first significant step in the development of a program for disposal of Hanford's RH-TRU waste. This PMP will address the path forward for disposition of waste streams that cannot be prepared for disposal in the Hanford Waste Receiving and Processing facility (a contact-handled, small container facility) or other Site facilities. The PMP development effort has been initiated, and the PMP will be provided to the regulators for their approval by June 30, 2000. This plan will detail the path forward for the Hanford RH-TRU program.

MCKENNEY, D.E.

2000-02-01T23:59:59.000Z

73

ABSORBING WIPP BRINES: A TRU WASTE DISPOSAL STRATEGY  

SciTech Connect (OSTI)

Los Alamos National Laboratory (LANL) has completed experiments involving 15 each, 250- liter experimental test containers of transuranic (TRU) heterogeneous waste immersed in two types of brine similar to those found in the underground portion of the Waste Isolation Pilot Plant (WIPP). To dispose of the waste without removing the brine from the test containers, LANL added commercially available cross-linked polyacrylate granules to absorb the 190 liters of brine in each container, making the waste compliant for shipping to the WIPP in a Standard Waste Box (SWB). Prior to performing the absorption, LANL and the manufacturer of the absorbent conducted laboratory and field tests to determine the ratio of absorbent to brine that would fully absorb the liquid. Bench scale tests indicated a ratio of 10 parts Castile brine to one part absorbent and 6.25 parts Brine A to one part absorbent. The minimum ratio of absorbent to brine was sought because headspace in the containers was limited. However, full scale testing revealed that the ratio should be adjusted to be about 15% richer in absorbent. Additional testing showed that the absorbent would not apply more than 13.8 kPa pressure on the walls of the vessel and that the absorbent would still function normally at that pressure and would not degrade in the approximately 5e-4 Sv/hr radioactive field produced by the waste. Heat generation from the absorption was minimal. The in situ absorption created a single waste stream of 8 SWBs whereas the least complicated alternate method of disposal would have yielded at least an additional 2600 liters of mixed low level liquid waste plus about two cubic meters of mixed low level solid waste, and would have resulted in higher risk of radiation exposure to workers. The in situ absorption saved $311k in a combination of waste treatment, disposal, material and personnel costs compared to the least expensive alternative and $984k compared to the original plan.

Yeamans, D. R.; Wrights, R. S.

2002-02-25T23:59:59.000Z

74

Absorbing WIPP brines : a TRU waste disposal strategy.  

SciTech Connect (OSTI)

Los Alamos National Laboratory (LANL) has completed experiments involving 15 each, 250-liter experimental test containers of transuranic (TRU) heterogeneous waste immersed in two types of brine similar to those found in the underground portion of the Waste Isolation Pilot Plant (WIPP). To dispose of the waste without removing the brine from the test containers, LANL added commercially available cross-linked polyacrylate granules to absorb the 190 liters of brine in each container, making the waste compliant for shipping to the WlPP in a Standard Waste Box (SWB). Prior to performing the absorption, LANL and the manufacturer of the absorbent conducted laboratory and field tests to determine the ratio of absorbent to brine that would fully absorb the liquid. Bench scale tests indicated a ratio of 10 parts Castile brine to one part absorbent and 6.25 parts Brine A to one part absorbent. The minimum ratio of absorbent to brine was sought because headspace in the containers was limited. However, full scale testing revealed that the ratio should be adjusted to be about 15% richer in absorbent. Additional testing showed that the absorbent would not apply more than 13.8 kPa pressure on the walls of the vessel and that the absorbent would still function normally at that pressure and would not degrade in the approximately 5e-4 Sv/hr radioactive field produced by the waste. Heat generation from the absorption was minimal. The in situ absorption created a single waste stream of 8 SWBs whereas the least complicated alternate method of disposal would have yielded at least an additional 2600 liters of mixed low level liquid waste plus about two cubic meters of mixed low level solid waste, and would have resulted in higher risk of radiation exposure to workers. The in situ absorption saved $3 1 lk in a combination of waste treatment, disposal, material and personnel costs compared to the least expensive alternative and $984k compared to the original plan.

Yeamans, D. R. (David R.); Wright, R. (Robert)

2002-01-01T23:59:59.000Z

75

Waste Isolation Pilot Plant TruDock crane system analysis  

SciTech Connect (OSTI)

The WIPP TruDock crane system located in the Waste Handling Building was identified in the WIPP Safety Analysis Report (SAR), November 1995, as a potential accident concern due to failures which could result in a dropped load. The objective of this analysis is to evaluate the frequency of failure of the TruDock crane system resulting in a dropped load and subsequent loss of primary containment, i.e. drum failure. The frequency of dropped loads was estimated to be 9.81E-03/year or approximately one every 102 years (or, for the 25% contingency, 7.36E-03/year or approximately one every 136 years). The dominant accident contributor was the failure of the cable/hook assemblies, based on failure data obtained from NUREG-0612, as analyzed by PLG, Inc. The WIPP crane system undergoes a rigorous test and maintenance program, crane operation is discontinued following any abnormality, and the crane operator and load spotter are required to be trained in safe crane operation, therefore it is felt that the WIPP crane performance will exceed the data presented in NUREG-0612 and the estimated failure frequency is felt to be conservative.

Morris, B.C. [Westinghouse Electric Corp., Pittsburgh, PA (United States); Carter, M. [Westinghouse Electric Corp., Carlsbad, NM (United States). Waste Isolation Div.

1996-10-01T23:59:59.000Z

76

Proposed technologies for use in the National TRU waste system optimization.  

SciTech Connect (OSTI)

Technology deployments planned for the National TRU Waste System Optimization Project are aimed at using appropriate cost-effective technologies to drive the national TRU waste system to a performance-driven certification system that is based on administrative and operational requirements with a sound safety and/or technical basis. Appropriate technology deployments are determined by first identifying technology needs; selecting promising technologies; and overseeing the development of operating procedures, personnel training, testing, and startup and operations to ensure that the resulting operations function correctly and meet the TRU waste certification requirements.

Moody, D. C. (David C.); Lott, S. A. (Sheila A.); Behrens, R. G. (Robert G.); Basabilvazo, George T. (George Taylor),; Countiss, S. (Sue)

2002-01-01T23:59:59.000Z

77

Transuranic (Tru) waste volume reduction operations at a plutonium facility  

SciTech Connect (OSTI)

Programmatic operations at the Los Alamos National Laboratory Plutonium Facility (TA 55) involve working with various amounts of plutonium and other highly toxic, alpha-emitting materials. The spread of radiological contamination on surfaces, airborne contamination, and excursions of contaminants into the operator's breathing zone are prevented through use of a variety of gloveboxes (the glovebox, coupled with an adequate negative pressure gradient, provides primary confinement). Size-reduction operations on glovebox equipment are a common activity when a process has been discontinued and the room is being modified to support a new customer. The Actin ide Processing Group at TA-55 uses one-meter-long glass columns to process plutonium. Disposal of used columns is a challenge, since they must be size-reduced to get them out of the glovebox. The task is a high-risk operation because the glass shards that are generated can puncture the bag-out bags, leather protectors, glovebox gloves, and the worker's skin when completing the task. One of the Lessons Learned from these operations is that Laboratory management should critically evaluate each hazard and provide more effective measures to prevent personnel injury. A bag made of puncture-resistant material was one of these enhanced controls. We have investigated the effectiveness of these bags and have found that they safely and effectively permit glass objects to be reduced to small pieces with a plastic or rubber mallet; the waste can then be easily poured into a container for removal from the glove box as non-compactable transuranic (TRU) waste. This size-reduction operation reduces solid TRU waste generation by almost 2% times. Replacing one-time-use bag-out bags with multiple-use glass crushing bags also contributes to reducing generated waste. In addition, significant costs from contamination, cleanup, and preparation of incident documentation are avoided. This effort contributes to the Los Alamos National Laboratory Continuous Improvement Program by improving the efficiency, cost-effectiveness, and formality of glovebox operations. In this report, the technical issues, associated with implementing this process improvement are addressed, the results discussed, effectiveness of Lessons Learned evaluated, and waste savings presented.

Cournoyer, Michael E [Los Alamos National Laboratory; Nixon, Archie E [Los Alamos National Laboratory; Dodge, Robert L [Los Alamos National Laboratory; Fife, Keith W [Los Alamos National Laboratory; Sandoval, Arnold M [Los Alamos National Laboratory; Garcia, Vincent E [Los Alamos National Laboratory

2010-01-01T23:59:59.000Z

78

Development of Infrared Welder for Sealing of Polyethylene TRU-Waste Containers  

SciTech Connect (OSTI)

Engineers at the Savannah River Technology Center have successfully performed infrared welding of High Density Polyethylene test specimens to prove the feasibility of using the infrared welding process in the HANDSS-55-TRU-Waste Repackaging Module.

Milling, R.B.

1999-06-08T23:59:59.000Z

79

MANAGING THE RETRIEVAL RISK OF BURIED TRANSURANIC (TRU) WASTE WITH UNIQUE CHARACTERISTICS  

SciTech Connect (OSTI)

United States-Department of Energy (DOE) sites that store transuranic (TRU) waste are almost certain to encounter waste packages with characteristics that are so unique as to warrant special precautions for retrieval. At the Hanford Site, a subgroup of stored TRU waste (12 drums) had special considerations due to the radioactive source content of plutonium oxide (PuO{sub 2}), and the potential for high heat generation, pressurization, criticality, and high radiation. These characteristics bear on the approach to safely retrieve, overpack, vent, store, and transport the waste package. Because of the potential risk to personnel, contingency planning for unexpected conditions played an effective role in work planning and in preparing workers for the field inspection activity. As a result, the integrity inspections successfully confirmed waste package configuration and waste confinement without experiencing any perturbations due to unanticipated packaging conditions. This paper discusses the engineering and field approach to managing the risk of retrieving TRU waste with unique characteristics.

WOJTASEK, R.D.; GADD, R.R.; GREENWELL, R.D.

2006-01-19T23:59:59.000Z

80

MANAGEING THE RETRIEVAL RISK OF BURIED TRANSURANIC (TRU) WASTE WITH UNIQUE CHARACTERISTICS  

SciTech Connect (OSTI)

United States-Department of Energy (DOE) sites that store transuranic (TRU) waste are almost certain to encounter waste packages with characteristics that are so unique as to warrant special precautions for retrieval. At the Hanford Site, a subgroup of stored TRU waste (12 drums) had special considerations due to the radioactive source content of plutonium oxide (PuO{sub 2}), and the potential for high heat generation, pressurization, criticality, and high radiation. These characteristics bear on the approach to safely retrieve, overpack, vent, store, and transport the waste package. Because of the potential risk to personnel, contingency planning for unexpected conditions played an effective roll in work planning and in preparing workers for the field inspection activity. As a result, the integrity inspections successfully confirmed waste package configuration and waste confinement without experiencing any perturbations due to unanticipated packaging conditions. This paper discusses the engineering and field approach to managing the risk of retrieving TRU waste with unique characteristics.

WOJTASEK, R.D.; GREENWELL, R.D.

2005-11-17T23:59:59.000Z

Note: This page contains sample records for the topic "legacy tru waste" 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

The effect of vibration on alpha radiolysis of transuranic (TRU) waste  

SciTech Connect (OSTI)

This paper reports on previously unpublished scoping work related to the potential for vibration to redistribute radionuclides on transuranic (TRU) waste. If this were to happen, the amount of gases generated, including hydrogen, could be increased above the undisturbed levels. This could be an important consideration for transport of TRU wastes either at DOE sites or from them to a future repository, e.g., the Waste Isolation Pilot Plant (WIPP). These preliminary data on drums of real waste seem to suggest that radionuclide redistribution does not occur. However improvements in the experimental methodology are suggested to enhance safety of future experiments on real wastes as well as to provide more rigorous data.

Zerwekh, A.; Kosiewicz, S. (Los Alamos National Lab., NM (United States)); Warren, J. (NFT, Inc., Lakewood, CO (United States))

1993-01-01T23:59:59.000Z

82

The effect of vibration on alpha radiolysis of transuranic (TRU) waste  

SciTech Connect (OSTI)

This paper reports on previously unpublished scoping work related to the potential for vibration to redistribute radionuclides on transuranic (TRU) waste. If this were to happen, the amount of gases generated, including hydrogen, could be increased above the undisturbed levels. This could be an important consideration for transport of TRU wastes either at DOE sites or from them to a future repository, e.g., the Waste Isolation Pilot Plant (WIPP). These preliminary data on drums of real waste seem to suggest that radionuclide redistribution does not occur. However improvements in the experimental methodology are suggested to enhance safety of future experiments on real wastes as well as to provide more rigorous data.

Zerwekh, A.; Kosiewicz, S. [Los Alamos National Lab., NM (United States); Warren, J. [NFT, Inc., Lakewood, CO (United States)

1993-02-01T23:59:59.000Z

83

Comparative assessment of TRU waste forms and processes. Volume I. Waste form and process evaluations  

SciTech Connect (OSTI)

This study provides an assesses seven waste forms and eight processes for immobilizing transuranic (TRU) wastes. The waste forms considered are cast cement, cold-pressed cement, FUETAP (formed under elevated temperature and pressure) cement, borosilicate glass, aluminosilicate glass, basalt glass-ceramic, and cold-pressed and sintered silicate ceramic. The waste-immobilization processes considered are in-can glass melting, joule-heated glass melting, glass marble forming, cement casting, cement cold-pressing, FUETAP cement processing, ceramic cold-pressing and sintering, basalt glass-ceramic processing. Properties considered included gas generation, chemical durability, mechanical strength, thermal stability, and radiation stability. The ceramic products demonstrated the best properties, except for plutonium release during leaching. The glass and ceramic products had similar properties. The cement products generally had poorer properties than the other forms, except for plutonium release during leaching. Calculations of the Pu release indicated that the waste forms met the proposed NRC release rate limit of 1 part in 10/sup 5/ per year in most test conditions. The cast-cement process had the lowest processing cost, followed closely by the cold-pressed and FUETAP cement processes. Joule-heated glass melting had the lower cost of the glass processes. In-can melting in a high-quality canister had the highest cost, and cold-pressed and sintered ceramic the second highest. Labor and canister costs for in-can melting were identified. The major contributor to costs of disposing of TRU wastes in a defense waste repository is waste processing costs. Repository costs could become the dominant cost for disposing of TRU wastes in a commercial repository. It is recommended that cast and FUETAP cement and borosilicate glass waste-form systems be considered. 13 figures, 16 tables.

Ross, W.A.; Lokken, R.O.; May, R.P.; Roberts, F.P.; Timmerman, C.L.; Treat, R.L.; Westsik, J.H. Jr.

1982-09-01T23:59:59.000Z

84

Quality assurance (QA) plan for the transportation and receipt of transuranic (TRU) waste  

SciTech Connect (OSTI)

The Department of Energy (DOE) Albuquerque Operations (AL) Office of Projects and Energy Programs has been assigned the responsibility for administration of the disposal of Contact-Handled (CH) Transuranic (TRU) contaminated material (waste) from generator/storage sites of the United States defense programs that are operated by the DOE. This responsibility encompasses all activities associated with the certification of TRU waste and the transportation, receipt and disposal of that waste at the Waste Isolation Pilot Plant (WIPP). The WIPP is located near Carlsbad, New Mexico and is being developed under the management of the DOE WIPP Project Office (WPO). The DOE/WPO is a branch of the DOE/AL and has been delegated overall responsibility for all aspects of the WIPP program. This report describes the quality assurance plan for the TRU waste transportation and receipt of waste.

Not Available

1990-02-01T23:59:59.000Z

85

PROJECT STRATEGY FOR THE REMEDIATION AND DISPOSITION OF LEGACY TRANSURANIC WASTE AT THE SAVANNAH RIVER SITE, South Carolina, USA  

SciTech Connect (OSTI)

This paper discusses the Savannah River Site Accelerated Transuranic (TRU) Waste Project that was initiated in April of 2009 to accelerate the disposition of remaining legacy transuranic waste at the site. An overview of the project execution strategy that was implemented is discussed along with the lessons learned, challenges and improvements to date associated with waste characterization, facility modifications, startup planning, and remediation activities. The legacy waste was generated from approximately 1970 through 1990 and originated both on site as well as at multiple US Department of Energy sites. Approximately two thirds of the waste was previously dispositioned from 2006 to 2008, with the remaining one third being the more hazardous waste due to its activity (curie content) and the plutonium isotope Pu-238 quantities in the waste. The project strategy is a phased approach beginning with the lower activity waste in existing facilities while upgrades are made to support remediation of the higher activity waste. Five waste remediation process lines will be used to support the full remediation efforts which involve receipt of the legacy waste container, removal of prohibited items, venting of containers, and resizing of contents to fit into current approved waste shipping containers. Modifications have been minimized to the extent possible to meet the accelerated goals and involve limited upgrades to address life safety requirements, radiological containment needs, and handling equipment for the larger waste containers. Upgrades are also in progress for implementation of the TRUPACT III for the shipment of Standard Large Boxes to the Waste Isolation Pilot Plant, the US TRU waste repository. The use of this larger shipping container is necessary for approximately 20% of the waste by volume due to limited size reduction capability. To date, approximately 25% of the waste has been dispositioned, and several improvements have been made to the overall processing plan as well as facility processing rates. These lessons learned, challenges, and improvements will be discussed to aid other sites in their efforts to conduct similar activities.

Rodriguez, M.

2010-12-17T23:59:59.000Z

86

Performance Demonstration Program Plan for Nondestructive Assay of Drummed Wastes for the TRU Waste Characterization Program  

SciTech Connect (OSTI)

The Performance Demonstration Program (PDP) for Nondestructive Assay (NDA) is a test program designed to yield data on measurement system capability to characterize drummed transuranic (TRU) waste generated throughout the Department of Energy (DOE) complex. The tests are conducted periodically and provide a mechanism for the independent and objective assessment of NDA system performance and capability relative to the radiological characterization objectives and criteria of the Office of Characterization and Transportation (OCT). The primary documents requiring an NDA PDP are the Waste Acceptance Criteria for the Waste Isolation Pilot Plant (WAC), which requires annual characterization facility participation in the PDP, and the Quality Assurance Program Document (QAPD). This NDA PDP implements the general requirements of the QAPD and applicable requirements of the WAC. Measurement facilities must demonstrate acceptable radiological characterization performance through measurement of test samples comprised of pre-specified PDP matrix drum/radioactive source configurations. Measurement facilities are required to analyze the NDA PDP drum samples using the same procedures approved and implemented for routine operational waste characterization activities. The test samples provide an independent means to assess NDA measurement system performance and compliance per criteria delineated in the NDA PDP Plan. General inter-comparison of NDA measurement system performance among DOE measurement facilities and commercial NDA services can also be evaluated using measurement results on similar NDA PDP test samples. A PDP test sample consists of a 55-gallon matrix drum containing a waste matrix type representative of a particular category of the DOE waste inventory and nuclear material standards of known radionuclide and isotopic composition typical of DOE radioactive material. The PDP sample components are made available to participating measurement facilities as designated by the Carlsbad Field Office (CBFO). The nuclear material type, mass and associated alpha activity of the NDA PDP radioactive standard sets have been specified and fabricated to allow assembly of PDP samples that simulate TRU alpha activity concentrations, radionuclidic/isotopic distributions and physical forms typical of the DOE TRU waste inventory. The PDP matrix drum waste matrix types were derived from an evaluation of information contained in the Transuranic Waste Baseline Inventory Report (TWBIR) to ensure representation of prevalent waste types and their associated matrix characteristics in NDA PDP testing. NDA drum analyses required by the Waste Isolation Pilot Plant (WIPP) may only be performed by measurement facilities that comply with the performance criteria as set forth in the NDA PDP Plan. In this document, these analyses are referred to as WIPP analyses, and the wastes on which they are performed are referred to as WIPP wastes.

Carlsbad Field Office

2005-08-03T23:59:59.000Z

87

W-026, transuranic waste (TRU) glovebox acceptance test report  

SciTech Connect (OSTI)

On July 18, 1997, the Transuranic (TRU) glovebox was tested using glovebox acceptance test procedure 13021A-86. The primary focus of the glovebox acceptance test was to examine control system interlocks, display menus, alarms, and operator messages. Limited mechanical testing involving the drum ports, hoists, drum lifter, compacted drum lifter, drum tipper, transfer car, conveyors, sorting table, lidder/delidder device and the TRU empty drum compactor were also conducted. As of February 25, 1998, 10 of the 102 test exceptions that affect the TRU glovebox remain open. These items will be tracked and closed via the WRAP Master Test Exception Database. As part of Test Exception resolution/closure the responsible individual closing the Test Exception performs a retest of the affected item(s) to ensure the identified deficiency is corrected, and, or to test items not previously available to support testing. Test exceptions are provided as appendices to this report.

Leist, K.J.

1998-03-11T23:59:59.000Z

88

TRU waste certification compliance requirements for contact-handled wastes retrieved from storage for shipment to the WIPP  

SciTech Connect (OSTI)

Compliance requirements are presented for certifying that unclassified, contact-handled (CH) transuranic (TRU) solid wastes retrieved from storage at DOE sites meet the Waste Isolation Pilot Plant (WIPP) Waste Acceptance Criteria (WAC). All applicable DOE Orders must continue to be met. The compliance requirements for certified waste retrieved from certified storage are addressed in another document. The compliance requirements are divided into four sections, primarily determined by the general feature that the requirements address. These sections are General Requirements, Waste Container Requirements, Waste Form Requirements, and Waste Package Requirements. The waste package is the combination of waste container and waste.

Not Available

1982-09-01T23:59:59.000Z

89

Performance Demonstration Program Plan for Nondestructive Assay of Drummed Wastes for the TRU Waste Characterization Program  

SciTech Connect (OSTI)

The Performance Demonstration Program (PDP) for nondestructive assay (NDA) consists of a series of tests to evaluate the capability for NDA of transuranic (TRU) waste throughout the Department of Energy (DOE) complex. Each test is termed a PDP cycle. These evaluation cycles provide an objective measure of the reliability of measurements obtained from NDA systems used to characterize the radiological constituents of TRU waste. The primary documents governing the conduct of the PDP are the Waste Acceptance Criteria for the Waste Isolation Pilot Plant (WAC; DOE 1999a) and the Quality Assurance Program Document (QAPD; DOE 1999b). The WAC requires participation in the PDP; the PDP must comply with the QAPD and the WAC. The WAC contains technical and quality requirements for acceptable NDA. This plan implements the general requirements of the QAPD and applicable requirements of the WAC for the NDA PDP. Measurement facilities demonstrate acceptable performance by the successful testing of simulated waste containers according to the criteria set by this PDP Plan. Comparison among DOE measurement groups and commercial assay services is achieved by comparing the results of measurements on similar simulated waste containers reported by the different measurement facilities. These tests are used as an independent means to assess the performance of measurement groups regarding compliance with established quality assurance objectives (QAO's). Measurement facilities must analyze the simulated waste containers using the same procedures used for normal waste characterization activities. For the drummed waste PDP, a simulated waste container consists of a 55-gallon matrix drum emplaced with radioactive standards and fabricated matrix inserts. These PDP sample components are distributed to the participating measurement facilities that have been designated and authorized by the Carlsbad Field Office (CBFO). The NDA Drum PDP materials are stored at these sites under secure conditions to protect them from loss, tampering, or accidental damage. Using removable PDP radioactive standards, isotopic activities in the simulated waste containers are varied to the extent possible over the range of concentrations anticipated in actual waste characterization situations. Manufactured matrices simulate expected waste matrix conditions and provide acceptable consistency in the sample preparation process at each measurement facility. Analyses that are required by the Waste Isolation Pilot Plant (WIPP) to demonstrate compliance with various regulatory requirements and that are included in the PDP may only be performed by measurement facilities that demonstrate acceptable performance in the PDP. These analyses are referred to as WIPP analyses, and the wastes on which they are performed are referred to as WIPP wastes in this document.

DOE Carlsbad Field Office

2001-04-06T23:59:59.000Z

90

Pyrolysis/Steam Reforming Technology for Treatment of TRU Orphan Wastes  

SciTech Connect (OSTI)

Certain transuranic (TRU) waste streams within the Department of Energy (DOE) complex cannot be disposed of at the Waste Isolation Pilot Plant (WIPP) because they do not meet the shipping requirements of the TRUPACT-II or the disposal requirements of the Waste Analysis Plan (WAP) in the WIPP RCRA Part B Permit. These waste streams, referred to as orphan wastes, cannot be shipped or disposed of because they contain one or more prohibited items, such as liquids, volatile organic compounds (VOCs), hydrogen gas, corrosive acids or bases, reactive metals, or high concentrations of polychlorinated biphenyl (PCB), etc. The patented, non-incineration, pyrolysis and steam reforming processes marketed by THOR Treatment Technologies LLC removes all of these prohibited items from drums of TRU waste and produces a dry, inert, inorganic waste material that meets the existing TRUPACT-II requirements for shipping, as well as the existing WAP requirements for disposal of TRU waste at WIPP. THOR Treatment Technologies is a joint venture formed in June 2002 by Studsvik, Inc. (Studsvik) and Westinghouse Government Environmental Services Company LLC (WGES) to further develop and deploy Studsvik's patented THORSM technology within the DOE and Department of Defense (DoD) markets. The THORSM treatment process is a commercially proven system that has treated over 100,000 cu. ft. of nuclear waste from commercial power plants since 1999. Some of this waste has had contact dose rates of up to 400 R/hr. A distinguishing characteristic of the THORSM process for TRU waste treatment is the ability to treat drums of waste without removing the waste contents from the drum. This feature greatly minimizes criticality and contamination issues for processing of plutonium-containing wastes. The novel features described herein are protected by issued and pending patents.

Mason, J. B.; McKibbin, J.; Schmoker, D.; Bacala, P.

2003-02-27T23:59:59.000Z

91

RH-TRU Waste Characterization by Acceptable Knowledge at the Idaho National Engineering and Environmental Laboratory  

SciTech Connect (OSTI)

Idaho National Engineering and Environmental Laboratory (INEEL) is conducting an effort to characterize approximately 620 drums of remote-handled (RH-) transuranic (TRU) waste currently in its inventory that were generated at the Argonne National Laboratory-East (ANL-E) Alpha Gamma Hot Cell Facility (AGHCF) between 1971 and 1995. The waste was generated at the AGHCF during the destructive examination of irradiated and unirradiated fuel pins, targets, and other materials from reactor programs at ANL-West (ANL-W) and other Department of Energy (DOE) reactors. In support of this effort, Shaw Environmental and Infrastructure (formerly IT Corporation) developed an acceptable knowledge (AK) collection and management program based on existing contact-handled (CH)-TRU waste program requirements and proposed RH-TRU waste program requirements in effect in July 2001. Consistent with Attachments B-B6 of the Waste Isolation Pilot Plant (WIPP) Hazardous Waste Facility Permit (HWFP) and th e proposed Class 3 permit modification (Attachment R [RH-WAP] of this permit), the draft AK Summary Report prepared under the AK procedure describes the waste generating process and includes determinations in the following areas based on AK: physical form (currently identified at the Waste Matrix Code level); waste stream delineation; applicability of hazardous waste numbers for hazardous waste constituents; and prohibited items. In addition, the procedure requires and the draft summary report contains information supporting determinations in the areas of defense relationship and radiological characterization.

Schulz, C.; Givens, C.; Bhatt, R.; Whitworth, J.

2003-02-24T23:59:59.000Z

92

Performance Demonstration Program Plan for Nondestructive Assay of Boxed Wastes for the TRU Waste Characterization Program  

SciTech Connect (OSTI)

The Performance Demonstration Program (PDP) for nondestructive assay (NDA) consists of a series of tests to evaluate the capability for NDA of transuranic (TRU) waste throughout the Department of Energy (DOE) complex. Each test is termed a PDP cycle. These evaluation cycles provide an objective measure of the reliability of measurements obtained from NDA systems used to characterize the radiological constituents of TRU waste. The primary documents governing the conduct of the PDP are the Waste Acceptance Criteria for the Waste Isolation Pilot Plant (WAC; DOE 1999a) and the Quality Assurance Program Document (QAPD; DOE 1999b). The WAC requires participation in the PDP; the PDP must comply with the QAPD and the WAC. The WAC contains technical and quality requirements for acceptable NDA. This plan implements the general requirements of the QAPD and applicable requirements of the WAC for the NDA PDP for boxed waste assay systems. Measurement facilities demonstrate acceptable performance by the successful testing of simulated waste containers according to the criteria set by this PDP Plan. Comparison among DOE measurement groups and commercial assay services is achieved by comparing the results of measurements on similar simulated waste containers reported by the different measurement facilities. These tests are used as an independent means to assess the performance of measurement groups regarding compliance with established quality assurance objectives (QAO’s). Measurement facilities must analyze the simulated waste containers using the same procedures used for normal waste characterization activities. For the boxed waste PDP, a simulated waste container consists of a modified standard waste box (SWB) emplaced with radioactive standards and fabricated matrix inserts. An SWB is a waste box with ends designed specifically to fit the TRUPACT-II shipping container. SWB’s will be used to package a substantial volume of the TRU waste for disposal. These PDP sample components are distributed to the participating measurement facilities that have been designated and authorized by the Carlsbad Field Office (CBFO). The NDA Box PDP materials are stored at these sites under secure conditions to protect them from loss, tampering, or accidental damage. Using removable PDP radioactive standards, isotopic activities in the simulated waste containers are varied to the extent possible over the range of concentrations anticipated in actual waste characterization situations. Manufactured matrices simulate expected waste matrix configurations and provide acceptable consistency in the sample preparation process at each measurement facility. Analyses that are required by the Waste Isolation Pilot Plant (WIPP) to demonstrate compliance with various regulatory requirements and that are included in the PDP may only be performed by measurement facilities that demonstrate acceptable performance in the PDP. These analyses are referred to as WIPP analyses, and the wastes on which they are performed are referred to as WIPP wastes in this document.

Carlsbad Field Office

2001-01-31T23:59:59.000Z

93

Adequacy of a Small Quantity Site RH-TRU Waste Program in Meeting Proposed WIPP Characterization Objectives  

SciTech Connect (OSTI)

The first remote-handled transuranic (RH-TRU) waste is expected to be permanently disposed of at the Waste Isolation Pilot Plant (WIPP) during Fiscal Year (FY) 2003. The first RH-TRU waste shipments are scheduled from the Battelle Columbus Laboratories (BCL) to WIPP in order to facilitate compliance with BCL Decommissioning Project (BCLDP) milestones. Milestones requiring RH-TRU waste containerization and removal from the site by 2004 in order to meet a 2006 site closure goal, established by Congress in the Defense Facilities Closure Projects account, necessitated the establishment and implementation of a site-specific program to direct the packaging of BCLDP RH-TRU waste prior to the finalization of WIPP RH-TRU waste characterization requirements. The program was designed to collect waste data, including audio and videotape records of waste packaging, such that upon completion of waste packaging, comprehensive data records exist from which compliance with final WIPP RH-TRU waste characterization requirements can be demonstrated. With the BCLDP data records generated to date and the development by the U.S. Department of Energy (DOE)-Carlsbad Field Office (CBFO) of preliminary documents proposing the WIPP RH-TRU waste characterization program, it is possible to evaluate the adequacy of the BCLDP program with respect to meeting proposed characterization objectives. The BCLDP characterization program uses primarily acceptable knowledge (AK) and visual examination (VE) during waste packaging to characterize RH-TRU waste. These methods are used to estimate physical waste parameters, including weight percentages of metals, cellulosics, plastics, and rubber in the waste, and to determine the absence of prohibited items, including free liquids. AK combined with computer modeling is used to estimate radiological waste parameters, including total activity on a waste container basis, for the majority of BCLDP RH-TRU waste. AK combined with direct analysis is used to characterize radiological parameters for the small populations of the RH-TRU waste generated by the BCLDP. All characterization based on AK is verified. Per its design for comprehensive waste data collection, the BCLDP characterization program using AK and waste packaging procedures, including VE during packaging, meets the proposed WIPP RH-TRU waste characterization objectives. The conservative program design implemented generates certification data that will be adequate to meet any additional program requirements that may be imposed by the CBFO.

Biedscheid, J.; Stahl, S.; Devarakonda, M.; Peters, K.; Eide, J.

2002-02-26T23:59:59.000Z

94

RH-TRU Waste Shipments from Battelle Columbus Laboratories to the Hanford Nuclear Facility for Interim Storage  

SciTech Connect (OSTI)

Battelle Columbus Laboratories (BCL), located in Columbus, Ohio, must complete decontamination and decommissioning (D&D) activities for nuclear research buildings and grounds by 2006, as directed by Congress. Most of the resulting waste (approximately 27 cubic meters [m3]) is remote-handled (RH) transuranic (TRU) waste destined for disposal at the Waste Isolation Pilot Plant (WIPP). The BCL, under a contract to the U.S. Department of Energy (DOE) Ohio Field Office, has initiated a plan to ship the TRU waste to the DOE Hanford Nuclear Facility (Hanford) for interim storage pending the authorization of WIPP for the permanent disposal of RH-TRU waste. The first of the BCL RH-TRU waste shipments was successfully completed on December 18, 2002. This BCL shipment of one fully loaded 10-160B Cask was the first shipment of RH-TRU waste in several years. Its successful completion required a complex effort entailing coordination between different contractors and federal agencies to establish necessary supporting agreements. This paper discusses the agreements and funding mechanisms used in support of the BCL shipments of TRU waste to Hanford for interim storage. In addition, this paper presents a summary of the efforts completed to demonstrate the effectiveness of the 10-160B Cask system. Lessons learned during this process are discussed and may be applicable to other TRU waste site shipment plans.

Eide, J.; Baillieul, T. A.; Biedscheid, J.; Forrester, T,; McMillan, B.; Shrader, T.; Richterich, L.

2003-02-26T23:59:59.000Z

95

W-026, transuranic waste restricted waste management (TRU RWM) glovebox operational test report  

SciTech Connect (OSTI)

The TRU Waste/Restricted Waste Management (LLW/PWNP) Glovebox 401 is designed to accept and process waste from the Transuranic Process Glovebox 302. Waste is transferred to the glovebox via the Drath and Schraeder Bagless Transfer Port (DO-07401) on a transfer stand. The stand is removed with a hoist and the operator inspects the waste (with the aid of the Sampling and Treatment Director) to determine a course of action for each item. The waste is separated into compliant and non compliant. One Trip Port DO-07402A is designated as ``Compliant``and One Trip Port DO-07402B is designated as ``Non Compliant``. As the processing (inspection, bar coding, sampling and treatment) of the transferred items takes place, residue is placed in the appropriate One Trip port. The status of the waste items is tracked by the Data Management System (DMS) via the Plant Control System (PCS) barcode interface. As an item is moved for sampling or storage or it`s state altered by treatment, the Operator will track an items location using a portable barcode reader and entry any required data on the DMS console. The Operational Test Procedure (OTP) will perform evolutions (described here) using the Plant Operating Procedures (POP) in order to verify that they are sufficient and accurate for controlled glovebox operation.

Leist, K.J.

1998-02-18T23:59:59.000Z

96

Transuranic (TRU) Waste Site Certification/ Recertification | Department of  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of EnergyEnergyENERGYWomen Owned SmallOf The 2012 Greenbuy3 Archive Transportation Fact ofATEnergy (TRU)

97

Design and performance of a fluidized-bed incinerator for TRU combustible wastes  

SciTech Connect (OSTI)

Problems encountered in the incineration of glovebox generated waste at Rocky Flats Plant (RFP) led to the development of a fluidized-bed incineration (FBI) system for transuranic (TRU) combustible wastes. Laboratory and pilot-scale testing of the process preceded the installation of an 82-kg/h production demonstration incinerator at RFP. The FBI process is discussed, and the design of the demonstration incinerator is described. Operating experience and process performance for both the pilot and demonstration units are presented.

Meile, L.J.; Meyer, F.G.

1982-01-01T23:59:59.000Z

98

Microbial Transformation of TRU and Mixed Waste: Actinide Speciation and Waste Volume  

SciTech Connect (OSTI)

In order to understand the susceptibility of transuranic and mixed waste to microbial degradation (as well as any mechanism which depends upon either complexation and/or redox of metal ions), it is essential to understand the association of metal ions with organic ligands present in mixed wastes. These ligands have been found in our previous EMSP study to limit electron transfer reactions and strongly affect transport and the eventual fate of radionuclides in the environment. As transuranic waste (and especially mixed waste) will be retained in burial sites and in legacy containment for (potentially) many years while awaiting treatment and removal (or remaining in place under stewardship agreements at government subsurface waste sites), it is also essential to understand the aging of mixed wastes and its implications for remediation and fate of radionuclides. Mixed waste containing actinides and organic materials are especially complex and require extensive study. The EMSP program described in this report is part of a joint program with the Environmental Sciences Department at Brookhaven National Laboratory. The Stony Brook University portion of this award has focused on the association of uranium (U(VI)) and transuranic analogs (Ce(III) and Eu(III)) with cellulosic materials and related compounds, with development of implications for microbial transformation of mixed wastes. The elucidation of the chemical nature of mixed waste is essential for the formulation of remediation and encapsulation technologies, for understanding the fate of contaminant exposed to the environment, and for development of meaningful models for contaminant storage and recovery.

Halada, Gary P

2008-04-10T23:59:59.000Z

99

Final Hanford Site Transuranic (TRU) Waste Characterization QA Project Plan  

SciTech Connect (OSTI)

The Transuranic Waste Characterization Quality Assurance Program Plan required each US Department of Energy (DOE) site that characterizes transuranic waste to be sent the Waste Isolation Pilot Plan that addresses applicable requirements specified in the QAPP.

GREAGER, T.M.

1999-09-09T23:59:59.000Z

100

EXPERIENCE FROM TWO SMALL QUANTITY RH-TRU WASTE SITES IN NAVIGATING THROUGH AN EVOLVING REGULATORY LANDSCAPE  

SciTech Connect (OSTI)

Two small quantity transuranic (TRU) waste generator sites have gained considerable experience in navigating through a changing regulatory landscape in their efforts to remove the TRU waste from their sites and proceed with site remediation. The Battelle Columbus Laboratories Decommissioning Project (BCLDP) has the objectives of decontaminating nuclear research buildings and associated grounds and remediating to a level of residual contamination allowing future use without radiological restrictions. As directed by Congress, BCLDP must complete decontamination and decommissioning activities by the end of Fiscal Year (FY) 2006. This schedule requires the containerization of all TRU waste in 2002. BCLDP will generate a total of approximately 27 cubic meters (m3) of remote-handled (RH) TRU waste. Similarly, the Energy Technology Engineering Center (ETEC) is scheduled to close in 2006 pursuant to an agreement between the U.S. Department of Energy (DOE) and Boeing Canoga Park, the management and operating contractor for ETEC. ETEC had 11.0 m3 of RH-TRU and contact-handled (CH) TRU waste in storage, with the requirement to remove this waste in 2002 in order to meet their site closure schedule. The individual milestones for BCLDP and ETEC necessitated the establishment of site-specific programs to direct packaging and characterization of RH-TRU waste before the regulatory framework for the WIPP disposal of RH-TRU waste is finalized. The lack of large infrastructure for characterization activities, as well as the expedited schedules needed to meet regulatory milestones, provided both challenges and opportunities that are unique to small quantity sites. Both sites have developed unique programs for waste characterization based on the same premise, which directs comprehensive waste data collection efforts such that additional characterization will not be required following the finalization of the WIPP RH-TRU waste program requirements. This paper details the BCLDP program evolution in terms of strategy, innovative solutions to waste characterization, and development of alternative transportation options. Preliminary indications from various regulatory and oversight agencies and professional organizations are that the BCLDP RH-TRU waste characterization program is the ''model WIPP certification program'' and will satisfy anticipated regulatory expectations. This paper also summarizes how BCLDP lessons learned and their development of new resources were applied to the RH-TRU waste characterization and disposition program at ETEC.

Biedscheid, Jennifer; Devarakonda, Murthy; Eide, Jim; Kneff, Dennis

2003-02-27T23:59:59.000Z

Note: This page contains sample records for the topic "legacy tru waste" 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.


101

Preliminary identification of interfaces for certification and transfer of TRU waste to WIPP  

SciTech Connect (OSTI)

This study complements the national program to certify that newly generated and stored, unclassified defense transuranic (TRU) wastes meet the Waste Isolation Pilot Plant (WIPP) Waste Acceptance Criteria. The objectives of this study were to identify (1) the existing organizational structure at each of the major waste-generating and shipping sites and (2) the necessary interfaces between the waste shippers and WIPP. The interface investigations considered existing waste management organizations at the shipping sites and the proposed WIPP organization. An effort was made to identify the potential waste-certifying authorities and the lines of communication within these organizations. The long-range goal of this effort is to develop practicable interfaces between waste shippers and WIPP to enable the continued generation, interim storage, and eventual shipment of certified TRU wastes to WIPP. Some specific needs identified in this study include: organizational responsibility for certification procedures and quality assurance (QA) program; simple QA procedures; and specification and standardization of reporting forms and procedures, waste containers, and container labeling, color coding, and code location.

Whitty, W.J.; Ostenak, C.A.; Pillay, K.K.S.

1982-02-01T23:59:59.000Z

102

Final Hanford Site Transuranic (TRU) Waste Characterization QA Project Plan  

SciTech Connect (OSTI)

The Transuranic Waste Characterization Quality Assurance Program Plan required each U.S. Department of Energy (DOE) site that characterizes transuranic waste to be sent the Waste Isolation Pilot Plan that addresses applicable requirements specified in the quality assurance project plan (QAPP).

GREAGER, T.M.

1999-12-14T23:59:59.000Z

103

MANAGEMENT OF TRANSURANIC (TRU) WASTE RETRIEVAL PROJECT RISKS SUCCESSES IN THE STARTUP OF THE HANFORD 200 AREA TRU WASTE RETRIEVAL PROJECT  

SciTech Connect (OSTI)

A risk identification and mitigation method applied to the Transuranic (TRU) Waste Retrieval Project performed at the Hanford 200 Area burial grounds is described. Retrieval operations are analyzed using process flow diagramming. and the anticipated project contingencies are included in the Authorization Basis and operational plans. Examples of uncertainties assessed include degraded container integrity, bulged drums, unknown containers, and releases to the environment. Identification and mitigation of project risks contributed to the safe retrieval of over 1700 cubic meters of waste without significant work stoppage and below the targeted cost per cubic meter retrieved. This paper will be of interest to managers, project engineers, regulators, and others who are responsible for successful performance of waste retrieval and other projects with high safety and performance risks.

GREENWLL, R.D.

2005-01-20T23:59:59.000Z

104

Analysis of long-term impacts of TRU waste remaining at generator/storage sites for No Action Alternative 2  

SciTech Connect (OSTI)

This report is a supplement to the Waste Isolation Pilot Plant Disposal-Phase Final Supplemental Environmental Impact Statement (SEIS-II). Described herein are the underlying information, data, and assumptions used to estimate the long-term human-health impacts from exposure to radionuclides and hazardous chemicals in transuranic (TRU) waste remaining at major generator/storage sites after loss of institutional control under No Action Alternative 2. Under No Action Alternative 2, TRU wastes would not be emplaced at the Waste Isolation Pilot Plant (WIPP) but would remain at generator/storage sites in surface or near-surface storage. Waste generated at smaller sites would be consolidated at the major generator/storage sites. Current TRU waste management practices would continue, but newly generated waste would be treated to meet the WIPP waste acceptance criteria. For this alternative, institutional control was assumed to be lost 100 years after the end of the waste generation period, with exposure to radionuclides and hazardous chemicals in the TRU waste possible from direct intrusion and release to the surrounding environment. The potential human-health impacts from exposure to radionuclides and hazardous chemicals in TRU waste were analyzed for two different types of scenarios. Both analyses estimated site-specific, human-health impacts at seven major generator/storage sites: the Hanford Site (Hanford), Idaho National Engineering and Environmental Laboratory (INEEL), Lawrence Livermore National Laboratory (LLNL), Los Alamos National Laboratory (LANL), Oak Ridge National Laboratory (ORNL), Rocky Flats Environmental Technology Site (RFETS), and Savannah River Site (SRS). The analysis focused on these seven sites because 99 % of the estimated TRU waste volume and inventory would remain there under the assumptions of No Action Alternative 2.

Buck, J.W.; Bagaasen, L.M.; Bergeron, M.P.; Streile, G.P. [and others

1997-09-01T23:59:59.000Z

105

Documentation of acceptable knowledge for Los Alamos National Laboratory Plutonium Facility TRU waste stream  

SciTech Connect (OSTI)

Characterization of transuranic waste from the LANL Plutonium Facility for certification and transportation to WIPP includes the use of acceptable knowledge as specified in the WIPP Quality Assurance Program Plan. In accordance with a site specific procedure, documentation of acceptable knowledge for retrievably stored and currently generated transuranic waste streams is in progress at LANL. A summary overview of the TRU waste inventory is complete and documented in the Sampling Plan. This document also includes projected waste generation, facility missions, waste generation processes, flow diagrams, times, and material inputs. The second part of acceptable knowledge documentation consists of assembling more detailed acceptable knowledge information into auditable records and is expected to require several years to complete. These records for each waste stream must support final assignment of waste matrix parameters, EPA hazardous waste numbers, and radionuclide characterization. They must also include a determination whether waste streams are defense waste streams for compliance with the WIPP Land Withdrawal Act. The LANL Plutonium Facility`s mission is primarily plutonium processing in basic special nuclear material (SNM) research activities to support national defense and energy programs. It currently has about 100 processes ranging from SNM recovery from residues to development of plutonium 238 heat sources for space applications. Its challenge is to characterize and certify waste streams from such diverse and dynamic operations using acceptable knowledge. This paper reports the progress on the certification of the first of these waste streams to the WIPP WAC.

Montoya, A.J.; Gruetzmacher, K.M.; Foxx, C.L.; Rogers, P.Z.

1998-03-01T23:59:59.000Z

106

System to control contamination during retrieval of buried TRU waste  

DOE Patents [OSTI]

A system to control contamination during the retrieval of hazardous waste comprising an outer containment building, an inner containment building, within the outer containment building, an electrostatic radioactive particle recovery unit connected to and in communication with the inner and outer containment buildings, and a contaminate suppression system including a moisture control subsystem, and a rapid monitoring system having the ability to monitor conditions in the inner and outer containment buildings.

Menkhaus, Daniel E. (Idaho Falls, ID); Loomis, Guy G. (Idaho Falls, ID); Mullen, Carlan K. (Idaho Falls, ID); Scott, Donald W. (Idaho Falls, ID); Feldman, Edgar M. (Idaho Falls, ID); Meyer, Leroy C. (Idaho Falls, ID)

1993-01-01T23:59:59.000Z

107

System to control contamination during retrieval of buried TRU waste  

DOE Patents [OSTI]

A system is described to control contamination during the retrieval of hazardous waste comprising an outer containment building, an inner containment building, within the outer containment building, an electrostatic radioactive particle recovery unit connected to and in communication with the inner and outer containment buildings, and a contaminate suppression system including a moisture control subsystem, and a rapid monitoring system having the ability to monitor conditions in the inner and outer containment buildings.

Menkhaus, D.E.; Loomis, G.G.; Mullen, C.K.; Scott, D.W.; Feldman, E.M.; Meyer, L.C.

1993-04-20T23:59:59.000Z

108

MANAGING HANFORD'S LEGACY NO-PATH-FORWARD WASTES TO DISPOSITION  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE) Richland Operations Office (RL) has adopted the 2015 Vision for Cleanup of the Hanford Site. This vision will protect the Columbia River, reduce the Site footprint, and reduce Site mortgage costs. The CH2M HILL Plateau Remediation Company's (CHPRC) Waste and Fuels Management Project (W&FMP) and their partners support this mission by providing centralized waste management services for the Hanford Site waste generating organizations. At the time of the CHPRC contract award (August 2008) slightly more than 9,000 m{sup 3} of waste was defined as 'no-path-forward waste.' The majority of these wastes are suspect transuranic mixed (TRUM) wastes which are currently stored in the low-level Burial Grounds (LLBG), or stored above ground in the Central Waste Complex (CWC). A portion of the waste will be generated during ongoing and future site cleanup activities. The DOE-RL and CHPRC have collaborated to identify and deliver safe, cost-effective disposition paths for 90% ({approx}8,000 m{sup 3}) of these problematic wastes. These paths include accelerated disposition through expanded use of offsite treatment capabilities. Disposal paths were selected that minimize the need to develop new technologies, minimize the need for new, on-site capabilities, and accelerate shipments of transuranic (TRU) waste to the Waste Isolation Pilot Plant (WIPP) in Carlsbad, New Mexico.

WEST LD

2011-01-13T23:59:59.000Z

109

Total Measurement Uncertainty (TMU) for Nondestructive Assay of Transuranic (TRU) Waste at the WRAP Facility  

SciTech Connect (OSTI)

The Waste Receiving and Processing (WRAP) facility, located on the Hanford Site in southeast Washington, is a key link in the certification of Hanford's transuranic (TRU) waste for shipment to the Waste Isolation Pilot Plant (WIPP). Waste characterization is one of the vital functions performed at WRAP, and nondestructive assay (NDA) measurements of TRU waste containers is one of two required methods used for waste characterization (Reference 1). Various programs exist to ensure the validity of waste characterization data; all of these cite the need for clearly defined knowledge of uncertainty, associated with any measurements taken. All measurements have an inherent uncertainty associated with them. The combined effect of all uncertainties associated with a measurement is referred to as the Total Measurement Uncertainty (TMU). The NDA measurement uncertainties can be numerous and complex. In addition to system-induced measurement uncertainty, other factors contribute to the TMU, each associated with a particular measurement. The NDA measurements at WRAP are based on processes (radioactive decay and induced fission) which are statistical in nature. As a result, the proper statistical summation of the various uncertainty components is essential. This report examines the contributing factors to NDA measurement uncertainty at WRAP. The significance of each factor on the TMU is analyzed, and a final method is given for determining the TMU for NDA measurements at WRAP. As more data becomes available, and WRAP gains in operational experience, this report will be reviewed semi-annually and updated as necessary. This report also includes the data flow paths for the analytical process in the radiometric determinations.

WILLS, C.E.

2000-02-24T23:59:59.000Z

110

Final Environmental Impact Statement for Treating Transuranic (TRU)/Alpha Low-level Waste at the Oak Ridge National Laboratory Oak Ridge, Tennessee  

SciTech Connect (OSTI)

The DOE proposes to construct, operate, and decontaminate/decommission a TRU Waste Treatment Facility in Oak Ridge, Tennessee. The four waste types that would be treated at the proposed facility would be remote-handled TRU mixed waste sludge, liquid low-level waste associated with the sludge, contact-handled TRU/alpha low-level waste solids, and remote-handled TRU/alpha low-level waste solids. The mixed waste sludge and some of the solid waste contain metals regulated under the Resource Conservation and Recovery Act and may be classified as mixed waste. This document analyzes the potential environmental impacts associated with five alternatives--No Action, the Low-Temperature Drying Alternative (Preferred Alternative), the Vitrification Alternative, the Cementation Alternative, and the Treatment and Waste Storage at Oak Ridge National Laboratory (ORNL) Alternative.

N /A

2000-06-30T23:59:59.000Z

111

In-situ stabilization of TRU/mixed waste project at the INEEL  

SciTech Connect (OSTI)

Throughout the DOE complex, buried waste poses a threat to the environment by means of contaminant transport. Many of the sites contain buried waste that is untreated, prior to disposal, or insufficiently treated, by today`s standards. One option to remedy these disposal problems is to stabilize the waste in situ. This project was in support of the Transuranic/Mixed Buried Waste - Arid Soils product line of the Landfill Focus Area, which is managed currently by the Idaho National Engineering Laboratory (BNL) provided the analytical laboratory and technical support for the various stabilization activities that will be performed as part of the In Situ Stabilization of TRU/Mixed Waste project at the INEL. More specifically, BNL was involved in laboratory testing that included the evaluation of several grouting materials and their compatibility, interaction, and long-term durability/performance, following the encapsulation of various waste materials. The four grouting materials chosen by INEL were: TECT 1, a two component, high density cementious grout, WAXFIX, a two component, molten wax product, Carbray 100, a two component elastomeric epoxy, and phosphate cement, a two component ceramic. A simulated waste stream comprised of sodium nitrate, Canola oil, and INEL soil was used in this study. Seven performance and durability tests were conducted on grout/waste specimens: compressive strength, wet-dry cycling, thermal analysis, base immersion, solvent immersion, hydraulic conductivity, and accelerated leach testing.

Milian, L.W.; Heiser, J.H.; Adams, J.W.; Rutenkroeger, S.P.

1997-08-01T23:59:59.000Z

112

Determination of H{sub 2} Diffusion Rates through Various Closures on TRU Waste Bag-Out Bags  

SciTech Connect (OSTI)

The amount of H{sub 2} diffusion through twist and tape (horse-tail), wire tie, plastic tie, and heat sealed closures on transuranic (TRU) waste bag-out bags has been determined. H{sub 2} diffusion through wire and plastic tie closures on TRU waste bag-out bags has not been previously characterized and, as such, TRU waste drums containing bags with these closures cannot be certified and/or shipped to the Waste Isolation Pilot Plant (WIPP). Since wire ties have been used at Los Alamos National Laboratory (LANL) from 1980 to 1991 and the plastic ties from 1991 to the present, there are currently thousands of waste drums that cannot be shipped to the WIPP site. Repackaging the waste would be prohibitively expensive. Diffusion experiments performed on the above mentioned closures show that the diffusion rates of plastic tie and horse-tail closures are greater than the accepted value presented in the TRU-PACT 11 Safety Analysis Report (SAR). Diffusion rates for wire tie closures are not statistically different from the SAR value. Thus, drums containing bags with these closures can now potentially be certified which would allow for their consequent shipment to WIPP.

Phillip D. Noll, Jr.; E. Larry Callis; Kirsten M. Norman

1999-06-01T23:59:59.000Z

113

Performance Demonstration Program Plan for Nondestructive Assay for the TRU Waste Characterization Program. Revision 1  

SciTech Connect (OSTI)

The Performance Demonstration Program (PDP) for Nondestructive Assay (NDA) consists of a series of tests conducted on a regular frequency to evaluate the capability for nondestructive assay of transuranic (TRU) waste throughout the Department of Energy (DOE) complex. Each test is termed a PDP cycle. These evaluation cycles provide an objective measure of the reliability of measurements performed with TRU waste characterization systems. Measurement facility performance will be demonstrated by the successful analysis of blind audit samples according to the criteria set by this Program Plan. Intercomparison between measurement groups of the DOE complex will be achieved by comparing the results of measurements on similar or identical blind samples reported by the different measurement facilities. Blind audit samples (hereinafter referred to as PDP samples) will be used as an independent means to assess the performance of measurement groups regarding compliance with established Quality Assurance Objectives (QAOs). As defined for this program, a PDP sample consists of a 55-gallon matrix drum emplaced with radioactive standards and fabricated matrix inserts. These PDP sample components, once manufactured, will be secured and stored at each participating measurement facility designated and authorized by Carlsbad Area Office (CAO) under secure conditions to protect them from loss, tampering, or accidental damage.

None

1997-05-01T23:59:59.000Z

114

TRU waste certification compliance requirements for acceptance of contact-handled wastes retrieved from storage to be shipped to the WIPP. Revision 1  

SciTech Connect (OSTI)

Compliance requirements are presented for certifying that unclassified, contact-handled (CH) transuranic (TRU) solid defense wastes retrieved from storage at DOE sites meet the Waste Isolation Pilot Plant (WIPP) Waste Acceptance Criteria (WAC). All applicable DOE orders must continue to be met. The compliance requirements for certified waste retrieved from certified storage are addressed in another document. The compliance requirements are divided into four sections, primarily determined by the general feature that the requirements address. These sections are General Requirements, Waste Container Requirements, Waste Form Requirements, and Waste Package Requirements. The waste package is the combination of waste container and waste. 2 refs., 1 fig.

Not Available

1985-09-01T23:59:59.000Z

115

TRU (transuranic) waste certification compliance requirements for acceptance of newly generated contact-handled wastes to be shipped to the Waste Isolation Pilot Plant: Revision 2  

SciTech Connect (OSTI)

Compliance requirements are presented for certifying that unclassified, newly generated (NG), contact-handled (CH) transuranic (TRU) solid wastes from defense programs meet the Waste Isolation Pilot Plant (WIPP) Waste Acceptance Criteria (WAC). Where appropriate, transportation and interim storage requirements are incorporated; however, interim storage sites may have additional requirements consistent with these requirements. All applicable Department of Energy (DOE) orders must continue to be met. The compliance requirements for stored or buried waste are not addressed in this document. The compliance requirements are divided into four sections, primarily determined by the general feature that the requirements address. These sections are General Requirements, Waste Container Requirements, Waste Form Requirements, and Waste Package Requirements. The waste package is the combination of waste container and waste. 10 refs., 1 fig.

Not Available

1989-01-01T23:59:59.000Z

116

TRU (transuranic) waste certification compliance requirements for acceptance of contact-handled wastes retrieved from storage to be shipped to the Waste Isolation Pilot Plant: Revision 2  

SciTech Connect (OSTI)

Compliance requirements are presented for certifying that unclassified, contact-handled (CH) transuranic (TRU) solid defense wastes retrieved from storage at DOE sites meet the Waste Isolation Pilot Plant (WIPP) Waste Acceptance Criteria (WAC). All applicable Department of Energy (DOE) orders must continue to be met. The compliance requirements for acceptance of newly generated CH waste to be shipped to the WIPP are addressed in another document. The compliance requirements are divided into four sections, primarily determined by the general feature that the requirements address. These sections are General Requirements, Waste Container Requirements, Waste Form Requirements, and Waste Package Requirements. The waste package is the combination of waste container and waste. 10 refs., 1 fig.

Not Available

1989-01-01T23:59:59.000Z

117

WIPP TRANSURANIC WASTE How has the WIPP TRU Waste Inventory Changed  

E-Print Network [OSTI]

of tank waste from the Hanford site that is currently managed as high-level waste. None of this waste has that these Hanford tank wastes will be treated and will eventually be able to meet the WIPP waste acceptance criteria on the Hanford Tank Waste and K-Basin Sludges that were included in the waste inventory for recertifica- tion

118

Preparation of certified working reference material sources for the national TRU waste performance demonstration program.  

SciTech Connect (OSTI)

Traceable non-destructive assay (NDA) standards containing a variety of radionuclides including uranium, americium, and plutonium oxides mixed with an inert matrix were prepared and certified for use in the U .S. Department of Energy's National TRU Waste Program (NTWP) . The NTWP requires traceable nuclear material standards of the Working Reference Material (WRM) class for qualification of NDA instrumentation that is used to quantify nuclear material in DOE-generated waste before the waste is shipped for final disposition at the Waste Isolation Pilot Plant (WIPP) in Carlsbad, New Mexico . Qualification and approval of measurement systems is accomplished in part through successful participation in the Non-Destructive Assay (NDA) Performance Demonstration Program (PDP) and is required for DOE and EPA regulatory compliance . An overview of the PDP program highlighting the role of the certified WRMs fabricated at LANL is presented, as well as a summary of the WRM fabrication process and an overview of the inventory of over 175 WRMs fabricated and deployed to DOE measurement facilities to date .

Mecklenburg, S. L. (Sandra L.); Thronas, D. L. (Denise L.); Wong, A. S. (Amy S.); Marshall, Robert S.,; Becker, G. K.

2003-01-01T23:59:59.000Z

119

A Cask Processing Enclosure for the TRU Waste Processing Center - 13408  

SciTech Connect (OSTI)

This paper will discuss the key elements considered in the design, construction, and use of an enclosure system built for the TRU Waste Processing Center (TWPC). The TWPC system is used for the repackaging and volume reduction of items contaminated with radioactive material, hazardous waste and mixed waste. The modular structural steel frame and stainless steel skin was designed for rapid field erection by the use of interchangeable self-framing panel sections to allow assembly of a sectioned containment building and for ease of field mobility. The structure was installed on a concrete floor inside of an outer containment building. The major sections included an Outer Cask Airlock, Inner Cask Airlock, Cask Process Area, and Personnel Airlocks. Casks in overpacks containing transuranic waste are brought in via an inter-site transporter. The overpack lid is removed and the cask/overpack is transferred into the Outer Cask Airlock. A contamination cover is installed on the overpack body and the Outer Cask Airlock is closed. The cask/overpack is transferred into the Inner Cask Airlock on a cask bogie and the Inner Cask Airlock is closed. The cask lid is removed and the cask is transferred into the Cask Process Area where it is placed on a cask tilting station. Once the Cask Processing Area is closed, the cask tilt station is activated and wastes are removed, size reduced, then sorted and re-packaged into drums and standard waste boxes through bag ports. The modular system was designed and built as a 'Fast Track' project at IP Systems in Broomfield Colorado and then installed and is currently in use at the DOE TWPC located near Oak Ridge, Tennessee. (authors)

Newman, John T.; Mendez, Nicholas [IP Systems, Inc., 2685 Industrial Lane, Broomfield, Colorado 80020 (United States)] [IP Systems, Inc., 2685 Industrial Lane, Broomfield, Colorado 80020 (United States)

2013-07-01T23:59:59.000Z

120

Development of the remote-handled transuranic waste radioassay data quality objectives. An evaluation of RH-TRU waste inventories, characteristics, radioassay methods and capabilities  

SciTech Connect (OSTI)

The Waste Isolation Pilot Plant will accept remote-handled transuranic waste as early as October of 2001. Several tasks must be accomplished to meet this schedule, one of which is the development of Data Quality Objectives (DQOs) and corresponding Quality Assurance Objectives (QAOs) for the assay of radioisotopes in RH-TRU waste. Oak Ridge National Laboratory (ORNL) was assigned the task of providing to the DOE QAO, information necessary to aide in the development of DQOs for the radioassay of RH-TRU waste. Consistent with the DQO process, information needed and presented in this report includes: identification of RH-TRU generator site radionuclide data that may have potential significance to the performance of the WIPP repository or transportation requirements; evaluation of existing methods to measure the identified isotopic and quantitative radionuclide data; evaluation of existing data as a function of site waste streams using documented site information on fuel burnup, radioisotope processing and reprocessing, special research and development activities, measurement collection efforts, and acceptable knowledge; and the current status of technologies and capabilities at site facilities for the identification and assay of radionuclides in RH-TRU waste streams. This report is intended to provide guidance in developing the RH-TRU waste radioassay DQOs, first by establishing a baseline from which to work, second, by identifying needs to fill in the gaps between what is known and achievable today and that which will be required before DQOs can be formulated, and third, by recommending measures that should be taken to assure that the DQOs in fact balance risk and cost with an achievable degree of certainty.

Meeks, A.M.; Chapman, J.A.

1997-09-01T23:59:59.000Z

Note: This page contains sample records for the topic "legacy tru waste" 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

Immobilization and Waste Form Product Acceptance for Low Level and TRU Waste Forms  

SciTech Connect (OSTI)

The Tanks Focus Area is supporting technology development in immobilization of both High Level (HLW) and Low Level (LLW) radioactive wastes. The HLW process development at Hanford and Idaho is patterned closely after that of the Savannah River (Defense Waste Processing Facility) and West Valley Sites (West Valley Demonstration Project). However, the development and options open to addressing Low Level Waste are diverse and often site specific. To start, it is important to understand the breadth of Low Level Wastes categories.

Holtzscheiter, E.W. [Westinghouse Savannah River Company, AIKEN, SC (United States); Harbour, J.R.

1998-05-01T23:59:59.000Z

122

TRU waste certification compliance requirements for acceptance of newly generated contact-handled wastes to be shipped to the WIPP. Revision 1  

SciTech Connect (OSTI)

Compliance requirements are presented for certifying that unclassified, newly generated, contact-handled (CH) transuranic (TRU) solid wastes from defense programs meet the Waste Isolation Pilot Plant (WIPP) Waste Acceptance Criteria (WAC). Where appropriate, transportation and interim storage requirements are incorporated, however, interim storage sites may have additional requirements consistent with these requirements. All applicable DOE orders must continue to be met. The compliance requirements for stored or buried waste are not addressed in this document. The compliance requirements are divided into four sections, primarily determined by the general feature that the requirements address. These sections are General Requirements, Waste Container Requirements, Waste Form Requirements, and Waste Package Requirements. The waste package is the combination of waste container and waste. 2 refs., 1 fig.

Not Available

1985-09-01T23:59:59.000Z

123

Safety evaluation for packaging (onsite) for the concrete-shielded RH TRU drum for the 327 Postirradiation Testing Laboratory  

SciTech Connect (OSTI)

This safety evaluation for packaging authorizes onsite transport of Type B quantities of radioactive material in the Concrete Shielded Remote-Handled Transuranic Waste (RH TRU) Drum per HNF-PRO-154, Responsibilities and Procedures for all Hazardous Material Shipments. The drum will be used for transport of 327 Building legacy waste from the 300 Area to a solid waste storage facility on the Hanford Site.

Smith, R.J.

1998-03-31T23:59:59.000Z

124

Conversion of historic waste treatment process for production of an LDR and WIPP/WAC compliant TRU wasteform  

SciTech Connect (OSTI)

In support of the historic weapons production mission at the, Rocky Flats Environmental Technology Site (RFETS), several liquid waste treatment processes were designed, built and operated for treatment of plutonium-contaminated aqueous waste. Most of these @ processes ultimately resulted in the production of a cemented wasteform. One of these treatment processes was the Miscellaneous Aqueous Waste Handling and Solidification Process, commonly referred to as the Bottlebox process. Due to a lack of processing demand, Bottlebox operations were curtailed in late 1989. Starting in 1992, a treatment capability for stabilization of miscellaneous, Resource Conservation and Recovery Act (RCRA) hazardous, plutonium-nitrate solutions was identified. This treatment was required to address potentially unsafe storage conditions for these liquids. The treatment would produce a TRU wasteform. It thus became necessary to restart the Bottlebox process, but under vastly different conditions and constraints than existed prior to its curtailment. This paper provides a description of the historical Bottlebox process and process controls; and then describes, in detail, all of the process and process control changes that were implemented to convert the treatment system such that a Waste Isolation Pilot Plant (WIPP) and a Land Disposal Requirements (LDR) compliant wasteform would be produced. The rationale for imposition of LDRs on a TRU wasteform is discussed. In addition, this paper discusses the program changes implemented to meet modem criticality safety, Conduct of Operations, and Department of Energy Nuclear Facility restart requirements.

Dunn, R.P.; Wagner, R.A.

1997-03-01T23:59:59.000Z

125

Application of Robotics and X-ray Radiography to the Examination of Large Contact Handled Transuranic (TRU) Waste Containers  

SciTech Connect (OSTI)

The US Department of Energy, Savannah River Site is storing a large number of transuranic (TRU) waste containers that are to be shipped to the Waste Isolation Pilot Plant (WIPP) in Carlsbad, New Mexico. Radiographic examination of waste containers is required prior to shipment. This paper will discuss the TRU waste container positioning system and safety system provided by PaR Systems, Inc., Shoreview, MN, to the inspection system prime contractor, Hytec, Inc., Los Alamos, NM. Most containers will be over-packed in large metal shipping containers (TRUPACT-III). The largest containers are 2.8 m x 1.9 m x 1.9 m and weigh 5600 kg. In addition, smaller containers and drums are inspected. The containers are manipulated to view the contents from various directions. The motions of the container, X-ray source and X-ray detectors are coordinated to obtain a constant viewing area relative to the item of interest in the container. (authors)

Pe, A.S. [PaR Systems, Inc., PaR Systems Inc., Shoreview, MN (United States)

2007-07-01T23:59:59.000Z

126

Preliminary fire hazard analysis for the PUTDR and TRU trenches in the Solid Waste Burial Ground  

SciTech Connect (OSTI)

This document represents the Preliminary Fire Hazards Analysis for the Pilot Unvented TRU Drum Retrieval effort and for the Transuranic drum trenches in the low level burial grounds. The FHA was developed in accordance with DOE Order 5480.7A to address major hazards inherent in the facility.

Gaschott, L.J.

1995-06-16T23:59:59.000Z

127

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

SciTech Connect (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

128

Type B Accident Investigation of the April 8, 2003, Electrical Arc Blast at the Foster Wheeler Environmental Corporation TRU Waste Processing Facility, Oak Ridge, Tennessee  

Broader source: Energy.gov [DOE]

At approximately 0330 hours on April 8, 2003, a phase-to-phase arc blast occurred in the boiler electrical control panel at the Foster Wheeler Environmental Corporation (FWENC) Transuranic (TRU) Waste Processing Facility. The boiler was providing steam for the evaporator and was reportedly operating at about 10% of its capacity.

129

Radioactive and nonradioactive waste intended for disposal at the Waste Isolation Pilot Plant  

SciTech Connect (OSTI)

Transuranic (TRU) waste generated by the handling of plutonium in research on or production of US nuclear weapons will be disposed of in the Waste Isolation Pilot Plant (WIPP). This paper describes the physical and radiological properties of the TRU waste that will be deposited in the WIPP. This geologic repository will accommodate up to 175,564 m{sup 3} of TRU waste, corresponding to 168,485 m{sup 3} of contact-handled (CH-) TRU waste and 7,079 m{sup 3} of remote-handled (RH-) TRU waste. Approximately 35% of the TRU waste is currently packaged and stored (i.e., legacy) waste, with the remainder of the waste to be packaged or generated and packaged in activities before the year 2033, the closure time for the repository. These wastes were produced at 27 US Department of Energy (DOE) sites in the course of generating defense nuclear materials. The radionuclide and nonradionuclide inventories for the TRU wastes described in this paper were used in the 1996 WIPP Compliance Certification Application (CCA) performance assessment calculations by Sandia National Laboratories/New Mexico (SNL/NM).

SANCHEZ,LAWRENCE C.; DREZ,P.E.; RATH,JONATHAN S.; TRELLUE,H.R.

2000-05-19T23:59:59.000Z

130

Criticality Safety Evaluation for TRU Waste In Storage at the RWMC  

SciTech Connect (OSTI)

Stored containers (drums, boxes, and bins) of transuranic waste at the Radioactive Waste Management Complex (RWMC) facility located at the Idaho National Engineering Laboratory (INEL) were evaluated based on inherent neutron absorption characteristics of the waste materials. It was demonstrated that these properties are sufficient to preclude a criticality accident at the actual fissile levels present in the waste stored at the RWMC. Based on the database information available, the results reported herein confirm that the waste drums, boxes, and bins currently stored at the RWMC will remain safely subcritical if rearranged, restacked, or otherwise handled. Acceptance criteria for receiving future drum shipments were established based on fully infinite systems.

M. E. Shaw; J. B. Briggs; C. A. Atkinson; G. J. Briscoe

1994-04-01T23:59:59.000Z

131

Process Description for the Retrieval of Earth Covered Transuranic (TRU) Waste Containers at the Hanford Site  

SciTech Connect (OSTI)

This document describes process and operational options for retrieval of the contact-handled suspect transuranic waste drums currently stored below grade in earth-covered trenches at the Hanford Site. Retrieval processes and options discussed include excavation, container retrieval, venting, non-destructive assay, criticality avoidance, incidental waste handling, site preparation, equipment, and shipping.

DEROSA, D.C.

2000-01-13T23:59:59.000Z

132

Results of detailed characterization on CH-TRU mixed waste at Argonne National Laboratory-West  

SciTech Connect (OSTI)

Argonne National Laboratory-West and Lockheed Idaho Technologies Company have jointly participated in the Department of Energy`s (DOE) Waste Isolation Pilot Plant Experimental Test Program since 1990. A new facility at Argonne was developed to improve the effectiveness and efficiency of contact-handled transuranic mixed waste characterization and to decrease the potential for facility contamination and personnel exposures. This new facility, the Waste Characterization Area, was approved for radioactive operations in March 1994. Between April and September 1994, forty-two waste drums containing mixed debris waste were characterized to support a study being performed to evaluate volatile organic compound concentrations in the void volume headspaces of waste drums. This paper presents the results of characterization performed at Argonne, emphasizing parameters important from a facility standpoint. Specifically, information is presented on drum surface dose rate, fissile content, number and type of gas samples, volatile organic compound concentration, and facility contamination levels. Actual values are compared to enveloping conditions assumed in the safety assessment for the characterization facility. Argonne-West is one of the first DOE sites to perform detailed waste characterization under the DOE`s Transuranic Waste Characterization Program. The information presented herein could aid other storage and generator sites in developing characterization procedures and facilities.

Dwight, C.C.; Jensen, B.A.; Duncan, D.S.

1995-03-01T23:59:59.000Z

133

Total Measurement Uncertainty (TMU) for Nondestructive Assay of Transuranic (TRU) Waste at the WRAP Facility  

SciTech Connect (OSTI)

At the WRAP facility, there are two identical imaging passive/active neutron (IPAN) assay systems and two identical gamma energy assay (GEA) systems. Currently, only the GEA systems are used to characterize waste, therefore, only the GEA systems are addressed in this document. This document contains the limiting factors relating to the waste drum analysis for shipments destined for WIPP. The TMU document provides the uncertainty basis in the NDA analysis of waste containers at the WRAP facility. The defined limitations for the current analysis scheme are as follows: (1) The WRAP waste stream debris is from the Hanford Plutonium Finishing Plant's process lines, primarily combustible materials. (2) Plutonium analysis range is from the minimum detectable concentration (MDC), Reference 6, to 200 grams (g). (3) The GEA system calibration density ranges from 0.013 g/cc to 1.6 g/cc. (4) PDP Plutonium drum densities were evaluated from 0.065 g/cc to 0.305 g/cc. (5) PDP Plutonium source weights ranged from 0.030 g to 318 g, in both empty and combustibles matrix drums. (6) The GEA system design density correction mass absorption coefficient table (MAC) is Lucite, a material representative of combustible waste. (7) Drums with material not fitting the debris waste criteria are targeted for additional calculations, reviews, and potential re-analysis using a calibration suited for the waste type.

CANTALOUB, M.G.

2000-10-20T23:59:59.000Z

134

Total Measurement Uncertainty (TMU) for Nondestructive Assay of Transuranic (TRU) Waste at the WRAP Facility  

SciTech Connect (OSTI)

At the WRAP facility, there are two identical imaging passive/active neutron (IPAN) assay systems and two identical gamma energy assay (GEA) systems. Currently, only the GEA systems are used to characterize waste, therefore, only the GEA systems are addressed in this document. This document contains the limiting factors relating to the waste drum analysis for shipments destined for WIPP. The TMU document provides the uncertainty basis in the NDA analysis of waste containers at the WRAP facility. The defined limitations for the current analysis scheme are as follows: The WRAP waste stream debris is from the Hanford Plutonium Finishing Plant's process lines, primarily combustible materials. Plutonium analysis range is from the minimum detectable concentration (MDC), Reference 6, to 160 grams (8). The GEA system calibration density ranges from 0.013 g/cc to 1.6 g/cc. PDP Plutonium drum densities were evaluated from 0.065 g/cc to 0.305 gkc. PDP Plutonium source weights ranged from 0.030 g to 3 18 g, in both empty and combustibles matrix drums. The GEA system design density correction macroscopic absorption cross section table (MAC) is Lucite, a material representative of combustible waste. Drums with material not fitting the debris waste criteria are targeted for additional calculations, reviews, and potential re-analysis using a calibration suited for the waste type.

CANTALOUB, M.G.

2000-05-22T23:59:59.000Z

135

Characterization of mixed CH-TRU waste at Argonne-West. A WIPP project update  

SciTech Connect (OSTI)

Argonne National Laboratory is participating in the Department of Energy`s Waste Isolation Pilot Plant (WIPP) Experimental Test Program by characterizing and repackaging mixed contact-handled transuranic waste. Argonne`s initial activities in the Program were described last year at Waste Management `92. Since then, additional waste has been characterized and repackaged, resulting in six bins ready for shipment to WIPP upon the initiation of the bin tests. Lessons learned from these operations are being factored in the design and installation of a new characterization facility, the Enhanced Waste Characterization Facility (EWCF). The objectives of the WIPP Experimental Test Program have also undergone change since last year leading to an accelerated effort to factor sludge sampling capability into the EWCF. Consequently, the initiation of non-sludge operations in the waste characterization chamber has been delayed to Summer 1993 while the sludge sampling modifications are incorporated into the facility. Benefits in operational flexibility, effectiveness, and efficiency and reductions in potential facility and personnel contamination and exposure are expected from the enhanced waste characterization facility within the Hot Fuel Examination Facility at Argonne-West. This paper summarizes results and lessons learned from recent characterization and repackaging efforts and future plans for characterization. It also describes design features and status of the EWCF.

Dwight, C.C.; Guay, K.P. [Argonne National Lab., Idaho Falls, ID (United States); Courtney, J.C. [Louisiana State Univ., Baton Rouge, LA (US). Nuclear Science Center; Connolly, M.J. [EG and G Idaho, Inc., Idaho Falls, ID (US); Higgins, P.J. [USDOE Albuquerque Field Office, NM (United States). Waste Isolation Pilot Plant Project Integration Office

1993-01-29T23:59:59.000Z

136

E-Print Network 3.0 - assay tru waste Sample Search Results  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Data Report 06062008 07:50 2.6 % LASB00411... % % Report Date Run by Report Site Id Container Number Waste Stream Data Status Code PEARCYM Version RP0360... Selection...

137

La Hague Legacy Waste Recovery Program: Scope, Progress and Issues -12080  

SciTech Connect (OSTI)

A significant inventory of process waste of varying natures and quantities has been generated during the thirty years of operation of UP2 400 facility on the site of La Hague, France. The retrieval, packaging and final storage of such an inventory has never been achieved before in France and thus requires the design and qualification of new processes, equipment, and waste packages. Following AREVA strategic decisions and French safety authority requirements, the legacy waste program has begun around the year 2000 and is scheduled to be completed around the year 2025. It is under the responsibility of AREVA Site Value Development Project teams. For each category of waste to be recovered, AREVA teams conducted detailed investigations, defined recovery modes, treatment processes, as well as final waste package forms, which they subsequently submitted to French safety and waste management authorities. A Task force initiative was subsequently launched to optimize the program cost and scenario, and lead to an optimization of about 15% of the entire program. The qualification of processes and waste packages required a significant amount of research and development which is now well under way for processes, and scheduled to be completed in 2015. Preparation work has begun on several installations to clear space for the construction of future retrieval facilities, scheduled to begin in the coming three years. La Hague Legacy waste retrieval program represents a significant challenge in the sense that it covers a significant variety and quantity of waste needing recovery and reconditioning, with tight financial objectives and a binding recovery schedule. During the past five years, AREVA SVD successfully conducted design, research, development, and qualification activities which lead to the definition of qualified processes and waste packages for each retrieval program. Preparation work and supplier consultations are now on-going, in order to meet our objectives of beginning retrieval operations in compliance with our commitments to the safety authorities, in 2015 and 2016. (author)

Chabeuf, Jean-Michel [AREVA Site Value Development Business Unit, La Hague Site (France)

2012-07-01T23:59:59.000Z

138

Compliance with Waste Acceptance Criteria of WIPP and NTS for Vitrified Low-Level and TRU Waste Forms  

SciTech Connect (OSTI)

A joint project between the Oak Ridge National Laboratory (ORNL) and the Savannah River Technology Center (SRTC) has been established to evaluate vitrification as an option for the immobilization of waste within ORNL tank farms. This paper presents details of calculations based on current best available analyses of the Oak Ridge Tanks on the limits for waste loadings imposed by the waste acceptance criteria.

Harbour, J.R. [Westinghouse Savannah River Company, AIKEN, SC (United States); Andrews, M.K.

1998-07-01T23:59:59.000Z

139

An Effective Waste Management Process for Segregation and Disposal of Legacy Mixed Waste at Sandia National Laboratories/New Mexico  

SciTech Connect (OSTI)

Sandia National Laboratories/New Mexico (SNL/NM) is a research and development facility that generates many highly diverse, low-volume mixed waste streams. Under the Federal Facility Compliance Act, SNL/NM must treat its mixed waste in storage to meet the Land Disposal Restrictions treatment standards. Since 1989, approximately 70 cubic meters (2500 cubic feet) of heterogeneous, poorly characterized and inventoried mixed waste was placed in storage that could not be treated as specified in the SNL/NM Site Treatment Plan. A process was created to sort the legacy waste into sixteen well- defined, properly characterized, and precisely inventoried mixed waste streams (Treatability Groups) and two low-level waste streams ready for treatment or disposal. From June 1995 through September 1996, the entire volume of this stored mixed waste was sorted and inventoried through this process. This process was planned to meet the technical requirements of the sorting operation and to identify and address the hazards this operation presented. The operations were routinely adapted to safely and efficiently handle a variety of waste matrices, hazards, and radiological conditions. This flexibility was accomplished through administrative and physical controls integrated into the sorting operations. Many Department of Energy facilities are currently facing the prospect of sorting, characterizing, and treating a large inventory of mixed waste. The process described in this paper is a proven method for preparing a diverse, heterogeneous mixed waste volume into segregated, characterized, inventoried, and documented waste streams ready for treatment or disposal.

Hallman, Anne K. [Sandia National Labs., Albuquerque, NM (United States); Meyer, Dann [IT Corporation, Albuquerque, NM (United States); Rellergert, Carla A. [Roy F. Weston, Inc., Albuquerque, NM (United States); Schriner, Joseph A. [Automated Solutions of Albuquerque, Albuquerque, NM (United States)

1998-06-01T23:59:59.000Z

140

An effective waste management process for segregation and disposal of legacy mixed waste at Sandia National Laboratories/New Mexico  

SciTech Connect (OSTI)

Sandia National Laboratories/New Mexico (SNL/NM) is a research and development facility that generates many highly diverse, low-volume mixed waste streams. Under the Federal Facility Compliance Act, SNL/NM must treat its mixed waste in storage to meet the Land Disposal Restrictions treatment standards. Since 1989, approximately 70 cubic meters (2,500 cubic feet) of heterogeneous, poorly characterized and inventoried mixed waste was placed in storage that could not be treated as specified in the SNL/NM Site Treatment Plan. A process was created to sort the legacy waste into sixteen well-defined, properly characterized, and accurately inventoried mixed waste streams (Treatability Groups) and two low-level waste streams ready for treatment or disposal. From June 1995 through September 1996, the entire volume of this stored mixed waste was sorted and inventoried. This process was planned to meet the technical requirements of the sorting operation and to identify and address the hazards this operation presented. The operations were routinely adapted to safely and efficiently handle a variety of waste matrices, hazards, and radiological conditions. This flexibility was accomplished through administrative and physical controls integrated into the sorting operations. Many Department of Energy facilities are currently facing the prospect of sorting, characterizing, and treating a large inventory of mixed waste. The process described in this report is a proven method for preparing a diverse, heterogeneous mixed waste volume into segregated, characterized, inventoried, and documented waste streams ready for treatment or disposal.

Hallman, A.K. [Sandia National Labs., Albuquerque, NM (United States); Meyer, D. [IT Corp., Albuquerque, NM (United States); Rellergert, C.A. [Roy F. Weston, Inc., Albuquerque, NM (United States); Schriner, J.A. [Automated Solutions of Albuquerque, Inc., NM (United States)

1998-04-01T23:59:59.000Z

Note: This page contains sample records for the topic "legacy tru waste" 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

Sealion Database: Tracking and Characterization of Legacy Wastes  

SciTech Connect (OSTI)

The Radioactive Scrap and Waste Facility Liner-by-Liner Characterization Project was initiated to support waste management planning and disposition activities at the Materials and Fuels Complex located at the Idaho National Laboratory. The project scope consisted of a detailed examination of available historical records to consolidate information and eliminate discrepancies between sources. This information was captured in a new comprehensive searchable online database dubbed Sealion (Searchable Liner Online). For each storage liner and associated waste container, Sealion tracks the physical configuration, radiological data (e.g., source term, transuranic content, fissile content, and direct gamma radiation reading), Resource Conservation and Recovery Act characterization data, contents descriptions, and a variety of other waste management data. Historical hard-copy records were scanned and are stored in the database for easy access. In addition to storing the consolidated data in a library for easy retrieval or linking, Sealion serves as a tool in the development of batching plans for retrieving, transporting, processing, and, ultimately, dispositioning the waste. An integral search function allows the user to query for a variety of parameters in order to plan custom batches and account for facility or regulatory limitations (e.g., U.S. Department of Transportation limits, hazard category determinations, and fissile gram equivalent limitations). Liners can be combined or batched together and the combined results displayed in real-time graphs and tables showing the cumulative characteristics. The basic database architecture has proven to be adaptable to a variety of other similar applications. Sealion is capable of tracking segmented inventories (i.e., the liners can be replaced with storage drums, racks in a warehouse, or grids overlaid on a landfill). Additionally, the batching functions allow for the ability to combine inventory sub-locations into real-time graphs that summarize the characteristics of the contents for ease in comparison of characteristics to established thresholds or decision-making modeling needed to support waste-management operations.

Michel Hall; Brady Orchard; Brett Welty; James Rivera; Paul Walker; Reese Gannon

2010-03-01T23:59:59.000Z

142

DOE - Office of Legacy Management -- Waste Isolation Pilot Plant - 019  

Office of Legacy Management (LM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "ofEarlyEnergyDepartment ofDepartment ofof EnergyYou areDowntown Site -Miami - FL06TNWashingtonWaste

143

Dose potential of sludge contaminated and/or TRU contaminated waste in B-25s for tornado and straight wind events  

SciTech Connect (OSTI)

F and H Tank Farms generate supernate and sludge contaminated Low-Level Waste. The waste is collected, characterized, and packaged for disposal. Before the waste can be disposed of, however, it must be properly characterized. Since the radionuclide distribution in typical supernate is well known, its characterization is relatively straight forward and requires minimal effort. Non-routine waste, including potentially sludge contaminated, requires much more effort to effectively characterize. The radionuclide distribution must be determined. In some cases the waste can be contaminated by various sludge transfers with unique radionuclide distributions. In these cases, the characterization can require an extensive effort. Even after an extensive characterization effort, the container must still be prepared for shipping. Therefore a significant amount of time may elapse from the time the waste is generated until the time of disposal. During the time it is possible for a tornado or high wind scenario to occur. The purpose of this report is to determine the effect of a tornado on potential sludge contaminated waste, or Transuranic (TRU) waste in B-25s [large storage containers], to evaluate the potential impact on F and H Tank Farms, and to help establish a B-25 control program for tornado events.

Aponte, C.I.

2000-02-17T23:59:59.000Z

144

Transuranic Waste Program Framework Agreement - December Deliverable July 2012  

SciTech Connect (OSTI)

Framework agreement deliverables are: (1) 'DOE/NNSA commits to complete removal of all non-cemented above-ground EM Legacy TRU and newly generated TRU currently-stored at Area G as of October 1, 2011, by no later than June 30, 2014. This inventory of above-ground TRU is defined as 3706 cubic meters of material.' (2) 'DOE commits to the complete removal of all newly generated TRU received in Area G during FY 2012 and 2013 by no later than December 31, 2014.' (3) 'Based on projected funding profiles, DOE/NNSA will develop by December 31, 2012, a schedule, including pacing milestones, for disposition of the below-ground TRU requiring retrieval at Area G.' Objectives are to: (1) restore the 'Core Team' to develop the December, 2012 deliverable; (2) obtain agreement on the strategy for below ground water disposition; and (3) establish timeline for completion of the deliverable. Below Grade Waste Strategy is to: (1) Perform an evaluation on below grade waste currently considered retrievable TRU; (2) Only commit to retrieve waste that must be retrieved; (3) Develop the Deliverable including Pacing Milestones based on planned commitments; (4) Align all Regulatory Documents for Consistency; and (5) answer these 3 primary questions, is the waste TRU; is the waste retrievable, can retrieval cause more harm than benefit?

Jones, Patricia [Los Alamos National Laboratory

2012-07-19T23:59:59.000Z

145

TRU decontamination of high-level Purex waste by solvent extraction using a mixed octyl(phenyl)-N,N-diisobutyl-carbamoylmethylphosphine oxide/TBP/NPH (TRUEX) solvent  

SciTech Connect (OSTI)

The TRUEX (transuranium extraction) process was tested on a simulated high-level dissolved sludge waste (DSW). A batch counter-current extraction mode was used for seven extraction and three scrub stages. One additional extraction stage and two scrub stages and all strip stages were performed by batch extraction. The TRUEX solvent consisted of 0.20 M octyl(phenyl)-N,N-diisobutylcarbamoyl-methylphosphine oxide-1.4 M TBP in Conoco (C/sub 12/-C/sub 14/). The feed solution was 1.0 M in HNO/sub 3/, 0.3 M in H/sub 2/C/sub 2/O/sub 4/ and contained mixed (stable) fission products, U, Np, Pu, and Am, and a number of inert constituents, e.g., Fe and Al. The test showed that the process is capable of reducing the TRU concentration in the DSW by a factor of 4 x 10/sup 4/ (to <100 nCi/g of disposed form) and reducing the quantity of TRU waste by two orders of magnitude.

Horwitz, E.P.; Kalina, D.G.; Diamond, H.; Kaplan, L.; Vandegrift, G.F.; Leonard, R.A.; Steindler, M.J.; Schulz, W.W.

1984-01-01T23:59:59.000Z

146

Preliminary Study of Radioactive Waste Package Made of High-Strength and Ultra Low-Permeability Concrete for Geological Disposal of TRU Wastes  

SciTech Connect (OSTI)

We have been developing a radioactive waste package made of high-strength and ultra low-permeability concrete (HSULPC) for geological disposal of TRU wastes, which is expected to be much more impervious to water than conventional concrete. In this study, basic data for the HSULPC regarding its the impervious character and the thermodynamics during cement hydration were obtained through water permeability measurements using cold isostatic pressing (CIP) and adiabatic concrete hydration experiments, respectively. Then, a prediction tool to find concrete package construction conditions to avoid thermal cracking was developed, which could deal with coupled calculations of cement hydration, heat transfer, stress, and cracking. The developed tool was applied to HSULPC hydration on a small-scale cylindrical model to examine whether there was any effect on cracking which depended on the ratio of concrete cylinder thickness to its inner diameter. The results were compared to experiments. For concrete with a compressive strength of 200MPa, the water permeability coefficient was 4 x 10{sup 19} m/s. Dependences of activation energy and frequency factor on degree of cement hydration had a sharp peaking due to the nucleation rate-determining step, and a gradual increase region due to the diffusion rate-determining step. From analyses of the small-scale cylindrical model, dependences of the maximum principal stress on the radius were obtained. When the ratio of the concrete thickness to the heater diameter was around 1, the risk of cracking was predicted to be minimized. These numerical predictions from the developed tool were verified by experiments.

Matsuo, T.; Kawasaki, T.; Sakamoto, H.; Asano, E.; Takei, A.; Shibuya, K.; Katagiri, M.

2003-02-27T23:59:59.000Z

147

RH TRU Waste Program  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLas ConchasPassive Solar HomePromising Science for1 20115, 2001 Media Contact:REPORT OFMadison

148

UP2 400 High Activity Oxide Legacy Waste Retrieval Project Scope and Progress-13048  

SciTech Connect (OSTI)

The High Activity Oxide facility (HAO) reprocessed sheared and dissolved 4500 metric tons of light water reactor fuel the fuel of the emerging light water reactor spent fuel between 1976 and 1998. Over the period, approximately 2200 tons of process waste, composed primarily of sheared hulls, was produced and stored in a vast silo in the first place, and in canisters stored in pools in subsequent years. Upon shutdown of the facility, AREVA D and D Division in La Hague launched a thorough investigation and characterization of the silos and pools content, which then served as input data for the definition of a legacy waste retrieval and reconditioning program. Basic design was conducted between 2005 and 2007, and was followed by an optimization phase which lead to the definition of a final scenario and budget, 12% under the initial estimates. The scenario planned for the construction of a retrieval and reconditioning cell to be built on top of the storage silo. The retrieved waste would then be rinsed and sorted, so that hulls could subsequently be sent to La Hague high activity compacting facility, while resins and sludge would be cemented within the retrieval cell. Detailed design was conducted successfully from 2008 until 2011, while a thorough research and development program was conducted in order to qualify each stage of the retrieval and reconditioning process, and assist in the elaboration of the final waste package specification. This R and D program was defined and conducted as a response and mitigation of the major project risks identified during the basic design process. Procurement and site preparatory works were then launched in 2011. By the end of 2012, R and D is nearly completed, the retrieval and reconditioning process have been secured, the final waste package specification is being completed, the first equipment for the retrieval cell is being delivered on site, while preparation works are allowing to free up space above and around the silo, to allow for construction which is scheduled to being during the first semester of 2013. The elaboration of the final waste package is still undergoing and expected to be completed by then end of 2013, following some final elements of R and D required to demonstrate the full compatibility of the package with deep geological repository. The HAO legacy waste retrieval project is so far the largest such project entering operational phase on the site of La Hague. It is on schedule, under budget, and in conformity with the delivery requirements set by the French Safety Authority, as well as other stakeholders. This project paves the way for the successful completion of AREVA La Hague other legacy waste retrieval projects, which are currently being drafted or already in active R and D phase. (authors)

Chabeuf, Jean-Michel; Varet, Thierry [AREVA Site Value Development Business Unit, La Hague Site (France)] [AREVA Site Value Development Business Unit, La Hague Site (France)

2013-07-01T23:59:59.000Z

149

Transuranic contaminated waste form characterization and data base  

SciTech Connect (OSTI)

This volume contains 5 appendices. Title listing are: technologies for recovery of transuranics; nondestructive assay of TRU contaminated wastes; miscellaneous waste characteristics; acceptance criteria for TRU waste; and TRU waste treatment technologies.

Kniazewycz, B.G.; McArthur, W.C.

1980-07-01T23:59:59.000Z

150

Project plans for transuranic waste at small quantity sites in the Department of Energy comples-10522  

SciTech Connect (OSTI)

Los Alamos National Laboratory, Carlsbad Office (LANL-CO), has been tasked to write Project Plans for all of the Small Quantity Sites (SQS) with defense related Transuranic (TRU) waste in the Department of Energy (DOE) complex. Transuranic Work-Off Plans were precursors to the Project Plans. LANL-CO prepared a Work-Off Plan for each small quantity site. The Work-Off Plan that identified issues, drivers, schedules, and inventory. Eight sites have been chosen to deinventory their legacy TRU waste; Bettis Atomic Power Laboratory, General Electric-Vallecitos Nuclear Center, Lawrence Berkeley National Laboratory, Lawrence Livermore National Laboratory-Area 300, Nevada Test Site, Nuclear Radiation Development, Sandia National Laboratory, and the Separations Process Research Unit. Each plan was written for contact and/or remote handled waste if present at the site. These project plans will assist the small quantity sites to ship legacy TRU waste offsite and de-inventory the site of legacy TRU waste. The DOE is working very diligently to reduce the nuclear foot print in the United States. Each of the eight SQSs will be de-inventoried of legacy TRU waste during a campaign that ends September 2011. The small quantity sites have a fraction of the waste that large quantity sites possess. During this campaign, the small quantity sites will package all of the legacy TRU waste and ship to Idaho or directly to the Waste Isolation Pilot Plant (WIPP) in Carlsbad, New Mexico. The sites will then be removed from the Transuranic Waste Inventory if they are de-inventoried of all waste. Each Project Plan includes the respective site inventory report, schedules, resources, drivers and any issues. These project plans have been written by the difficult waste team and will be approved by each site. Team members have been assigned to each site to write site specific project plans. Once the project plans have been written, the difficult team members will visit the sites to ensure nothing has been overlooked and to verify the inventory. After each site has approved their project plan, the site will begin writing procedures and packaging/repackaging their waste. In some cases the sites have already begun the process. The waste will be shipped after all of the waste has been characterized and approved.

Mctaggart, Jerri Lynne [Los Alamos National Laboratory; Lott, Sheila [Los Alamos National Laboratory; Gadbury, Casey [DOE

2009-01-01T23:59:59.000Z

151

Mobile/Modular Deployment Project-Enhancing Efficiencies within the National Transuranic Waste Program.  

SciTech Connect (OSTI)

In 1999, the National Transuranic (TRU) Waste Program (NTP) achieved two significant milestones. First, the Waste Isolation Plant (WIPP) opened in March for the permanent disposal of TRU waste generated by, and temporarily stored at, various sites supporting the nation's defense programs. Second, the Hazardous Waste Facility Permit, issued by the New Mexico Environment Department, for WIPP became effective in November. While the opening of WIPP brought to closure a number of scientific, engineering, regulatory, and political challenges, achieving this major milestone led to a new set of challenges-how to achieve the Department of Energy's (DOE's) NTP end-state vision: All TRU waste from DOE sites scheduled for closure is removed All legacy TRU waste from DOE sites with an ongoing nuclear mission is disposed 0 All newly generated TRU waste is disposed as it is generated The goal is to operate the national TRU waste program safely, cost effectively, in compliance with applicable regulations and agreements, and at full capacity in a fully integrated mode. The existing schedule for TRU waste disposition would achieve the NTP vision in 2034 at an estimated life-cycle cost of $16B. The DOE's Carlsbad Field Office (CBFO) seeks to achieve this vision early-by at least 10 years- while saving the nation an estimated $48 to $6B. CBFO's approach is to optimize, or to make as functional as possible, TRU waste disposition. That is, to remove barriers that impede waste disposition, and increase the rate and cost efficiency of waste disposal at WIPP, while maintaining safety. The Mobile/Modular Deployment Project (MMDP) is the principal vehicle for implementing DOE's new commercial model of using best business practices of national authorization basis, standardization, and economies of scale to accelerate the completion of WIPP's mission. The MMDP is one of the cornerstones of the National TRU Waste System Optimization Project (1). The objective of the MMDP is to increase TRU waste shipment and disposal rates from currently certified sites as well as to provide a means to remove TRU waste from sites that have no characterization capability.

Triay, I. R. (Ines R.); Basabilvazo, G. B. (George B.); Countiss, S. (Sue); Moody, D. C. (David C.); Behrens, R. G. (Robert G.); Lott, S. A. (Sheila A.)

2002-01-01T23:59:59.000Z

152

Architectural Framework for Addressing Legacy Waste from the Cold War - 13611  

SciTech Connect (OSTI)

We present an architectural framework for the use of a hybrid simulation model of enterprise-wide operations used to develop system-level insight into the U.S. Department of Energy's (DOE) environmental cleanup of legacy nuclear waste at the Savannah River Site. We use this framework for quickly exploring policy and architectural options, analyzing plans, addressing management challenges and developing mitigation strategies for DOE Office of Environmental Management (EM). The socio-technical complexity of EM's mission compels the use of a qualitative approach to complement a more a quantitative discrete event modeling effort. We use this model-based analysis to pinpoint pressure and leverage points and develop a shared conceptual understanding of the problem space and platform for communication among stakeholders across the enterprise in a timely manner. This approach affords the opportunity to discuss problems using a unified conceptual perspective and is also general enough that it applies to a broad range of capital investment/production operations problems. (authors)

Love, Gregory A.; Glazner, Christopher G.; Steckley, Sam [The MITRE Corporation, 7515 Colshire Drive, McLean, VA 22102 (United States)] [The MITRE Corporation, 7515 Colshire Drive, McLean, VA 22102 (United States)

2013-07-01T23:59:59.000Z

153

High Hydrogen Concentrations Detected In The Underground Vaults For RH-TRU Waste At INEEL Compared With Calculated Values Using The INEEL-Developed Computer Code  

SciTech Connect (OSTI)

About 700 remote-handled transuranic (RH-TRU) waste drums are stored in about 144 underground vaults at the Intermediate-Level Transuranic Storage Facility at the Idaho National Environmental and Engineering Laboratory’s (INEEL’s) Radioactive Waste Management Complex (RWMC). These drums were shipped to the INEEL from 1976 through 1996. During recent monitoring, concentrations of hydrogen were found to be in excess of lower explosive limits. The hydrogen concentration in one vault was detected to be as high as 18% (by volume). This condition required evaluation of the safety basis for the facility. The INEEL has developed a computer program to estimate the hydrogen gas generation as a function of time and diffusion through a series of layers (volumes), with a maximum five layers plus a sink/environment. The program solves the first-order diffusion equations as a function of time. The current version of the code is more flexible in terms of user input. The program allows the user to estimate hydrogen concentrations in the different layers of a configuration and then change the configuration after a given time; e.g.; installation of a filter on an unvented drum or placed in a vault or in a shipping cask. The code has been used to predict vault concentrations and to identify potential problems during retrieval and aboveground storage. The code has generally predicted higher hydrogen concentrations than the measured values, particularly for the drums older than 20 year, which could be due to uncertainty and conservative assumptions in drum age, heat generation rate, hydrogen generation rate, Geff, and diffusion rates through the layers.

Rajiv Bhatt; Soli Khericha

2005-02-01T23:59:59.000Z

154

Accelerating the disposition of transuranic waste from LANL - 9495  

SciTech Connect (OSTI)

Los Alamos National Laboratory (LANL) was established during World War II with a single mission -- to design and build an atomic bomb. In the 65 years since, nuclear weapons physics, design and engineering have been the Laboratory's primary and sustaining mission. Experimental and process operations -- and associated cleanout and upgrade activities -- have generated a significant inventory of transuranic (TRU) waste that is stored at LANL's Technical Area 54, Material Disposal Area G (MDA G). When the Waste Isolation Pilot Plant (WIPP) opened its doors in 1999, LANL's TRU inventory totaled about 10,200 m{sup 3}, with a plutonium 239-equivalent curie (PE Ci) content of approximately 250,000 curies. By December 2008, a total of about 2,300 m3 (61,000 PE Ci) had been shipped to WIPP from LANL. This has resulted in a net reduction of about 1,000 m{sup 3} of TRU inventory over that time frame. This paper presents progress in dispositioning legacy and newly-generated transuranic waste (TRU) from ongoing missions at the LANL. The plans for, and lessons learned, in dispositioning several hundred high-activity TRU waste drums are reviewed. This waste population was one of the highest risks at LANL. Technical challenges in disposition of the high-activity drums are presented. These provide a preview of challenges to be addressed in dispositioning the remaining 6,800 m{sup 3} of TRU stored above ground and 2,400 m{sup 3} of TRU waste that is 'retrievably' stored below-grade. LANL is using subcontractors for much of this work and has formed a strong partnership with WIPP and its contractor to address this cleanup challenge.

Shepard, Mark D [Los Alamos National Laboratory; Stiger, Susan G [Los Alamos National Laboratory; Blankenhorn, James A [Los Alamos National Laboratory; Rael, George J [Los Alamos National Laboratory; Moody, David C [U.S DOE

2009-01-01T23:59:59.000Z

155

Department of Energy Idaho Operations Office evaluation of feasibility studies for private sector treatment of alpha and TRU mixed wastes  

SciTech Connect (OSTI)

The Idaho National Engineering Laboratory (INEL) is currently storing a large quantity of alpha contaminated mixed low level waste which will require treatment prior to disposal. The DOE Idaho Operations Office (DOE-ID) recognized that current knowledge and funding were insufficient to directly pursue services for the requisite treatment. Therefore, it was decided that private sector studies would be funded to clarify cost, regulatory, technology, and contractual issues associated with procuring treatment services. This report analyzes the three private sector studies procured and recommends a path forward for DOE in procuring retrieval, assay, characterization, and treatment services for INEL transuranic and alpha contaminated mixed low level waste. This report was prepared by a team of subject matter experts from the INEL referred to as the DOE-ID Evaluation Team.

NONE

1995-05-01T23:59:59.000Z

156

Transuranic Waste Burning Potential of Thorium Fuel in a Fast Reactor - 12423  

SciTech Connect (OSTI)

Westinghouse Electric Company (referred to as 'Westinghouse' in the rest of this paper) is proposing a 'back-to-front' approach to overcome the stalemate on nuclear waste management in the US. In this approach, requirements to further the societal acceptance of nuclear waste are such that the ultimate health hazard resulting from the waste package is 'as low as reasonably achievable'. Societal acceptability of nuclear waste can be enhanced by reducing the long-term radiotoxicity of the waste, which is currently driven primarily by the protracted radiotoxicity of the transuranic (TRU) isotopes. Therefore, a transition to a more benign radioactive waste can be accomplished by a fuel cycle capable of consuming the stockpile of TRU 'legacy' waste contained in the LWR Used Nuclear Fuel (UNF) while generating waste which is significantly less radio-toxic than that produced by the current open U-based fuel cycle (once through and variations thereof). Investigation of a fast reactor (FR) operating on a thorium-based fuel cycle, as opposed to the traditional uranium-based is performed. Due to a combination between its neutronic properties and its low position in the actinide chain, thorium not only burns the legacy TRU waste, but it does so with a minimal production of 'new' TRUs. The effectiveness of a thorium-based fast reactor to burn legacy TRU and its flexibility to incorporate various fuels and recycle schemes according to the evolving needs of the transmutation scenario have been investigated. Specifically, the potential for a high TRU burning rate, high U-233 generation rate if so desired and low concurrent production of TRU have been used as metrics for the examined cycles. Core physics simulations of a fast reactor core running on thorium-based fuels and burning an external TRU feed supply have been carried out over multiple cycles of irradiation, separation and reprocessing. The TRU burning capability as well as the core isotopic content have been characterized. Results will be presented showing the potential for thorium to reach a high TRU transmutation rate over a wide variety of fuel types (oxide, metal, nitride and carbide) and transmutation schemes (recycle or partition of in-bred U-233). In addition, a sustainable scheme has been devised to burn the TRU accumulated in the core inventory once the legacy TRU supply has been exhausted, thereby achieving long-term virtually TRU-free. A comprehensive 'back-to-front' approach to the fuel cycle has recently been proposed by Westinghouse which emphasizes achieving 'acceptable', low-radiotoxicity, high-level waste, with the intent not only to satisfy all technical constraints but also to improve public acceptance of nuclear energy. Following this approach, the thorium fuel cycle, due to its low radiotoxicity and high potential for TRU transmutation has been selected as a promising solution. Additional studies not shown here have shown significant reduction of decay heat. The TRU burning potential of the Th-based fuel cycle has been illustrated with a variety of fuel types, using the Toshiba ARR to perform the analysis, including scenarios with continued LWR operation of either uranium fueled or thorium fueled LWRs. These scenarios will afford overall reduction in actinide radiotoxicity, however when the TRU supply is exhausted, a continued U- 235 LWR operation must be assumed to provide TRU makeup feed. This scenario will never reach the characteristically low TRU content of a closed thorium fuel cycle with its associated potential benefits on waste radiotoxicity, as exemplified by the transition scenario studied. At present, the cases studied indicate ThC as a potential fuel for maximizing TRU burning, while ThN with nitrogen enriched to 95% N-15 shows the highest breeding potential. As a result, a transition scenario with ThN was developed to show that a sustainable, closed Th-cycle can be achieved starting from burning the legacy TRU stock and completing the transmutation of the residual TRU remaining in the core inventory after the legacy TRU external supply has been

Wenner, Michael; Franceschini, Fausto; Ferroni, Paolo [Westinghouse Electric Company LLC,Cranberry Township, PA, 16066 (United States); Sartori, Alberto; Ricotti, Marco [Politecnico di Milano, Milan (Italy)

2012-07-01T23:59:59.000Z

157

Potential VOC Deflagrations in a Vented TRU Drum  

SciTech Connect (OSTI)

The objective of the analysis is to examine the potential for lid ejection from a vented transuranic (TRU) waste drum due to pressure buildup caused by the deflagration of hydrogen and volatile organic compounds (VOCs) inside the drum. In this analysis, the AICC pressure for a stoichiometric mixture of VOCs is calculated and then compared against the experimental peak pressure of stoichiometric combustion of propane and hexane in a combustion chamber. The experimental peak pressures of propane and hexane are about 12 percent lower than the calculated AICC pressure. Additional losses in the drum are calculated due to venting of the gases, drum bulging, waste compaction, and heat losses from the presence of waste in the drum. After accounting for these losses, the final pressures are compared to the minimum observed pressure that ejects the lid from a TRU drum. The ejection pressure of 105 psig is derived from data that was recorded for a series of tests where hydrogen-air mixtures were ignited inside sealed TRU drums. Since the calculated pressures are below the minimum lid ejection pressure, none of the VOCs and the hydrogen (up to 4 percent) mixtures present in the TRU waste drum is expected to cause lid ejection if ignited. The analysis of potential VOC deflagrations in a vented TRU drum can be applied across the DOE-Complex since TRU waste is stored in drums throughout the complex.

Mukesh, GUPTA

2005-04-07T23:59:59.000Z

158

EIS-0305: Treating Transuranic (TRU)/Alpha Low-Level at the Oak Ridge National Laboratory, Oak Ridge, Tennessee  

Broader source: Energy.gov [DOE]

Treating Transuranic (TRU)/Alpha Low-Level Waste at the Oak Ridge National Laboratory, Oak Ridge, Tennessee)This EIS evaluates DOE's proposal to construct, operate, and decontaminate/decommission a Transuranic (TRU) Waste Treatment Facility in Oak Ridge, Tennessee. The four waste types that would be treated at the proposed facility would be remote-handled TRU mixed waste sludge, liquid low-level waste associated with the sludge, contact-handled TRU/alpha low-level waste solids, and remote-handled TRU/alpha low-level waste solids. The mixed waste sludge and some of the solid waste contain metals regulated under the Resource Conservation and Recovery Act and may be classified as mixed waste.

159

A Robust Power Remote Manipulator for Use in Waste Sorting, Processing, and Packaging - 12158  

SciTech Connect (OSTI)

Disposition of radioactive waste is one of the Department of Energy's (DOE's) highest priorities. A critical component of the waste disposition strategy is shipment of Transuranic (TRU) waste from DOE's Oak Ridge Reservation to the Waste Isolation Plant Project (WIPP) in Carlsbad, New Mexico. This is the mission of the DOE TRU Waste Processing Center (TWPC). The remote-handled TRU waste at the Oak Ridge Reservation is currently in a mixed waste form that must be repackaged in to meet WIPP Waste Acceptance Criteria (WAC). Because this remote-handled legacy waste is very diverse, sorting, size reducing, and packaging will require equipment flexibility and strength that is not possible with standard master-slave manipulators. To perform the wide range of tasks necessary with such diverse, highly contaminated material, TWPC worked with S.A. Technology (SAT) to modify SAT's Power Remote Manipulator (PRM) technology to provide the processing center with an added degree of dexterity and high load handling capability inside its shielded cells. TWPC and SAT incorporated innovative technologies into the PRM design to better suit the operations required at TWPC, and to increase the overall capability of the PRM system. Improving on an already proven PRM system will ensure that TWPC gains the capabilities necessary to efficiently complete its TRU waste disposition mission. The collaborative effort between TWPC and S.A. Technology has yielded an extremely capable and robust solution to perform the wide range of tasks necessary to repackage TRU waste containers at TWPC. Incorporating innovative technologies into a proven manipulator system, these PRMs are expected to be an important addition to the capabilities available to shielded cell operators. The PRMs provide operators with the ability to reach anywhere in the cell, lift heavy objects, perform size reduction associated with the disposition of noncompliant waste. Factory acceptance testing of the TWPC Powered Remote Manipulators has completed at SAT's Colorado facility, and on-site training at TWPC is scheduled to start in early 2012. (authors)

Cole, Matt; Martin, Scott [S.A. Technology, Loveland, Colorado 80537, Transuranic Waste Processing Center, Lenoir City, TN 37771 (United States)

2012-07-01T23:59:59.000Z

160

Management of Legacy Spent Nuclear Fuel Wastes at the Chalk River Laboratories: The Challenges and Innovative Solutions Implemented - 13301  

SciTech Connect (OSTI)

AECL's Fuel Packaging and Storage (FPS) Project was initiated in 2004 to retrieve, transfer, and stabilize an identified inventory of degraded research reactor fuel that had been emplaced within in-ground 'Tile Hole' structures in Chalk River Laboratories' Waste Management Area in the 1950's and 60's. Ongoing monitoring of the legacy fuel storage conditions had identified that moisture present in the storage structures had contributed to corrosion of both the fuel and the storage containers. This prompted the initiation of the FPS Project which has as its objective to design, construct, and commission equipment and systems that would allow for the ongoing safe storage of this fuel until a final long-term management, or disposition, pathway was available. The FPS Project provides systems and technologies to retrieve and transfer the fuel from the Waste Management Area to a new facility that will repackage, dry, safely store and monitor the fuel for a period of 50 years. All equipment and the new storage facility are designed and constructed to meet the requirements for Class 1 Nuclear Facilities in Canada. (authors)

Schruder, Kristan [Atomic Energy of Canada Limited - Chalk River Laboratories, Chalk River, Ontario (Canada)] [Atomic Energy of Canada Limited - Chalk River Laboratories, Chalk River, Ontario (Canada); Goodwin, Derek [Rolls-Royce Civil Nuclear Canada Limited, 678 Neal Dr., Peterborough, Ontario (Canada)] [Rolls-Royce Civil Nuclear Canada Limited, 678 Neal Dr., Peterborough, Ontario (Canada)

2013-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "legacy tru waste" 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.


161

TRU drum corrosion task team report  

SciTech Connect (OSTI)

During routine inspections in March 1996, transuranic (TRU) waste drums stored at the Radioactive Waste Management Complex (RWMC) were found with pinholes and leaking fluid. These drums were overpacked, and further inspection discovered over 200 drums with similar corrosion. A task team was assigned to investigate the problem with four specific objectives: to identify any other drums in RWMC TRU storage with pinhole corrosion; to evaluate the adequacy of the RWMC inspection process; to determine the precise mechanism(s) generating the pinhole drum corrosion; and to assess the implications of this event for WIPP certifiability of waste drums. The task team investigations analyzed the source of the pinholes to be Hcl-induced localized pitting corrosion. Hcl formation is directly related to the polychlorinated hydrocarbon volatile organic compounds (VOCs) in the waste. Most of the drums showing pinhole corrosion are from Content Code-003 (CC-003) because they contain the highest amounts of polychlorinated VOCs as determined by headspace gas analysis. CC-001 drums represent the only other content code with a significant number of pinhole corrosion drums because their headspace gas VOC content, although significantly less than CC-003, is far greater than that of the other content codes. The exact mechanisms of Hcl formation could not be determined, but radiolytic and reductive dechlorination and direct reduction of halocarbons were analyzed as the likely operable reactions. The team considered the entire range of feasible options, ranked and prioritized the alternatives, and recommended the optimal solution that maximizes protection of worker and public safety while minimizing impacts on RWMC and TRU program operations.

Kooda, K.E.; Lavery, C.A.; Zeek, D.P.

1996-05-01T23:59:59.000Z

162

WASTE MANAGEMENT AT SRS - MAKING IT HAPPEN  

SciTech Connect (OSTI)

The past five years have witnessed a remarkable transition in the pace and scope of waste management activities at SRS. At the start of the new M&O contract in 1996, little was being done with the waste generated at the site apart from storing it in readiness for future treatment and disposal. Large volumes of legacy waste, particularly TRU and Low Level Waste, had accumulated over many years of operation of the site's nuclear facilities, and the backlog was increasing. WSRC proposed the use of the talents of the ''best in class'' partners for the new contract which, together with a more commercial approach, was expected to deliver more results without a concomitant increase in cost. This paper charts the successes in the Solid Waste arena and analyzes the basis for success.

Heenan, T. F.; Kelly, S.

2002-02-25T23:59:59.000Z

163

Westinghouse TRU Solutions Launches New Web Site  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear SecurityTensile Strain Switched FerromagnetismWaste and MaterialsWenjun DengWISP Sign In About |SelectsForTRU

164

Contact-Handled and Remote-Handled Transuranic Waste Packaging  

Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

Provides specific instructions for packaging and/or repackaging contact-handled transuranic (CH-TRU) and remote-handled transuranic (RH-TRU) waste in a manner consistent with DOE O 435.1, Radioactive Waste Management, DOE M 435.1-1 Chg 1, Radioactive Waste Management Manual, CH-TRU and RH-TRU waste transportation requirements, and Waste Isolation Pilot Plant (WIPP) programmatic requirements. Does not cancel other directives.

2011-08-09T23:59:59.000Z

165

Nevada Test Site Perspective on Characterization and Loading of Legacy Transuranic Drums Utilizing the Central Characterization Project  

SciTech Connect (OSTI)

The Nevada Test Site (NTS) has successfully completed a multi-year effort to characterize and ship 1860 legacy transuranic (TRU) waste drums for disposal at the Waste Isolation Pilot Plant (WIPP), a permanent TRU disposal site. This has been a cooperative effort among the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO), the U.S. Department of Energy, Carlsbad Field Office (DOE/CBFO), the NTS Management and Operations (M&O) contractor Bechtel Nevada (BN), and various contractors under the Central Characterization Project (CCP) umbrella. The success is due primarily to the diligence, perseverance, and hard work of each of the contractors, the DOE/CBFO, and NNSA/NSO, along with the support of the U.S. Department of Energy, Headquarters (DOE/HQ). This paper presents, from an NTS perspective, the challenges and successes of utilizing the CCP for obtaining a certified characterization program, sharing responsibilities for characterization, data validation, and loading of TRU waste with BN to achieve disposal at WIPP from a Small Quantity Site (SQS) such as the NTS. The challenges in this effort arose from two general sources. First, the arrangement of DOE/CBFO contractors under the CCP performing work and certifying waste at the NTS within a Hazard Category 2 (HazCat 2) non-reactor nuclear facility operated by BN, presented difficult challenges. The nuclear safety authorization basis, safety liability and responsibility, conduct of operations, allocation and scheduling of resources, and other issues were particularly demanding. The program-level and field coordination needed for the closely interrelated characterization tasks was extensive and required considerable effort by all parties. The second source of challenge was the legacy waste itself. None of the waste was generated at the NTS. The waste was generated at Lawrence Livermore National Laboratory (LLNL), Lawrence Berkeley Laboratory (LBL), Lynchburg, Rocky Flats Environmental Technology Site (RFETS), and a variety of other sites over 20 years ago, making the development of Acceptable Knowledge a significant and problematic effort. In addition, the characterization requirements, and data quality objectives for shipment and WIPP disposal today, were non-existent when this waste was generated, resulting in real-time adjustments to unexpected conditions.

R.G. Lahoud; J. F. Norton; I. L. Siddoway; L. W. Griswold

2006-01-01T23:59:59.000Z

166

Acceptable Knowledge Summary Report for Mixed TRU Waste Streams: SR-W026-221F-HET-A through D  

SciTech Connect (OSTI)

This document, along with referenced supporting documents provides a defensible and auditable record of acceptable knowledge for the heterogeneous debris mixed transuranic waste streams generated in the FB-Line after January 25, 1990 and before March 20, 1997.

Lunsford, G.F.

2001-10-02T23:59:59.000Z

167

Repository disposal requirements for commercial transuranic wastes (generated without reprocessing)  

SciTech Connect (OSTI)

This report forms a preliminary planning basis for disposal of commercial transuranic (TRU) wastes in a geologic repository. Because of the unlikely prospects for commercial spent nuclear fuel reprocessing in the near-term, this report focuses on TRU wastes generated in a once-through nuclear fuel cycle. The four main objectives of this study were to: develop estimates of the current inventories, projected generation rates, and characteristics of commercial TRU wastes; develop proposed acceptance requirements for TRU wastes forms and waste canisters that ensure a safe and effective disposal system; develop certification procedures and processing requirements that ensure that TRU wastes delivered to a repository for disposal meet all applicable waste acceptance requirements; and identify alternative conceptual strategies for treatment and certification of commercial TRU first objective was accomplished through a survey of commercial producers of TRU wastes. The TRU waste acceptance and certification requirements that were developed were based on regulatory requirements, information in the literature, and from similar requirements already established for disposal of defense TRU wastes in the Waste Isolation Pilot Plant (WIPP) which were adapted, where necessary, to disposal of commercial TRU wastes. The results of the TRU waste-producer survey indicated that there were a relatively large number of producers of small quantities of TRU wastes.

Daling, P.M.; Ludwick, J.D.; Mellinger, G.B.; McKee, R.W.

1986-06-01T23:59:59.000Z

168

Unresolved issues for the disposal of remote-handled transuranic waste in the Waste Isolation Pilot Plant  

SciTech Connect (OSTI)

The purpose of the Waste Isolation Pilot Plant (WIPP) is to dispose of 176,000 cubic meters of transuranic (TRU) waste generated by the defense activities of the US Government. The envisioned inventory contains approximately 6 million cubic feet of contact-handled transuranic (CH TRU) waste and 250,000 cubic feet of remote handled transuranic (RH TRU) waste. CH TRU emits less than 0.2 rem/hr at the container surface. Of the 250,000 cubic feet of RH TRU waste, 5% by volume can emit up to 1,000 rem/hr at the container surface. The remainder of RH TRU waste must emit less than 100 rem/hr. These are major unresolved problems with the intended disposal of RH TRU waste in the WIPP. (1) The WIPP design requires the canisters of RH TRU waste to be emplaced in the walls (ribs) of each repository room. Each room will then be filled with drums of CH TRU waste. However, the RH TRU waste will not be available for shipment and disposal until after several rooms have already been filled with drums of CH TRU waste. RH TRU disposal capacity will be loss for each room that is first filled with CH TRU waste. (2) Complete RH TRU waste characterization data will not be available for performance assessment because the facilities needed for waste handling, waste treatment, waste packaging, and waste characterization do not yet exist. (3) The DOE does not have a transportation cask for RH TRU waste certified by the US Nuclear Regulatory Commission (NRC). These issues are discussed along with possible solutions and consequences from these solutions. 46 refs.

Silva, M.K.; Neill, R.H.

1994-09-01T23:59:59.000Z

169

GEANT4 Simulation of a Scintillating-Fibre Tracker for the Cosmic-ray Muon Tomography of Legacy Nuclear Waste Containers  

E-Print Network [OSTI]

Cosmic-ray muons are highly penetrative charged particles that are observed at sea level with a flux of approximately one per square centimetre per minute. They interact with matter primarily through Coulomb scattering, which is exploited in the field of muon tomography to image shielded objects in a wide range of applications. In this paper, simulation studies are presented that assess the feasibility of a scintillating-fibre tracker system for use in the identification and characterisation of nuclear materials stored within industrial legacy waste containers. A system consisting of a pair of tracking modules above and a pair below the volume to be assayed is simulated within the GEANT4 framework using a range of potential fibre pitches and module separations. Each module comprises two orthogonal planes of fibres that allow the reconstruction of the initial and Coulomb-scattered muon trajectories. A likelihood-based image reconstruction algorithm has been developed that allows the container content to be det...

Clarkson, Anthony; Hoek, Matthias; Ireland, David G; Johnstone, Russell; Kaiser, Ralf; Keri, Tibor; Lumsden, Scott; Mahon, David F; McKinnon, Bryan; Murray, Morgan; Nutbeam-Tuffs, Sian; Shearer, Craig; Staines, Cassie; Yang, Guangliang; Zimmerman, Colin

2013-01-01T23:59:59.000Z

170

The Design and Performance of a Scintillating-Fibre Tracker for the Cosmic-ray Muon Tomography of Legacy Nuclear Waste Containers  

E-Print Network [OSTI]

Tomographic imaging techniques using the Coulomb scattering of cosmic-ray muons are increasingly being exploited for the non-destructive assay of shielded containers in a wide range of applications. One such application is the characterisation of legacy nuclear waste materials stored within industrial containers. The design, assembly and performance of a prototype muon tomography system developed for this purpose are detailed in this work. This muon tracker comprises four detection modules, each containing orthogonal layers of Saint-Gobain BCF-10 2mm-pitch plastic scintillating fibres. Identification of the two struck fibres per module allows the reconstruction of the incoming and Coulomb-scattered muon trajectories. These allow the container content, with respect to the atomic number Z of the scattering material, to be determined through reconstruction of the scattering location and magnitude. On each detection layer, the light emitted by the fibre is detected by a single Hamamatsu H8500 MAPMT with two fibre...

Clarkson, Anthony; Hoek, Matthias; Ireland, David G; Johnstone, Russell; Kaiser, Ralf; Keri, Tibor; Lumsden, Scott; Mahon, David F; McKinnon, Bryan; Murray, Morgan; Nutbeam-Tuffs, Sian; Shearer, Craig; Staines, Cassie; Yang, Guangliang; Zimmerman, Colin

2013-01-01T23:59:59.000Z

171

Solid waste retrieval. Phase 1, Operational basis  

SciTech Connect (OSTI)

This Document describes the operational requirements, procedures, and options for execution of the retrieval of the waste containers placed in buried storage in Burial Ground 218W-4C, Trench 04 as TRU waste or suspect TRU waste under the activity levels defining this waste in effect at the time of placement. Trench 04 in Burial Ground 218W-4C is totally dedicated to storage of retrievable TRU waste containers or retrievable suspect TRU waste containers and has not been used for any other purpose.

Johnson, D.M.

1994-09-30T23:59:59.000Z

172

EA-0981: Solid Waste Retrieval Complex, Enhanced Radioactive and Mixed Waste Storage Facility, Infrastructure Upgrades, and Central Waste Support Complex, Hanford Site, Richland, Washington  

Broader source: Energy.gov [DOE]

This EA evaluates the environmental impacts of the proposal to retrieve transuranic waste (TRU), provide storage capacity for retrieved and newly generated TRU, Greater-than-Category 3, and mixed...

173

Improvements in Hanford TRU Program Utilizing Systems Modeling and Analyses  

SciTech Connect (OSTI)

Hanford's Transuranic (TRU) Program is responsible for certifying contact-handled (CH) TRU waste and shipping the certified waste to the Waste Isolation Pilot Plant (WIPP). Hanford's CH TRU waste includes material that is in retrievable storage as well as above ground storage, and newly generated waste. Certifying a typical container entails retrieving and then characterizing it (Non-Destructive Examination [NDE], Non-Destructive Assay [NDA], and Head Space Gas Sampling [HSG]), validating records (data review and reconciliation), and designating the container for a payload. The certified payload is then shipped to WIPP. Systems modeling and analysis techniques were applied to Hanford's TRU Program to help streamline the certification process and increase shipping rates. The modeling and analysis yields several benefits: - Maintains visibility on system performance and predicts downstream consequences of production issues. - Predicts future system performance with higher confidence, based on tracking past performance. - Applies speculation analyses to determine the impact of proposed changes (e.g., apparent shortage of feed should not be used as basis to reassign personnel if more feed is coming in the queue). - Positively identifies the appropriate queue for all containers (e.g., discovered several containers that were not actively being worked because they were in the wrong 'physical' location - method used previously for queuing up containers). - Identifies anomalies with the various data systems used to track inventory (e.g., dimensional differences for Standard Waste Boxes). A model of the TRU Program certification process was created using custom queries of the multiple databases for managing waste containers. The model was developed using a simplified process chart based on the expected path for a typical container. The process chart was augmented with the remediation path for containers that do not meet acceptance criteria for WIPP. Containers are sorted into queues based on their current status in the process. A container can be in only one queue at any given time. Existing data systems are queried to establish the quantity of containers in each queue on any given day. This sets the amount of feed available that is then modeled to be processed according to the daily production plans. The daily production plans were created by identifying the equipment necessary and the staff that performs each process step, and determining the expected production rate for each step. Production performance is monitored on a weekly basis with Project senior staff to establish a total operating efficiency (TOE) for each step (comparing actual performance to production capacity). The unit operations were modeled to be constrained by each day's feed queue plus the performance of the preceding step. The TOE for each unit operation was applied to an integrated model to determine bottlenecks and identify areas for improvement. All of the steps were linked to predict future system performance based on available feed and integrated system-level TOE. It has been determined that at times sub-optimization of a particular unit operation is necessary to ensure the system remains balanced (e.g., having excess capacity in assay does no good if there is no feed available because the real-time radiography [RTR] is working at half capacity). Several recommendations have been provided to the Project management team resulting in improvements in the performance of TRU certification activities by Hanford's TRU Program. (authors)

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

2008-07-01T23:59:59.000Z

174

A Novel Fuel/Reactor Cycle to Implement the 300 Years Nuclear Waste Policy Approach - 12377  

SciTech Connect (OSTI)

A thorium-based fuel cycle system can effectively burn the currently accumulated commercial used nuclear fuel and move to a sustainable equilibrium where the actinide levels in the high level waste are low enough to yield a radiotoxicity after 300 years lower than that of the equivalent uranium ore. The second step of the Westinghouse approach to solving the waste 'problem' has been completed. The thorium fuel cycle has indeed the potential of burning the legacy TRU and achieve the waste objective proposed. Initial evaluations have been started for the third step, development and selection of appropriate reactors. Indications are that the probability of show-stoppers is rather remote. It is, therefore, believed that development of the thorium cycle and associated technologies will provide a permanent solution to the waste management. Westinghouse is open to the widest collaboration to make this a reality. (authors)

Carelli, M.D.; Franceschini, F.; Lahoda, E.J. [Westinghouse Electric Company LLC., Cranberry Township, PA (United States); Petrovic, B. [Georgia Institute of Technology, Atlanta, GA (United States)

2012-07-01T23:59:59.000Z

175

LANL sets TRU waste hauling record  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsruc DocumentationP-SeriesFlickrinformationPostdocs &Jeff Yarbrough joins LosPost-Recoverysets

176

IPP RH-TRU Waste Study - Summary  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation ProposedUsingFun withconfinementEtching. | EMSLthe U.S.;2c JeffersonDelegateSummary This

177

Transuranic (TRU) Waste | Department of Energy  

Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Delicious Rank EERE:YearRound-Up from theDepartment of EnergyThe SunMelissa HowellTechnologies »Transportation

178

Transportation Refrigeration Unit (TRU) Retrofit with HUSS Active...  

Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

Transportation Refrigeration Unit (TRU) Retrofit with HUSS Active Diesel Particulate Filters Transportation Refrigeration Unit (TRU) Retrofit with HUSS Active Diesel Particulate...

179

CRAD, Conduct of Operations - Oak Ridge National Laboratory TRU...  

Broader source: Energy.gov (indexed) [DOE]

Conduct of Operations - Oak Ridge National Laboratory TRU ALPHA LLWT Project CRAD, Conduct of Operations - Oak Ridge National Laboratory TRU ALPHA LLWT Project November 2003 A...

180

CRAD, Radiological Controls - Oak Ridge National Laboratory TRU...  

Broader source: Energy.gov (indexed) [DOE]

Radiological Controls - Oak Ridge National Laboratory TRU ALPHA LLWT Project CRAD, Radiological Controls - Oak Ridge National Laboratory TRU ALPHA LLWT Project November 2003 A...

Note: This page contains sample records for the topic "legacy tru waste" 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.


181

CRAD, Safety Basis - Oak Ridge National Laboratory TRU ALPHA...  

Broader source: Energy.gov (indexed) [DOE]

Safety Basis - Oak Ridge National Laboratory TRU ALPHA LLWT Project CRAD, Safety Basis - Oak Ridge National Laboratory TRU ALPHA LLWT Project November 2003 A section of Appendix C...

182

CRAD, Quality Assurance - Oak Ridge National Laboratory TRU ALPHA...  

Broader source: Energy.gov (indexed) [DOE]

Quality Assurance - Oak Ridge National Laboratory TRU ALPHA LLWT Project CRAD, Quality Assurance - Oak Ridge National Laboratory TRU ALPHA LLWT Project November 2003 A section of...

183

CRAD, Management - Oak Ridge National Laboratory TRU ALPHA LLWT...  

Broader source: Energy.gov (indexed) [DOE]

Management - Oak Ridge National Laboratory TRU ALPHA LLWT Project CRAD, Management - Oak Ridge National Laboratory TRU ALPHA LLWT Project November 2003 A section of Appendix C to...

184

CH-TRU Content Codes (CH-TRUCON)  

SciTech Connect (OSTI)

The CH-TRU Waste Content Codes (CH-TRUCON) document describes the inventory of the U.S. Department of Energy (DOE) CH-TRU waste within the transportation parameters specified by the Contact-Handled Transuranic Waste Authorized Methods for Payload Control (CH-TRAMPAC). The CH-TRAMPAC defines the allowable payload for the Transuranic Package Transporter-II (TRUPACT-II) and HalfPACT packagings. This document is a catalog of TRUPACT-II and HalfPACT authorized contents and a description of the methods utilized to demonstrate compliance with the CH-TRAMPAC. A summary of currently approved content codes by site is presented in Table 1. The CH-TRAMPAC describes "shipping categories" that are assigned to each payload container. Multiple shipping categories may be assigned to a single content code. A summary of approved content codes and corresponding shipping categories is provided in Table 2, which consists of Tables 2A, 2B, and 2C. Table 2A provides a summary of approved content codes and corresponding shipping categories for the "General Case," which reflects the assumption of a 60-day shipping period as described in the CH-TRAMPAC and Appendix 3.4 of the CH-TRU Payload Appendices. For shipments to be completed within an approximately 1,000-mile radius, a shorter shipping period of 20 days is applicable as described in the CH-TRAMPAC and Appendix 3.5 of the CH-TRU Payload Appendices. For shipments to WIPP from Los Alamos National Laboratory (LANL), Nevada Test Site, and Rocky Flats Environmental Technology Site, a 20-day shipping period is applicable. Table 2B provides a summary of approved content codes and corresponding shipping categories for "Close-Proximity Shipments" (20-day shipping period). For shipments implementing the controls specified in the CH-TRAMPAC and Appendix 3.6 of the CH-TRU Payload Appendices, a 10-day shipping period is applicable. Table 2C provides a summary of approved content codes and corresponding shipping categories for "Controlled Shipments" (10-day shipping period).

Washington TRU Solutions LLC

2005-10-15T23:59:59.000Z

185

GEANT4 Simulation of a Scintillating-Fibre Tracker for the Cosmic-ray Muon Tomography of Legacy Nuclear Waste Containers  

E-Print Network [OSTI]

Cosmic-ray muons are highly penetrative charged particles that are observed at sea level with a flux of approximately one per square centimetre per minute. They interact with matter primarily through Coulomb scattering, which is exploited in the field of muon tomography to image shielded objects in a wide range of applications. In this paper, simulation studies are presented that assess the feasibility of a scintillating-fibre tracker system for use in the identification and characterisation of nuclear materials stored within industrial legacy waste containers. A system consisting of a pair of tracking modules above and a pair below the volume to be assayed is simulated within the GEANT4 framework using a range of potential fibre pitches and module separations. Each module comprises two orthogonal planes of fibres that allow the reconstruction of the initial and Coulomb-scattered muon trajectories. A likelihood-based image reconstruction algorithm has been developed that allows the container content to be determined with respect to the atomic number Z of the scattering material. Images reconstructed from this simulation are presented for a range of anticipated scenarios that highlight the expected image resolution and the potential of this system for the identification of high-Z materials within a shielded, concrete-filled container. First results from a constructed prototype system are presented in comparison with those from a detailed simulation. Excellent agreement between experimental data and simulation is observed showing clear discrimination between the different materials assayed throughout.

Anthony Clarkson; David J. Hamilton; Matthias Hoek; David G. Ireland; Russell Johnstone; Ralf Kaiser; Tibor Keri; Scott Lumsden; David F. Mahon; Bryan McKinnon; Morgan Murray; Sian Nutbeam-Tuffs; Craig Shearer; Cassie Staines; Guangliang Yang; Colin Zimmerman

2013-09-13T23:59:59.000Z

186

Hanford site transuranic waste certification plan  

SciTech Connect (OSTI)

As a generator of transuranic (TRU) and TRU mixed waste destined for disposal at the Waste Isolation Pilot Plant (WIPP), the Hanford Site must ensure that its TRU waste meets the requirements of U.S. Department of Energy (DOE) Order 5820.2A, ''Radioactive Waste Management, and the Waste Acceptance Criteria for the Waste Isolation Pilot Plant' (DOE 1996d) (WIPP WAC). The WIPP WAC establishes the specific physical, chemical, radiological, and packaging criteria for acceptance of defense TRU waste shipments at WIPP. The WIPP WAC also requires that participating DOE TRU waste generator/treatment/storage sites produce site-specific documents, including a certification plan, that describe their management of TRU waste and TRU waste shipments before transferring waste to WIPP. The Hanford Site must also ensure that its TRU waste destined for disposal at WIPP meets requirements for transport in the Transuranic Package Transporter41 (TRUPACT-11). The U.S. Nuclear Regulatory Commission (NRC) establishes the TRUPACT-I1 requirements in the ''Safety Analysis Report for the TRUPACT-II Shipping Package'' (NRC 1997) (TRUPACT-I1 SARP).

GREAGER, T.M.

1999-05-12T23:59:59.000Z

187

Environmental assessment for transuranic waste work-off plan, Los Alamos National Laboratory. Rough draft: Final report  

SciTech Connect (OSTI)

The Los Alamos National Laboratory (LANL) generates transuranic (TRU) waste in a variety of programs related to national defense. TRU waste is a specific class of radioactive waste requiring permanent isolation. Most defense-related TRU waste will be permanently disposed of in the Waste Isolation Pilot Plant (WIPP). WIPP is a deep geologic repository located in southeastern New Mexico and is now in the testing phase of development. All waste received by Wipp must conform with established Waste Acceptance Criteria (WAC). The purpose of the proposed action is to retrieve stored TRU waste and prepare the waste for shipment to and disposal WIPP. Stored TRU waste LANL is represented by four waste forms. The facilities necessary for work-off activities are tailored to the treatment and preparation of these four waste forms. Preparation activities for newly generated TRU waste are also covered by this action.

Not Available

1990-10-26T23:59:59.000Z

188

Resource Conservation and Recovery Act, Part B Permit Application [for the Waste Isolation Pilot Plant (WIPP)]. Volume 2, Chapter C, Appendix C1--Chapter C, Appendix C3 (beginning), Revision 3  

SciTech Connect (OSTI)

This volume contains appendices for the following: Rocky Flats Plant and Idaho National Engineering Laboratory waste process information; TRUPACT-II content codes (TRUCON); TRUPACT-II chemical list; chemical compatibility analysis for Rocky Flats Plant waste forms; chemical compatibility analysis for waste forms across all sites; TRU mixed waste characterization database; hazardous constituents of Rocky Flats Transuranic waste; summary of waste components in TRU waste sampling program at INEL; TRU waste sampling program; and waste analysis data.

Not Available

1993-03-01T23:59:59.000Z

189

Remote-handled transuranic waste study  

SciTech Connect (OSTI)

The Waste Isolation Pilot Plant (WIPP) was developed by the US Department of Energy (DOE) as a research and development facility to demonstrate the safe disposal of transuranic (TRU) radioactive wastes generated from the Nation`s defense activities. The WIPP disposal inventory will include up to 250,000 cubic feet of TRU wastes classified as remote handled (RH). The remaining inventory will include contact-handled (CH) TRU wastes, which characteristically have less specific activity (radioactivity per unit volume) than the RH-TRU wastes. The WIPP Land Withdrawal Act (LWA), Public Law 102-579, requires a study of the effect of RH-TRU waste on long-term performance. This RH-TRU Waste Study has been conducted to satisfy the requirements defined by the LWA and is considered by the DOE to be a prudent exercise in the compliance certification process of the WIPP repository. The objectives of this study include: conducting an evaluation of the impacts of RH-TRU wastes on the performance assessment (PA) of the repository to determine the effects of Rh-TRU waste as a part of the total WIPP disposal inventory; and conducting a comparison of CH-TRU and RH-TRU wastes to assess the differences and similarities for such issues as gas generation, flammability and explosiveness, solubility, and brine and geochemical interactions. This study was conducted using the data, models, computer codes, and information generated in support of long-term compliance programs, including the WIPP PA. The study is limited in scope to post-closure repository performance and includes an analysis of the issues associated with RH-TRU wastes subsequent to emplacement of these wastes at WIPP in consideration of the current baseline design. 41 refs.

NONE

1995-10-01T23:59:59.000Z

190

Nuclear waste management. Quarterly progress report, January-March 1980  

SciTech Connect (OSTI)

Reported are: high-level waste immobilization, alternative waste forms, nuclear waste materials characterization, TRU waste immobilization, TRU waste decontamination, krypton solidification, thermal outgassing, iodine-129 fixation, unsaturated zone transport, well-logging instrumentation development, mobile organic complexes of fission products, waste management system and safety studies, assessment of effectiveness of geologic isolation systems, waste/rock interactions, engineered barriers, criteria for defining waste isolation, and spent fuel and pool component integrity. (DLC)

Platt, A.M.; Powell, J.A. (comps.)

1980-06-01T23:59:59.000Z

191

Oak Ridge National Laboratory Transuranic Waste Certification Program  

SciTech Connect (OSTI)

The US Department of Energy (DOE) has requested that all DOE facilities handling defense transuranic (TRU) waste develop and implement a program whereby all TRU waste will be contained, stored, and shipped to the Waste Isolation Pilot Plant (WIPP) in accordance with the requirements set forth in the DOE certification documents WIPP-DOE-069, 114, 120, 137, 157, and 158. The program described in this report describes how Oak Ridge National Laboratory (ORNL) intends to comply with these requirements and the techniques and procedures used to ensure that ORNL TRU wastes are certifiable for shipment to WIPP. This document describes the program for certification of newly generated (NG) contact-handled transuranic (CH-TRU) waste. Previsions have been made for addenda, which will extend the coverage of this document to include certification of stored CH-TRU and NG and stored remote-handled transuranic (RH-TRU) waste, as necessary. 24 refs., 11 figs., 4 tabs.

Smith, J.H.; Bates, L.D.; Box, W.D.; Aaron, W.S.; Setaro, J.A.

1988-08-01T23:59:59.000Z

192

Natural and Enhanced Attenuation of Soil and Groundwater at the Monument Valley, Arizona, DOE Legacy Waste Site—10281  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE), the Navajo Nation, and the University of Arizona are exploring natural and enhanced attenuation remedies for groundwater contamination at a former uranium-ore processing site near Monument Valley, Arizona. DOE removed radioactive tailings from the Monument Valley site in 1994. Nitrate and ammonium, waste products of the milling process, remain in an alluvial groundwater plume spreading from the soil source where tailings were removed. Planting and irrigating two native shrubs, fourwing saltbush and black greasewood, markedly reduced both nitrate and ammonium in the source area over an 8-year period. Total nitrogen dropped from 350 mg/kg in 2000 to less than 200 mg/kg in 2008. Most of the reduction is attributable to irrigation-enhanced microbial denitrification rather than plant uptake. However, soil moisture and percolation flux monitoring show that the plantings control the soil water balance in the source area, preventing additional leaching of nitrogen compounds. Enhanced denitrification and phytoremediation also look promising for plume remediation. Microcosm experiments, nitrogen isotopic fractionation analysis, and solute transport modeling results suggest that (1) up to 70 percent of nitrate in the plume has been lost through natural denitrification since the mill was closed in 1968, and (2) injection of ethanol may accelerate microbial denitrification in plume hot spots. A field-scale ethanol injection pilot study is underway. Landscape-scale remote sensing methods developed for the project suggest that transpiration from restored native phreatophyte populations rooted in the aquifer could limit further expansion of the plume. An evaluation of landfarm phytoremediation, the irrigation of native shrub plantings with high nitrate water pumped from the alluvial aquifer, is also underway.

Waugh, W.J. [S.M. Stoller Corporation, Grand Junction, CO; Miller, D.E. [S.M. Stoller Corporation, Grand Junction, CO; Morris, S.A. [S.M. Stoller Corporation, Grand Junction, CO; Sheader, L.R. [S.M. Stoller Corporation, Grand Junction, CO; Glenn, E.P. [University of Arizona, Tucson, AZ; Moore, D. [University of Arizona, Tucson, AZ; Carroll, K.C. [University of Arizona, Tucson, AZ; Benally, L. [Navajo Nation, Window Rock, AZ; Roanhorse, M. [Navajo Nation, Window Rock, AZ; Bush, R.P. [U.S. Department of Energy, Grand Junction, CO; none,

2010-03-07T23:59:59.000Z

193

Nuclear waste management. Quarterly progress report, October-December 1979  

SciTech Connect (OSTI)

Progress and activities are reported on the following: high-level waste immobilization, alternative waste forms, nuclear waste materials characterization, TRU waste immobilization programs, TRU waste decontamination, krypton solidification, thermal outgassing, iodine-129 fixation, monitoring of unsaturated zone transport, well-logging instrumentation development, mobile organic complexes of fission products, waste management system and safety studies, assessment of effectiveness of geologic isolation systems, waste/rock interactions technology, spent fuel and fuel pool integrity program, and engineered barriers. (DLC)

Platt, A.M.; Powell, J.A. (comps.)

1980-04-01T23:59:59.000Z

194

Hanford Tank Waste Information Enclosure 1 Hanford Tank Waste Information  

E-Print Network [OSTI]

Hanford Tank Waste Information Enclosure 1 1 Hanford Tank Waste Information 1.0 Summary This information demonstrates the wastes in the twelve Hanford Site tanks meet the definition of transuranic (TRU. The wastes in these twelve (12) tanks are not high-level waste (HLW), and contain more than 100 nanocuries

195

A preliminary evaluation of certain NDA techniques for RH-TRU characterization  

SciTech Connect (OSTI)

This report presents the results of modeling efforts to evaluate selected NDA assay methods for RH-TRU waste characterization. The target waste stream was Content Code 104/107 113-liter waste drums that comprise the majority of the INEL`s RH-TRU waste inventory. Two NDA techniques are treated in detail. One primary NDA technique examined is gamma-ray spectrometry to determine the drum fission and activation product content, and fuel sample inventory calculations using the ORIGEN code to predict the total drum inventory. A heavily shielded and strongly collimated HPGE spectrometer system was designed using MCNP modeling. Detection limits and expected precision of this approach were estimated by a combination of Monte Carlo modeling and synthetic gamma-ray spectrum generation. This technique may allow the radionuclide content of these wastes to be determined with relative standard deviations of 20 to 55% depending on the drum matrix and radionuclide. The INEL Passive/Active Neutron (PAN) assay system is the second primary technique considered. A shielded overpack for the 113-liter CC104/107 RH-TRU drums was designed to shield the PAN detectors from excessive gamma radiation. MCNP modeling suggests PAN detection limits of about 0.06 g {sup 235}U and 0.04 g {sup 239}Pu during active assays.

Hartwell, J.K.; Yoon, W.Y.; Peterson, H.K.

1996-12-31T23:59:59.000Z

196

CRAD, Training - Oak Ridge National Laboratory TRU ALPHA LLWT...  

Broader source: Energy.gov (indexed) [DOE]

Training - Oak Ridge National Laboratory TRU ALPHA LLWT Project CRAD, Training - Oak Ridge National Laboratory TRU ALPHA LLWT Project November 2003 A section of Appendix C to DOE G...

197

Technical Evaluations of Proposed Remote-Handled Transuranic Waste Characterization Requirements at WIPP  

SciTech Connect (OSTI)

Characterization, packaging, transport, handling and disposal of remotely handled transuranic (RH TRU) waste at WIPP will be different than similar operations with contact handled transuranic (CH TRU) waste. This paper presents results of technical evaluations associated with the planned disposal of remotely handled transuranic waste at the Waste Isolation Pilot Plant (WIPP).

Anastas, G.; Channell, J. K.

2002-02-26T23:59:59.000Z

198

Transuranic contaminated waste container characterization and data base. Revision I  

SciTech Connect (OSTI)

The Nuclear Regulatory Commission (NRC) is developing regulations governing the management, handling and disposal of transuranium (TRU) radioisotope contaminated wastes as part of the NRC's overall waste management program. In the development of such regulations, numerous subtasks have been identified which require completion before meaningful regulations can be proposed, their impact evaluated and the regulations implemented. This report was prepared to assist in the development of the technical data base necessary to support rule-making actions dealing with TRU-contaminated wastes. An earlier report presented the waste sources, characteristics and inventory of both Department of Energy (DOE) generated and commercially generated TRU waste. In this report a wide variety of waste sources as well as a large TRU inventory were identified. The purpose of this report is to identify the different packaging systems used and proposed for TRU waste and to document their characteristics. This document then serves as part of the data base necessary to complete preparation and initiate implementation of TRU waste container and packaging standards and criteria suitable for inclusion in the present TRU waste management program. It is the purpose of this report to serve as a working document which will be used as appropriate in the TRU Waste Management Program. This report, and those following, will be compatible not only in format, but also in reference material and direction.

Kniazewycz, B.G.

1980-05-01T23:59:59.000Z

199

E-Print Network 3.0 - active nuclear wastes Sample Search Results  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

disposal site for transuranic (TRU) radio- active waste created during... , americium, curium, and neptunium are created during the produc- tion of nuclear weapons. Transuranic...

200

Documentation of TRU biological transport model (BIOTRAN)  

SciTech Connect (OSTI)

Inclusive of Appendices, this document describes the purpose, rationale, construction, and operation of a biological transport model (BIOTRAN). This model is used to predict the flow of transuranic elements (TRU) through specified plant and animal environments using biomass as a vector. The appendices are: (A) Flows of moisture, biomass, and TRU; (B) Intermediate variables affecting flows; (C) Mnemonic equivalents (code) for variables; (D) Variable library (code); (E) BIOTRAN code (Fortran); (F) Plants simulated; (G) BIOTRAN code documentation; (H) Operating instructions for BIOTRAN code. The main text is presented with a specific format which uses a minimum of space, yet is adequate for tracking most relationships from their first appearance to their formulation in the code. Because relationships are treated individually in this manner, and rely heavily on Appendix material for understanding, it is advised that the reader familiarize himself with these materials before proceeding with the main text.

Gallegos, A.F.; Garcia, B.J.; Sutton, C.M.

1980-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "legacy tru waste" 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

Process Knowledge Summary Report for Materials and Fuels Complex Contact-Handled Transuranic Debris Waste  

SciTech Connect (OSTI)

This Process Knowledge Summary Report summarizes the information collected to satisfy the transportation and waste acceptance requirements for the transfer of transuranic (TRU) waste between the Materials and Fuels Complex (MFC) and the Advanced Mixed Waste Treatment Project (AMWTP). The information collected includes documentation that addresses the requirements for AMWTP and the applicable portion of their Resource Conservation and Recovery Act permits for receipt and treatment of TRU debris waste in AMWTP. This report has been prepared for contact-handled TRU debris waste generated by the Idaho National Laboratory at MFC. The TRU debris waste will be shipped to AMWTP for purposes of supercompaction. This Process Knowledge Summary Report includes information regarding, but not limited to, the generation process, the physical form, radiological characteristics, and chemical contaminants of the TRU debris waste, prohibited items, and packaging configuration. This report, along with the referenced supporting documents, will create a defensible and auditable record for waste originating from MFC.

R. P. Grant; P. J. Crane; S. Butler; M. A. Henry

2010-02-01T23:59:59.000Z

202

Mixed waste characterization, treatment & disposal focus area  

SciTech Connect (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

203

A Comprehensive Solution for Managing TRU and LLW From Generation to Final Disposition - 13205  

SciTech Connect (OSTI)

A LANL multi-disciplinary team faced the challenge of building and delivering a waste information system capable of managing radioactive, hazardous, and industrial waste from cradle to grave. The result is the Waste Compliance and Tracking System (WCATS) a flexible, adaptive system that has allowed LANL to consolidate its legacy applications into one system, and leverage the advantages of managing all waste types within a single scalable enterprise application. Key functionality required for robust waste operations, include: waste characterization, waste identification, transportation, inventory management, waste processing, and disposal. In order to maintain data quality, field operations such as waste identification, surveillance checklists, wall-to-wall inventory assessments, waste transfers, shipment pickup and receipt, and simple consolidation operations are captured by the operator or technician using mobile computers. Work flow is managed via end-user defined work paths, to ensure that unit operations are performed in the correct order. Regulatory compliance reports and algorithms are provided to support typical U.S. EPA, DOT, NRC, and DOE requirements, including the EPA hazardous waste manifest, NRC LLW manifest, DOE nuclear material at risk, RCRA TSDF inventory rules, and so forth. The WCATS application has allowed LANL to migrate and consolidate its disparate legacy applications. The design and implementation is generalized so that facility owners can customize the user interface, setup facilities and unit operations (i.e., treatment, storage, disposal, characterization, and administrative), define inventory compliance rules, and establish custom work flow requirements. (authors)

Tozer, Justin C.; Sanchez, Edwina G.; Dorries, Alison M. [Los Alamos National Laboratory, Los Alamos, NM 87544 (United States)] [Los Alamos National Laboratory, Los Alamos, NM 87544 (United States)

2013-07-01T23:59:59.000Z

204

Greater-than-Class C Low-Level Radioactive Waste (GTCC LLW) ...  

Broader source: Energy.gov (indexed) [DOE]

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...

205

Strontium and cesium release mechanisms during unsaturated flow through waste-weathered Hanford sediments  

E-Print Network [OSTI]

Plutonium from Simulated Hanford Tank-Waste Sludges. Separ.Containing Tank Waste at Hanford. Separ. Sci. Technol. 2005,T. B. , Sr/TRU Removal from Hanford High Level Waste. Separ.

Chang, H.

2013-01-01T23:59:59.000Z

206

Draft Title 40 CFR 191 compliance certification application for the Waste Isolation Pilot Plant. Volume 3: Appendix BIR Volume 1  

SciTech Connect (OSTI)

The Waste Isolation Pilot Plant (WIPP) Transuranic Waste Baseline Inventory Report (WTWBIR) establishes a methodology for grouping wastes of similar physical and chemical properties, from across the US Department of Energy (DOE) transuranic (TRU) waste system, into a series of ``waste profiles`` that can be used as the basis for waste form discussions with regulatory agencies. The majority of this document reports TRU waste inventories of DOE defense sites. An appendix is included which provides estimates of commercial TRU waste from the West Valley Demonstration Project. The WIPP baseline inventory is estimated using waste streams identified by the DOE TRU waste generator/storage sites, supplemented by information from the Mixed Waste Inventory Report (MWIR) and the 1994 Integrated Data Base (IDB). The sites provided and/or authorized all information in the Waste Stream Profiles except the EPA (hazardous waste) codes for the mixed inventories. These codes were taken from the MWIR (if a WTWBIR mixed waste stream was not in MWIR, the sites were consulted). The IDB was used to generate the WIPP radionuclide inventory. Each waste stream is defined in a waste stream profile and has been assigned a waste matrix code (WMC) by the DOE TRU waste generator/storage site. Waste stream profiles with WMCs that have similar physical and chemical properties can be combined into a waste matrix code group (WMCG), which is then documented in a site-specific waste profile for each TRU waste generator/storage site that contains waste streams in that particular WMCG.

NONE

1995-03-31T23:59:59.000Z

207

Supplement Analysis for Site-Wide Environmental Impact Statement for Continued Operation of Los Alamos National Laboratory -- Modification of Management Methods for Transuranic Waste Characterization at Los Alamos National Laboratory  

SciTech Connect (OSTI)

This Supplement Analysis (SA) has been prepared to determine if the Site-Wide Environmental Impact Statement for Continued Operations of Los Alamos National Laboratory (SWEIS) (DOE/EIS-0238) adequately addresses the environmental effects of a waste management proposal for installing and operating modular units for the characterization of transuranic (TRU) waste1 at the Los Alamos National Laboratory (LANL) Technical Area (TA)-54, Area G, or if the SWEIS needs to be supplemented. Council on Environmental Quality regulations at Title 40, Section 1502.9 (c) of the Code of Federal Regulations (40 CFR 1502.9[c]) require federal agencies to prepare a supplement to an EIS when an agency makes substantial changes in the proposed action that are relevant to environmental concerns or there are circumstances or information relevant to concerns and bearing on the proposed action or its impacts. This SA is prepared in accordance with Section 10 CFR 1021.314(c) of the Department of Energy's (DOE's) regulations for NEPA implementation stating that ''When it is unclear whether or not an EIS supplement is required, DOE shall prepare a Supplement Analysis.'' This SA specifically compares key impact assessment parameters of the waste management program evaluated in the SWEIS with those of a proposal that would change the approach of a portion of this management program. It also provides an explanation of any differences between the proposed action and activities described in the previous SWEIS analysis. DOE proposes to expedite the shipment of legacy TRU waste to the Waste Isolation Pilot Plant (WIPP) in Carlsbad, New Mexico. The Cerro Grande Fire in 2000 and events of September 11, 2001, have focused attention on the potential risk to the public and the credible security hazard posed by the amount of plutonium stored above ground at LANL and the increased necessity to safeguard our nation's nuclear waste. The safest place for defense-generated TRU waste has been determined to be DOE's permitted repository for TRU waste 2100 feet underground at WIPP. The proposed accelerated plan to dispose of TRU waste at WIPP would result in the complete disposition of LANL legacy TRU waste by 2010; this accelerated disposition would be 20 years ahead of schedule, at a savings of $500 million in life-cycle costs and result in 3,000 fewer shipments to WIPP. However, the current individual small facilities at LANL lack the buildings, equipment, and trained personnel to conduct efficient characterization activities on an increased scale. Installing new modular structures and equipment close to the drum storage location at TA-54 in housings designed for a large inventory and high throughput would support DOE's expedited shipment program by increasing the repackaging rate, and it would also decrease on-site transportation vulnerabilities.

N /A

2002-08-13T23:59:59.000Z

208

Readiness Assessments for the Shipment of TRU from West Jefferson, Ohio  

SciTech Connect (OSTI)

From 1943 through 1986, Battelle Memorial Institute (BMI) performed research and development work at its own facilities for the U.S. Department of Energy (DOE) and its predecessor agencies. The most highly contaminated facilities, comprising BMI's Nuclear Sciences Area, are located on 11 acres in West Jefferson, Ohio. Three buildings in this area were used to study nuclear reactor fuels, fuel element components, reactor designs, and radiochemistry analyses: one building contained nuclear hot cells, a second building contained a critical assembly and radiochemistry laboratory, and a third building once housed a nuclear research reactor. The Columbus Environmental Management Project (CEMP), one of the DOE Ohio Field Office's radioactive cleanup sites, oversees the Battelle Columbus Laboratories Decommissioning Project (BCLDP) for the decontamination and decommissioning (D&D) of BMI's Nuclear Sciences Area. The BCLDP mission is to decontaminate the Nuclear Sciences Area to a condition that is suitable for use without restrictions and to dispose of or store the associated radioactive waste at a suitable DOE-approved facility. During decontamination work, the CEMP is expected to generate approximately 120, 55-gallon drums of transuranic (TRU) waste, or about 20 truckloads. This TRU waste will be transported to DOE's Hanford nuclear facility in Washington State for temporary storage, prior to its ultimate disposal at the Waste Isolation Pilot Plant (WIPP). This paper presents a detailed approach for conducting readiness assessments for TRU waste shipments from any DOE site. It is based on demonstrating satisfaction of the 18 core requirements contained in DOE Order 425.1B, Startup and Restart of Nuclear Facilities, that are derived from the seven guiding principles of DOE's integrated safety management system.

Duffy, M. A.

2003-02-26T23:59:59.000Z

209

Defense waste transportation: cost and logistics studies  

SciTech Connect (OSTI)

Transportation of nuclear wastes from defense programs is expected to significantly increase in the 1980s and 1990s as permanent waste disposal facilities come into operation. This report uses models of the defense waste transportation system to quantify potential transportation requirements for treated and untreated contact-handled transuranic (CH-TRU) wastes and high-level defense wastes (HLDW). Alternative waste management strategies in repository siting, waste retrieval and treatment, treatment facility siting, waste packaging and transportation system configurations were examined to determine their effect on transportation cost and hardware requirements. All cost estimates used 1980 costs. No adjustments were made for future changes in these costs relative to inflation. All costs are reported in 1980 dollars. If a single repository is used for defense wastes, transportation costs for CH-TRU waste currently in surface storage and similar wastes expected to be generated by the year 2000 were estimated to be 109 million dollars. Recovery and transport of the larger buried volumes of CH-TRU waste will increase CH-TRU waste transportation costs by a factor of 70. Emphasis of truck transportation and siting of multiple repositories would reduce CH-TRU transportation costs. Transportation of HLDW to repositories for 25 years beginning in 1997 is estimated to cost $229 M in 1980 costs and dollars. HLDW transportation costs could either increase or decrease with the selection of a final canister configuration. HLDW transportation costs are reduced when multiple repositories exist and emphasis is placed on truck transport.

Andrews, W.B.; Cole, B.M.; Engel, R.L.; Oylear, J.M.

1982-08-01T23:59:59.000Z

210

Waste acceptance criteria for the Waste Isolation Pilot Plant  

SciTech Connect (OSTI)

The Waste Isolation Pilot Plant (WIPP) Waste Acceptance Criteria (WAC), DOE/WIPP-069, was initially developed by a U.S. Department of Energy (DOE) Steering Committee to provide performance requirements to ensure public health and safety as well as the safe handling of transuranic (TRU) waste at the WIPP. This revision updates the criteria and requirements of previous revisions and deletes those which were applicable only to the test phase. The criteria and requirements in this document must be met by participating DOE TRU Waste Generator/Storage Sites (Sites) prior to shipping contact-handled (CH) and remote-handled (RH) TRU waste forms to the WIPP. The WIPP Project will comply with applicable federal and state regulations and requirements, including those in Titles 10, 40, and 49 of the Code of Federal Regulations (CFR). The WAC, DOE/WIPP-069, serves as the primary directive for assuring the safe handling, transportation, and disposal of TRU wastes in the WIPP and for the certification of these wastes. The WAC identifies strict requirements that must be met by participating Sites before these TRU wastes may be shipped for disposal in the WIPP facility. These criteria and requirements will be reviewed and revised as appropriate, based on new technical or regulatory requirements. The WAC is a controlled document. Revised/changed pages will be supplied to all holders of controlled copies.

NONE

1996-04-01T23:59:59.000Z

211

COMPREHENSIVE LEGACY MANAGEMENT  

Office of Legacy Management (LM)

Revision 7.0 Final This page intentionally left blank LMSFERS03496-7.0 Comprehensive Legacy Management and Institutional Controls Plan Volumes I and II Fernald Preserve Fernald,...

212

Washington TRU Solutions Inc | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data CenterFranconia, Virginia:FAQ < RAPID Jump to:Seadov PtyInformationSEDS dataIndiana:Coop Inc Place:Existing WaterAct JumpTRU

213

Tru-Lite | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data CenterFranconia, Virginia:FAQ < RAPID Jump to:Seadov Pty LtdSteen,LtdInformation DixieTraverseEnergy. ItTroy, Michigan:Tru-Lite Jump

214

TruRead | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data CenterFranconia, Virginia:FAQ < RAPID Jump to:Seadov Pty LtdSteen,LtdInformation DixieTraverseEnergy. ItTroy, Michigan:Tru-Lite

215

An Alternative to Performing Remote-Handled Transuranic Waste Container Headspace Gas Sampling and Analysis  

SciTech Connect (OSTI)

The Waste Isolation Pilot Plant (WIPP) is operating under a Resource Conservation and Recovery Act (RCRA) Hazardous Waste Facility Permit (HWFP) for contact-handled (CH) transuranic (TRU) waste. The HWFP contains limitations on allowable emissions from waste disposed in the underground. This environmental performance standard imposed on the WIPP consists of limiting volatile organic compound (VOC) emissions from emplaced waste to ensure protection of human health and the environment. The standard is currently met by tracking individual waste container headspace gas concentrations, which are determined by headspace gas sampling and analysis of CH TRU waste containers. The WIPP is seeking a HWFP modification to allow the disposal of remote-handled (RH) TRU waste. Because RH TRU waste is limited to approximately 5% of the waste volume and is emplaced in the disposal room walls, it is possible to bound the potential RH TRU waste contribution to VOC emissions using conservative upper bounds. These conservative upper bounds were developed as an alternative to RH TRU waste canister headspace gas sampling and analysis. The methodology used to perform the calculations used to evaluate VOC emissions from emplaced RH TRU waste canisters applied the same equations as those used to evaluate VOC emissions in the original HWFP application.

Spangler, L. R.; Djordjevic, S. M.; Kehrman, R. F.; Most, W. A.

2002-02-26T23:59:59.000Z

216

Solid Waste Processing Center Primary Opening Cells Systems, Equipment and Tools  

SciTech Connect (OSTI)

This document addresses the remote systems and design integration aspects of the development of the Solid Waste Processing Center (SWPC), a facility to remotely open, sort, size reduce, and repackage mixed low-level waste (MLLW) and transuranic (TRU)/TRU mixed waste that is either contact-handled (CH) waste in large containers or remote-handled (RH) waste in various-sized packages.

Bailey, Sharon A.; Baker, Carl P.; Mullen, O Dennis; Valdez, Patrick LJ

2006-04-17T23:59:59.000Z

217

Acceptable knowledge document for INEEL stored transuranic waste -- Rocky Flats Plant waste. Revision 2  

SciTech Connect (OSTI)

This document and supporting documentation provide a consistent, defensible, and auditable record of acceptable knowledge for waste generated at the Rocky Flats Plant which is currently in the accessible storage inventory at the Idaho National Engineering and Environmental Laboratory. The inventory consists of transuranic (TRU) waste generated from 1972 through 1989. Regulations authorize waste generators and treatment, storage, and disposal facilities to use acceptable knowledge in appropriate circumstances to make hazardous waste determinations. Acceptable knowledge includes information relating to plant history, process operations, and waste management, in addition to waste-specific data generated prior to the effective date of the RCRA regulations. This document is organized to provide the reader a comprehensive presentation of the TRU waste inventory ranging from descriptions of the historical plant operations that generated and managed the waste to specific information about the composition of each waste group. Section 2 lists the requirements that dictate and direct TRU waste characterization and authorize the use of the acceptable knowledge approach. In addition to defining the TRU waste inventory, Section 3 summarizes the historical operations, waste management, characterization, and certification activities associated with the inventory. Sections 5.0 through 26.0 describe the waste groups in the inventory including waste generation, waste packaging, and waste characterization. This document includes an expanded discussion for each waste group of potential radionuclide contaminants, in addition to other physical properties and interferences that could potentially impact radioassay systems.

NONE

1998-01-23T23:59:59.000Z

218

THE USE OF VAPOR EXTRACTION SYSTEM AND ITS SUBSEQUENT REDUCTION OF WORKER EXPOSURE TO CARBON TETRACHLORIDE DURING RETRIEVAL OF HANFORDS LEGACY WASTE  

SciTech Connect (OSTI)

The Hanford Site is a decommissioned nuclear productions complex located in south eastern Washington and is operated by the Department of Energy (DOE). From 1955 to 1973, carbon tetrachloride (CCl{sub 4}), used in mixtures with other organic compounds, was used to recover plutonium from aqueous streams at Z Plant located on the Hanford Site. The aqueous and organic liquid waste that remained at the end of this process was discharged to soil columns in waste cribs located near Z Plant. Included in this waste slurry along with CCl{sub 4} were tributyl phosphate, dibutyl butyl phosphate, and lard oil. (Truex et al., 2001). In the mid 1980's, CCl{sub 4} was found in the unconfined aquifer below the 200 West Area and subsequent ground water monitoring indicated that the plume was widespread and that the concentrations were increasing. It has been estimated that approximately 750,000 kg (826.7 tons) of CCl{sub 4} was discharged to the soil from 1955 to 1973. (Truex et al., 2001). With initial concentration readings of approximately 30,000 parts per million by volume (ppmv) in one well field alone, soil vapor extraction began in 1992 in an effort to remove the CCl{sub 4} from the soil. (Rohay, 1999). Since 1992, approximately 78,607.6 kg (86.65 tons) of CCl{sub 4} have been extracted from the soil through the process of soil vapor extraction and 9,409.8 kg (10.37 tons) have been removed from the groundwater. (EPA, 2006). The success of this environmental cleanup process benefited not only the environment but also workers who were later involved in the retrieval of solid waste from trenches that were in or near the CCl{sub 4} plume. Solid waste was buried in trenches near Z Plant from 1967 to 1990. The solid waste, some of which was chemically and/or radioactively contaminated, was buried in trenches in steel or fiber drums, fiberboard boxes, fiberglass-reinforced plywood boxes, and steel, concrete, or wooden boxes. Much of this waste was buried with the intention of retrieving it later for permanent disposal and storage. Removal of this solid waste would disturb the soil that was potentially contaminated with CC4 and thereby pose a risk to workers involved in the retrieval effort. However, with the success of the VES, worker exposure did not occur.

PITTS DA

2008-03-18T23:59:59.000Z

219

SEPARATION AND EXTRACTION OF PLUTONIUM IN MIXED WASTE  

SciTech Connect (OSTI)

The Sonatol process uses ultrasonic agitation in fluorinated surfactant solutions to remove radioactive particles from surfaces. Filtering the suspended particles allows the solutions to be reused indefinitely. The current work applies the Sonatol process to the decontamination of heterogeneous legacy Pu-238 waste that exhibits excessive hydrogen gas generation, which prevents transportation of the waste to the Waste Isolation Pilot Plant. Bartlett Services, Inc. (BSI) designed and fabricated a prototype decontamination system within a replica of a Savannah River Site glovebox. In Phase I, BSI conducted cold testing with surrogate waste material to verify that the equipment, operating procedures, and test protocols would support testing with Pu-238 in Phase II. The surrogate waste material is representative of known constituents of legacy job control waste. Two sub-micron sized Pu-238 simulants were added to the surrogate waste so that decontamination could be tested. The first simulant was an Osram Sylvania Phosphor 2284C powder that fluoresces under ultraviolet light. The use of the fluorescent simulant allows rapid, inexpensive system startup testing because residuals can be assayed using a digital camera. The results of digital pixel analysis (DPA) are available immediately and do not require use of licensed material. The second simulant, which was used for integrated cold testing, was a cerium oxide powder that was activated in a research reactor neutron flux and assayed by photon spectroscopy. The surrogate transuranic (TRU) waste material was contaminated with Pu-238 simulants and loaded into the cleaning chamber, where the surrogates were ultrasonically agitated and rinsed. The decontaminated materials were then assayed for surface contamination by DPA to establish optimum operating parameters and provide process quality control. Selected samples were sent to the Massachusetts Institute of Technology for neutron activation analysis (NAA). NAA testing resulted in weighted average decontamination factors (DFs) in the range of 125 to 157 for the surrogate waste mixtures. The weighted DFs for the organic portion of the surrogate waste mixtures ranged from 66 to 140. The NAA DF for inorganic material was 370. Other than the removal of particulate contamination, the processed samples were unchanged by decontamination. Most NAA samples were irradiated after decontamination. However, several samples were irradiated in the reactor core prior to decontamination in order to investigate the possible interference of radiation induced imbedding of particles in organic materials. The radiation dose was in excess of 110 Mrad. The NAA DF for samples irradiated before decontamination was six.

Arthur E. Desrosiers, ScD, CHP; Robert Kaiser, ScD; Jason Antkowiak; Justin Desrosiers; Josh Jondro; Adam Kulczyk

2002-12-13T23:59:59.000Z

220

Fiscal year 1986 program plan for the Defense Transuranic Waste Program (DTWP)  

SciTech Connect (OSTI)

The Defense TRU Waste Program (DTWP) is the focal point for the Department of Energy is national planning, integration, and technical development for TRU waste management. The scope of this program extends from the point of TRU waste generation through delivery to a permanent repository. The TRU program maintains a close interface with repository development to ensure program compatibility and coordination. The defense TRU program does not directly address commercial activities that generate TRU waste. Instead, it is concerned with providing alternatives to manage existing and future defense TRU wastes. The FY 86 Program Plan is consistent with the Defense TRU Waste Program goals and objectives stated in the Defense Transuranic Waste Program Strategy Document, January 1984. The roles of participants, the responsibilities and authorities for Research Development (R D), the organizational interfaces and communication channels for R D and the establishment of procedures for planning, reporting, and budgeting of all R D activities meet requirements tated in the Technical Management Plan for the Transuranic Waste Management Program. The Program Plan is revised as needed. Detailed budget planning (i.e., programmatic funding and capital equipment) is presented for FY 86; outyear budget projections are presented for future years.

Not Available

1985-11-01T23:59:59.000Z

Note: This page contains sample records for the topic "legacy tru waste" 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

WIPP Remote Handled Waste Facility: Performance Dry Run Operations  

SciTech Connect (OSTI)

The Remote Handled (RH) TRU Waste Handling Facility at the Waste Isolation Pilot Plant (WIPP) was recently upgraded and modified in preparation for handling and disposal of RH Transuranic (TRU) waste. This modification will allow processing of RH-TRU waste arriving at the WIPP site in two different types of shielded road casks, the RH-TRU 72B and the CNS 10-160B. Washington TRU Solutions (WTS), the WIPP Management and Operation Contractor (MOC), conducted a performance dry run (PDR), beginning August 19, 2002 and successfully completed it on August 24, 2002. The PDR demonstrated that the RHTRU waste handling system works as designed and demonstrated the handling process for each cask, including underground disposal. The purpose of the PDR was to develop and implement a plan that would define in general terms how the WIPP RH-TRU waste handling process would be conducted and evaluated. The PDR demonstrated WIPP operations and support activities required to dispose of RH-TRU waste in the WIPP underground.

Burrington, T. P.; Britain, R. M.; Cassingham, S. T.

2003-02-24T23:59:59.000Z

222

Tru-ly Clean - What Does It Mean?  

SciTech Connect (OSTI)

The evolution and genesis of the definition of transuranic waste (known as TRU) and its application to the cleanup criteria applied to soils contaminated with transuranics, specifically plutonium, has been a matter of discussion at contaminated sites in the United States and elsewhere. Cleanup decisions and the processes that led up to those decisions have varied at several plutonium contaminated sites within the United States and without the pacific region. The sites with radionuclide soil action levels include Bikini and Enewetak Atolls, Republic of the Marshall Islands; Johnston Atoll, Hawaii; the Hanford Site in Washington State; the Nevada Test Site; the Rocky Flats Environmental Technology Site in Colorado; the Chariot Site in north Alaska; and the Maralinga Site in Australia. The soil-action level developed for Rocky Flats by the U.S. Department of Energy, U.S. Environmental Protection Agency, and the Colorado Department of Public Health and Environment for plutonium is one of the higher soil-action levels approved by regulatory agencies that is considered protective for future use of land at a cleanup site. The Republic of the Marshall Islands has adopted a relatively conservative cleanup standard to accommodate the subsistence lifestyle of the islanders, while the Rocky Flats Environmental Technology Site has been transferred to the U.S. Department of the Interior to be used as a fish and wildlife refuge, a land use that resulted in a less conservative plutonium soil cleanup level. (authors)

Hopkins, A. [Fluor Hanford, Inc, Richland, WA (United States)

2008-07-01T23:59:59.000Z

223

Westinghouse TRU Solutions LLC Earns Corporate Award For Air Monitoring Initiative  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

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224

The PEACE PIPE: Recycling nuclear weapons into a TRU storage/shipping container  

SciTech Connect (OSTI)

This paper describes results of a contract undertaken by the National Conversion Pilot Project (NCPP) at the Rocky Flats Environmental Technology Site (RFETS) to fabricate stainless steel ``pipe`` containers for use in certification testing at Sandia National Lab, Albuquerque to qualify the container for both storage of transuranic (TRU) waste at RFETS and other DOE sites and shipping of the waste to the Waste Isolation Pilot Project (WIPP). The paper includes a description of the nearly ten-fold increase in the amount of contained plutonium enabled by the product design, the preparation and use of former nuclear weapons facilities to fabricate the components, and the rigorous quality assurance and test procedures that were employed. It also describes how stainless steel nuclear weapons components can be converted into these pipe containers, a true ``swords into plowshare`` success story.

Floyd, D.; Edstrom, C. [Manufacturing Sciences Corp. (United States); Biddle, K.; Orlowski, R. [BNFL, Inc. (United States); Geinitz, R. [Safe Sites of Colorado, Golden, CO (United States); Keenan, K. [USDOE-RFFO (United States); Rivera, M. [Science Applications International Corp./LATA (United States)

1997-03-01T23:59:59.000Z

225

Phase 2, Solid waste retrieval strategy  

SciTech Connect (OSTI)

Solid TRU retrieval, Phase 1 is scheduled to commence operation in 1998 at 218W-4C-T01 and complete recovery of the waste containers in 2001. Phase 2 Retrieval will recover the remaining buried TRU waste to be retrieved and provide the preliminary characterization by non-destructive means to allow interim storage until processing for disposal. This document reports on researching the characterization documents to determine the types of wastes to be retrieved and where located, waste configurations, conditions, and required methods for retrieval. Also included are discussions of wastes encompassed by Phase 2 for which there are valid reasons to not retrieve.

Johnson, D.M.

1994-09-29T23:59:59.000Z

226

Microsoft Word - Final_DOE_Cleanup_of_Legacy_TRU_at_SNL_Release.doc  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

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227

Waste Isolation Pilot Plant Status and Plans - 2012 - 12049  

SciTech Connect (OSTI)

The Waste Isolation Pilot Plant (WIPP), a deep geologic repository for safe disposal of long-lived transuranic radioactive waste related to the nation's defense, is completing its 12. year of operations. WIPP's mission includes coordination of all Department of Energy (DOE) sites to prepare, package and characterize transuranic (TRU) waste for final shipment and emplacement in WIPP. Five of the 10 disposal panels planned have been filled and sealed from ventilation. Additional small quantity sites have been de-inventoried by consolidating their waste through the certified characterization line at the Idaho National Laboratory (INL). New emplacement methods for RH waste in shielded containers are being considered for disposal by WIPP's regulatory authorities. A new large Type B shipping package, was added to the WIPP transportation fleet, and facility modifications to the WIPP waste unloading and emplacement processes for large containers were completed in 2011. Shipments from the Savannah River site in these new large rectangular packages began in August 2011. Licensing efforts are proceeding for a new criticality control over-pack container that will allow almost twice the fissile content to be shipped than previously. This will reduce the number and cost of shipments of Special Nuclear Material (SNM) declared as waste. Modifications to WIPP regulatory requirements for the disposal footprint and disposal unit closure systems are in progress. These, and other developments, make for exciting times at WIPP. This paper provides an up-to-date look at the many aspects of America's only deep geologic long-lived radioactive waste repository, which is completing its 12. year of operations. A record year of safe and compliant shipments to WIPP tops the list of accomplishments in 2011. Four more small quantity sites were de-inventoried by consolidating their waste through the certified characterization line at INL in 2011. A new Type B shipping package, the TRUPACT-III has been added to the transportation fleet, and large waste boxes are being shipped from SRS without the need for repackaging. New emplacement methods for remote-handled waste in shielded containers are undergoing regulatory review. WIPP plans to license a new criticality control payload container that will allow almost twice the fissile content to be shipped than previously, thereby reducing the number and cost of shipments of SNM declared as waste. Other regulatory modifications planned in 2012 include approval of a design change that would replace the disposal concept for panels 9 and 10 from using the common access drifts (the 'mains') with a new footprint south of panels 4 and 5. DOE also plans to change the panel closure design set forth in its certification by EPA and the HWFP by the NMED. The panel closure design change will be a rule making under EPA's procedures and a class 3 permit modification request under NMED procedures. Plans for achieving 90% of legacy TRU waste retrieval and emplacement in WIPP by 2015 have been developed. Key to the success of this so-called 90/15 plan is adequate funding, both for WIPP operations, as well as for TRU retrieval programs at the generator sites. (authors)

Nelson, Roger A.; Ziemianski, Edward J. [U.S. Department of Energy, Carlsbad, NM 88220 (United States)

2012-07-01T23:59:59.000Z

228

CHALLENGES WITH RETRIEVING TRANSURANIC WASTE FROM THE HANFORD BURIAL GROUNDS  

SciTech Connect (OSTI)

The U.S. DOE's Hanford Reservation produced plutonium and other nuclear materials for the nation's defense starting in World War II. The defense mission generated wastes that were either retrievably stored (i.e. retrievably stored waste) and/or disposed of in burial grounds. Challenges have emerged from retrieving suspect TRU waste including adequacy of records, radiological concerns, container integrity, industrial hygiene and safety issues, the lack of processing/treatment facilities, and the integration of regulatory requirements. All retrievably stored waste is managed as mixed waste and assumed to be TRU waste, unless documented otherwise. Mixed waste is defined as radioactive waste that contains hazardous constituents. The Atomic Energy Act governs waste with radionuclides, and the Resource Conservation and Recovery Act (RCRA) governs waste with hazardous constituents. Waste may also be governed by the Toxic Substances Control Act (TSCA), and a portion may be managed under the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA). In 1970, TRU waste was required to be placed in 20-year retrievable storage and segregated from other Waste. Prior to that date, segregation did not occur. Because of the changing definition of TRU over the years, and the limitations of early assay equipment, all retrievably stored waste in the burial grounds is managed as suspect TRU. Experience has shown that some of this waste will be characterized as low-level (non-TRU) waste after assay. The majority of the retrieved waste is not amenable to sampling due to waste type and/or radiological issues. Key to waste retrieval and disposition are characterization, historical investigation and research, knowledge of past handling and packaging, as well as a broad understanding and application of the regulations.

SWAN, R.J.; LAKES, M.E.

2007-08-06T23:59:59.000Z

229

Waste acceptance criteria for the Waste Isolation Pilot Plant. Revision 4  

SciTech Connect (OSTI)

This Revision 4 of the Waste Acceptance Criteria (WAC), WIPP-DOE-069, identifies and consolidates existing criteria and requirements which regulate the safe handling and preparation of Transuranic (TRU) waste packages for transportation to and emplacement in the Waste Isolation Pilot Plant (WIPP). This consolidation does not invalidate any existing certification of TRU waste to the WIPP Operations and Safety Criteria (Revision 3 of WIPP-DOE--069) and/or Transportation: Waste Package Requirements (TRUPACT-II Safety Analysis Report for Packaging [SARP]). Those documents being consolidated, including Revision 3 of the WAC, currently support the Test Phase.

Not Available

1991-12-01T23:59:59.000Z

230

Nondestructive radioassay for waste management: an assessment  

SciTech Connect (OSTI)

Nondestructive Assay (NDA) for Transuranic Waste Management is used to mean determining the amount of transuranic (TRU) isotopes in crates, drums, boxes, cans, or other containers without having to open the container. It also means determining the amount of TRU in soil, bore holes, and other environmental testing areas without having to go through extensive laboratory wet chemistry analyses. it refers to radioassay techniques used to check for contamination on objects after decontamination and to determine amounts of TRU in waste processing streams without taking samples to a laboratory. Gednerally, NDA instrumentation in this context refers to all use of radioassay which does not involve taking samples and using wet chemistry techniques. NDA instruments have been used for waste assay at some sites for over 10 years and other sites are just beginning to consider assay of wastes. The instrumentation used at several sites is discussed in this report. Almost all these instruments in use today were developed for special nuclear materials safeguards purposes and assay TRU waste down to the 500 nCi/g range. The need for instruments to assay alpha particle emitters at 10 nCi/g or less has risen from the wish to distinguish between Low Level Waste (LLW) and TRU Waste at the defined interface of 10 nCi/g. Wastes have historically been handled as TRU wastes if they were just suspected to be transuranically contaminated but their exact status was unknown. Economic and political considerations make this practice undesirable since it is easier and less costly to handle LLW. This prompted waste generators to want better instrumentation and led the Transuranic Waste Management Program to develop and test instrumentation capable of assaying many types of waste at the 10 nCi/g level. These instruments are discussed.

Lehmkuhl, G.D.

1981-06-01T23:59:59.000Z

231

EM's Los Alamos TRU Waste Campaign Heads Toward Completion | Department  

Broader source: Energy.gov (indexed) [DOE]

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232

Preparation of Safety Basis Documents for Transuranic (TRU) Waste Facilities  

Broader source: Energy.gov (indexed) [DOE]

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233

DOE Achieves Second TRU Waste Cleanup | Department of Energy  

Broader source: Energy.gov (indexed) [DOE]

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234

DOE Completes TRU Waste Cleanup at Bettis | Department of Energy  

Broader source: Energy.gov (indexed) [DOE]

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235

WIPP RH-TRU Waste Study - Notice To Users  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

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236

Transuranic (TRU) Waste Processing Center - Cask Processing Enclosure |  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

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237

Transuranic (TRU) Waste Processing Center - Overview | Department of Energy  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

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238

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

SciTech Connect (OSTI)

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

239

MRI Beginnings - a Legacy | GE Global Research  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

Legacy From Nobel Ideas to Industrial Success - Bill Edelstein's Legacy Scott Smith 2014.06.13 Edelsteinwith-MRmachine Nuclear magnetic resonance (NMR) was discovered in...

240

Focus Sheet | Hazardous Waste Checklist How to be ready for state hazardous waste  

E-Print Network [OSTI]

-hazardous solid chemicals may go in the trash. Have you disposed of "waste-like", legacy and unknown c Manage anyFocus Sheet | Hazardous Waste Checklist How to be ready for state hazardous waste inspectors. See a hazardous waste inspection. ons, rrosive. n hemicals? ical waste. Waste-like chemicals have als Are you

Wilcock, William

Note: This page contains sample records for the topic "legacy tru waste" from the National Library of EnergyBeta (NLEBeta).
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We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


241

Oak Ridge National Laboratory contact-handled Transuranic Waste Certification Program plan  

SciTech Connect (OSTI)

The Oak Ridge National Laboratory (ORNL) is required by Department of Energy (DOE) Order 5820.2A to package its transuranic (TRU) waste to comply with waste acceptance criteria (WAC) for the Waste Isolation Pilot Plant (WIPP). TRU wastes are defined in DOE Order 5820.A as those radioactive wastes that are contaminated with alpha-emitting transuranium radionuclides having half-lives greater than 20 years and concentrations greater than 100 nCi/g at the time of the assay. In addition, ORNL handles U{sup 233}, Cm{sup 244}, and Cf{sup 252} as TRU waste radionuclides. The ORNL Transuranic Waste Certification Program was established to ensure that all TRU waste at ORNL is packaged to meet the required transportation and storage criteria for shipping to and storage at the WIPP. The objective of this document is to describe the methods that will be used at ORNL to package contact handled-transuranic (CH-TRU) waste to meet the criteria set forth in the WIPP certification requirements documents. This document addresses newly generated (NG) CH-TRU waste. Stored CH-TRU will be repackaged. This document is organized to provide a brief overview of waste generation operations at ORNL, along with details on data management for CH-TRU waste. The methods used to implement this plan are discussed briefly along with the responsibilities and authorities of applicable organizations. Techniques used for waste data collection, records control, and data archiving are defined. Procedures for the procurement and handling of waste containers are also described along with related quality control methods. 11 refs., 3 figs.

Smith, J.H.; Smith, M.A.

1990-08-01T23:59:59.000Z

242

Radioactive mixed waste disposal  

SciTech Connect (OSTI)

Various types of waste have been generated during the 50-year history of the Hanford Site. Regulatory changes in the last 20 years have provided the emphasis for better management of these wastes. Interpretations of the Atomic Energy Act of 1954 (AEA), the Resource Conservation and Recovery Act of 1976 (RCRA), and the Hazardous and Solid Waste Amendments (HSWA) have led to the definition of radioactive mixed wastes (RMW). The radioactive and hazardous properties of these wastes have resulted in the initiation of special projects for the management of these wastes. Other solid wastes at the Hanford Site include low-level wastes, transuranic (TRU), and nonradioactive hazardous wastes. This paper describes a system for the treatment, storage, and disposal (TSD) of solid radioactive waste.

Jasen, W.G.; Erpenbeck, E.G.

1993-02-01T23:59:59.000Z

243

Safer Transportation and Disposal of Remote Handled Transuranic Waste - 12033  

SciTech Connect (OSTI)

Since disposal of remote handled (RH) transuranic (TRU) waste at the Waste Isolation Pilot Plant (WIPP) began in 2007, the Department of Energy (DOE) has had difficulty meeting the plans and schedule for disposing this waste. PECOS Management Services, Inc. (PECOS) assessed the feasibility of proposed alternate RH-TRU mixed waste containerisation concepts that would enhance the transportation rate of RH-TRU waste to WIPP and increase the utilization of available WIPP space capacity for RH-TRU waste disposal by either replacing or augmenting current and proposed disposal methods. In addition engineering and operational analyses were conducted that addressed concerns regarding criticality, heat release, and worker exposure to radiation. The results of the analyses showed that the concept, development, and use of a concrete pipe based design for an RH-TRU waste shipping and disposal container could be potentially advantageous for disposing a substantial quantity of RHTRU waste at WIPP in the same manner as contact-handled RH waste. Additionally, this new disposal method would eliminate the hazard associated with repackaging this waste in other containers without the requirement for NRC approval for a new shipping container. (authors)

Rojas, Vicente; Timm, Christopher M.; Fox, Jerry V. [PECOS Management Services, Inc., Albuquerque, NM (United States)

2012-07-01T23:59:59.000Z

244

CsIX/TRU Grout Feasibility Study  

SciTech Connect (OSTI)

A settlement agreement between the Department of Energy (DOE) and the State of Idaho mandates that liquid waste now stored at the Idaho Nuclear Technology Engineering Center (INTEC - formerly the Idaho Chemical Processing Plant, ICPP) will be calcined by the end of year 2012. This study investigates an alternative treatment of the liquid waste that removes undissolved solids (UDS) by filtration and removes cesium by ion exchange followed by cement-based grouting of the remaining liquid into 55-gal drums. Operations are assumed to be from January 2008 through December 2012. The grouted waste will be contact-handled and will be shipped to the Waste Isolation Pilot Plant (WIPP) in New Mexico for disposal. The small volume of secondary wastes such as the filtered solids and cesium sorbent (resin) would remain in storage at the Idaho National Engineering and Environmental Laboratory for treatment and disposal under another project, with an option to dispose of the filtered solids as a r emote-handled waste at WIPP.

S. J. Losinski; C. M. Barnes; B. K. Grover

1998-11-01T23:59:59.000Z

245

EIS-0305: Treating Transuranic (TRU)/Alpha Low-Level at the Oak...  

Broader source: Energy.gov (indexed) [DOE]

05: Treating Transuranic (TRU)Alpha Low-Level at the Oak Ridge National Laboratory, Oak Ridge, Tennessee EIS-0305: Treating Transuranic (TRU)Alpha Low-Level at the Oak Ridge...

246

LEGACY MANAGEMENT REQUIRES INFORMATION  

SciTech Connect (OSTI)

''Legacy Management Requires Information'' describes the goal(s) of the US Department of Energy's Office of Legacy Management (LM) relative to maintaining critical records and the way those goals are being addressed at Hanford. The paper discusses the current practices for document control, as well as the use of modern databases for both storing and accessing the data to support cleanup decisions. In addition to the information goals of LM, the Hanford Federal Facility Agreement and Consent Order, known as the ''Tri-Party Agreement'' (TPA) is one of the main drivers in documentation and data management. The TPA, which specifies discrete milestones for cleaning up the Hanford Site, is a legally binding agreement among the US Department of Energy (DOE), the Washington State Department of Ecology (Ecology), and the US Environmental Protection Agency (EPA). The TPA requires that DOE provide the lead regulatory agency with the results of analytical laboratory and non-laboratory tests/readings to help guide them in making decisions. The Agreement also calls for each signatory to preserve--for at least ten years after the Agreement has ended--all of the records in its or its contractors, possession related to sampling, analysis, investigations, and monitoring conducted. The tools used at Hanford to meet TPA requirements are also the tools that can satisfy the needs of LM.

CONNELL, C.W.; HILDEBRAND, R.D.

2006-12-14T23:59:59.000Z

247

Robust Solution to Difficult Hydrogen Issues When Shipping Transuranic Waste to the Waste Isolation Pilot Plant  

SciTech Connect (OSTI)

The Waste Isolation Pilot Plant (WIPP) has been open, receiving, and disposing of transuranic (TRU) waste since March 26, 1999. The majority of the waste has a path forward for shipment to and disposal at the WIPP, but there are about two percent (2%) or approximately 3,020 cubic meters (m{sup 3}) of the volume of TRU waste (high wattage TRU waste) that is not shippable because of gas generation limits set by the U.S. Nuclear Regulatory Commission (NRC). This waste includes plutonium-238 waste, solidified organic waste, and other high plutonium-239 wastes. Flammable gases are potentially generated during transport of TRU waste by the radiolysis of hydrogenous materials and therefore, the concentration at the end of the shipping period must be predicted. Two options are currently available to TRU waste sites for solving this problem: (1) gas generation testing on each drum, and (2) waste form modification by repackaging and/or treatment. Repackaging some of the high wattage waste may require up to 20:1 drum increase to meet the gas generation limits of less than five percent (5%) hydrogen in the inner most layer of confinement (the layer closest to the waste). (This is the limit set by the NRC.) These options increase waste handling and transportation risks and there are high costs and potential worker exposure associated with repackaging this high-wattage TRU waste. The U.S. Department of Energy (DOE)'s Carlsbad Field Office (CBFO) is pursuing a twofold approach to develop a shipping path for these wastes. They are: regulatory change and technology development. For the regulatory change, a more detailed knowledge of the high wattage waste (e.g., void volumes, gas generation potential of specific chemical constituents) may allow refinement of the current assumptions in the gas generation model for Safety Analysis Reports for Packaging for Contact-Handled (CH) TRU waste. For technology development, one of the options being pursued is the use of a robust container, the ARROW-PAK{trademark} System. (1) The ARROW-PAK{trademark} is a macroencapsulation treatment technology, developed by Boh Environmental, LLC, New Orleans, Louisiana. This technology has been designed to withstand any unexpected hydrogen deflagration (i.e. no consequence) and other benefits such as criticality control.

Countiss, S. S.; Basabilvazo, G. T.; Moody, D. C. III; Lott, S. A.; Pickerell, M.; Baca, T.; CH2M Hill; Tujague, S.; Svetlik, H.; Hannah, T.

2003-02-27T23:59:59.000Z

248

Characteristics of transuranic waste at Department of Energy sites  

SciTech Connect (OSTI)

This document reports data and information on TRU waste from all DOE generating and storage sites. The geographical location of the sites is shown graphically. There are four major sections in this document. The first three cover the TRU waste groups known as Newly Generated, Stored, and Buried Wastes. Subsections are included under Newly Generated and Stored on contact-handled and remote-handled waste. These classifications of waste are defined, and the current or expected totals of each are given. Figure 1.3 shows the total amount of Buried and Stored TRU waste. Preparation of this document began in 1981, and most of the data are as of December 31, 1980. In a few cases data were reported to December 31, 1981, and these have been noted. The projections in the Newly Generated section were made, for the most part, at the end of 1981.

Jensen, R.T.; Wilkinson, F.J. III

1983-05-01T23:59:59.000Z

249

Advanced Safeguards Approaches for New TRU Fuel Fabrication Facilities  

SciTech Connect (OSTI)

This second report in a series of three reviews possible safeguards approaches for the new transuranic (TRU) fuel fabrication processes to be deployed at AFCF – specifically, the ceramic TRU (MOX) fuel fabrication line and the metallic (pyroprocessing) line. The most common TRU fuel has been fuel composed of mixed plutonium and uranium dioxide, referred to as “MOX”. However, under the Advanced Fuel Cycle projects custom-made fuels with higher contents of neptunium, americium, and curium may also be produced to evaluate if these “minor actinides” can be effectively burned and transmuted through irradiation in the ABR. A third and final report in this series will evaluate and review the advanced safeguards approach options for the ABR. In reviewing and developing the advanced safeguards approach for the new TRU fuel fabrication processes envisioned for AFCF, the existing international (IAEA) safeguards approach at the Plutonium Fuel Production Facility (PFPF) and the conceptual approach planned for the new J-MOX facility in Japan have been considered as a starting point of reference. The pyro-metallurgical reprocessing and fuel fabrication process at EBR-II near Idaho Falls also provided insight for safeguarding the additional metallic pyroprocessing fuel fabrication line planned for AFCF.

Durst, Philip C.; Ehinger, Michael H.; Boyer, Brian; Therios, Ike; Bean, Robert; Dougan, A.; Tolk, K.

2007-12-15T23:59:59.000Z

250

CRAD, Management- Oak Ridge National Laboratory TRU ALPHA LLWT Project  

Broader source: Energy.gov [DOE]

A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a November 2003 assessment of the Management Program portion of an Operational Readiness Review of the Oak Ridge National Laboratory TRU ALPHA LLWT Project.

251

TruLifesaver American Heart Association Basic Life Support Course  

E-Print Network [OSTI]

TruLifesaver American Heart Association Basic Life Support Course The Truman Institute P: 660 concepts of high-quality CPR · The American Heart Association Chain of Survival · Differences between Cost includes all instruction, materials and two year certification with the American Heart Association

Gering, Jon C.

252

Audit Report on "Waste Processing and Recovery Act Acceleration Efforts for Contact-Handled Transuranic Waste at the Hanford Site"  

SciTech Connect (OSTI)

The Department of Energy's Office of Environmental Management's (EM), Richland Operations Office (Richland), is responsible for disposing of the Hanford Site's (Hanford) transuranic (TRU) waste, including nearly 12,000 cubic meters of radioactive contact-handled TRU wastes. Prior to disposing of this waste at the Department's Waste Isolation Pilot Plant (WIPP), Richland must certify that it meets WIPP's waste acceptance criteria. To be certified, the waste must be characterized, screened for prohibited items, treated (if necessary) and placed into a satisfactory disposal container. In a February 2008 amendment to an existing Record of Decision (Decision), the Department announced its plan to ship up to 8,764 cubic meters of contact-handled TRU waste from Hanford and other waste generator sites to the Advanced Mixed Waste Treatment Project (AMWTP) at Idaho's National Laboratory (INL) for processing and certification prior to disposal at WIPP. The Department decided to maximize the use of the AMWTP's automated waste processing capabilities to compact and, thereby, reduce the volume of contact-handled TRU waste. Compaction reduces the number of shipments and permits WIPP to more efficiently use its limited TRU waste disposal capacity. The Decision noted that the use of AMWTP would avoid the time and expense of establishing a processing capability at other sites. In May 2009, EM allocated $229 million of American Recovery and Reinvestment Act of 2009 (Recovery Act) funds to support Hanford's Solid Waste Program, including Hanford's contact-handled TRU waste. Besides providing jobs, these funds were intended to accelerate cleanup in the short term. We initiated this audit to determine whether the Department was effectively using Recovery Act funds to accelerate processing of Hanford's contact-handled TRU waste. Relying on the availability of Recovery Act funds, the Department changed course and approved an alternative plan that could increase costs by about $25 million by processing Hanford TRU-waste on-site rather than at AMWTP. Further, under the newly adopted alternative approach, the Department would fail to achieve the previously anticipated reductions in volume associated with the use of existing AMWTP waste compaction capabilities.

None

2010-05-01T23:59:59.000Z

253

Real-Time Detection Methods to Monitor TRU Compositions in UREX+Process Streams  

SciTech Connect (OSTI)

The U.S. Department of Energy has developed advanced methods for reprocessing spent nuclear fuel. The majority of this development was accomplished under the Advanced Fuel Cycle Initiative (AFCI), building on the strong legacy of process development R&D over the past 50 years. The most prominent processing method under development is named UREX+. The name refers to a family of processing methods that begin with the Uranium Extraction (UREX) process and incorporate a variety of other methods to separate uranium, selected fission products, and the transuranic (TRU) isotopes from dissolved spent nuclear fuel. It is important to consider issues such as safeguards strategies and materials control and accountability methods. Monitoring of higher actinides during aqueous separations is a critical research area. By providing on-line materials accountability for the processes, covert diversion of the materials streams becomes much more difficult. The importance of the nuclear fuel cycle continues to rise on national and international agendas. The U.S. Department of Energy is evaluating and developing advanced methods for safeguarding nuclear materials along with instrumentation in various stages of the fuel cycle, especially in material balance areas (MBAs) and during reprocessing of used nuclear fuel. One of the challenges related to the implementation of any type of MBA and/or reprocessing technology (e.g., PUREX or UREX) is the real-time quantification and control of the transuranic (TRU) isotopes as they move through the process. Monitoring of higher actinides from their neutron emission (including multiplicity) and alpha signatures during transit in MBAs and in aqueous separations is a critical research area. By providing on-line real-time materials accountability, diversion of the materials becomes much more difficult. The objective of this consortium was to develop real time detection methods to monitor the efficacy of the UREX+ process and to safeguard the separated TRUs against unlawful diversion from within a processing facility. To achieve this, a comprehensive strategy was implemented to incorporate traditional detectors and advanced Tensioned Metastable Fluid (TMFD) metastable fluid detectors (developed, in part, under this project) into a novel detector assembly coupled to the UREX+ centrifugal contactor array. The sections below provide a brief summary of the technical achievements completed during this project. The principal outcomes are documented in more complete details contained the doctoral dissertations and masters theses, journal papers, conference proceedings and additional items for more than the 35 publications that are listed in the program bibliography in Section 3.

McDeavitt, Sean; Charlton, William; Indacochea, J Ernesto; taleyarkhan, Rusi; Pereira, Candido

2013-03-01T23:59:59.000Z

254

Keeping Track of the National Transuranic Program Complex Defense Transuranic Waste  

SciTech Connect (OSTI)

The long-term performance of the Waste Isolation Pilot Plant (WIPP) disposal system in southeastern New Mexico is assessed periodically using transuranic (TRU) waste physical and radiological properties and other information describing the waste. This TRU waste estimate is based on the best knowledge of the TRU waste across the DOE complex at the time repository performance is assessed. TRU waste inventory was collected from each of the Department of Energy (DOE) sites that generated TRU waste for the Compliance Certification Application (CCA) and subsequently for the Compliance Re-certification Application (CRA) in order to support the assessments that ultimately led to certification and re-certification of the WIPP. In each case, information was collected, stored and maintained in the Transuranic Waste Baseline Inventory Database (TWBID) that was used to generate tables describing the volumetric, physical, and radiological properties of the TRU waste. The tables and other descriptions of the waste were reported in baseline reports for the certification and the re-certification. Information maintained in the TWBID database has now been transferred to a new qualified database that utilizes a more efficient operating configuration. This database known as the Comprehensive Inventory Database (CID) will be the information repository for TRU waste destined to WIPP, and the source for information submitted for annual Transuranic Waste Inventory Update Reports to be used in future repository performance assessments (PAs) and re-certifications. The information that has been collected will support a wider range of data needs including waste management, transportation and strategic planning. (authors)

Crawford, B.; Lott, S.; McInroy, W.; VanSoest, G. [Los Alamos National Laboratory-Carlsbad Operations, Carlsbad, NM (United States); Patterson, R. [U.S. Department of Energy Carlsbad Field Office, Carlsbad, NM (United States)

2007-07-01T23:59:59.000Z

255

Certification document for newly generated contact-handled transuranic waste  

SciTech Connect (OSTI)

The US Department of Energy has requested that all national laboratories handling defense waste develop and augment a program whereby all newly generated contact-handled transuranic (TRU) waste be contained, stored, and then shipped to the Waste Isolation Pilot Plant (WIPP) in accordance with the requirements set forth in WIPP-DOE-114. The program described in this report delineates how Oak Ridge National Laboratory intends to comply with these requirements and lists the procedures used by each generator to ensure that their TRU wastes are certifiable for shipment to WIPP.

Box, W.D.; Setaro, J.

1984-01-01T23:59:59.000Z

256

Westinghouse TRU Solutions LLC Announces Scholarship Awards  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear SecurityTensile Strain Switched FerromagnetismWaste and MaterialsWenjun DengWISP Sign In About |Selects Bill

257

Westinghouse TRU Solutions LLC Announces Scholarship Awards  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear SecurityTensile Strain Switched FerromagnetismWaste and MaterialsWenjun DengWISP Sign In About |Selects BillLea and

258

Westinghouse TRU Solutions LLC Assumes WIPP Operations  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear SecurityTensile Strain Switched FerromagnetismWaste and MaterialsWenjun DengWISP Sign In About |Selects BillLea

259

Characterization of past and present waste streams from the 325 Radiochemistry Building  

SciTech Connect (OSTI)

The purpose of this report is to characterize, as far as possible, the solid waste generated by the 325 Radiochemistry Building since its construction in 1953. Solid waste as defined in this document is any containerized or self-contained material that has been declared waste. This characterization is of particular interest in the planning of transuranic (TRU) waste retrieval operations including the Waste Receiving and Processing (WRAP) Facility. Westinghouse Hanford Company (Westinghouse Hanford) and Battelle Pacific Northwest Laboratory (PNL) activities at Building 325 have generated approximately 4.4% and 2.4%, respectively, of the total volume of TRU waste currently stored at the Hanford Site.

Pottmeyer, J.A.; Weyns-Rollosson, M.I.; Dicenso, K.D.; DeLorenzo, D.S. [Los Alamos Technical Associates, Kennewick, WA (United States); Duncan, D.R. [Westinghouse Hanford Co., Richland, WA (United States)

1993-12-01T23:59:59.000Z

260

Nuclear waste management. Quarterly progress report, April-June 1981  

SciTech Connect (OSTI)

Reports and summaries are presented for the following: high-level waste process development; alternative waste forms; TMI zeolite vitrification demonstration program; nuclear waste materials characterization center; TRU waste immobilization; TRU waste decontamination; krypton implantation; thermal outgassing; iodine-129 fixation; NWVP off-gas analysis; monitoring and physical characterization of unsaturated zone transport; well-logging instrumentation development; verification instrument development; mobility of organic complexes of radionuclides in soils; handbook of methods to decrease the generation of low-level waste; waste management system studies; waste management safety studies; assessment of effectiveness of geologic isolation systems; waste/rock interactions technology program; high-level waste form preparation; development of backfill materials; development of structural engineered barriers; disposal charge analysis; and analysis of spent fuel policy implementation.

Chikalla, T.D.; Powell, J.A.

1981-09-01T23:59:59.000Z

Note: This page contains sample records for the topic "legacy tru waste" 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.


261

EM Makes Significant Progress on Dispositioning Transuranic Waste at Idaho Site  

Broader source: Energy.gov [DOE]

IDAHO FALLS, Idaho – EM and contractor CH2M-WG, IDAHO, LLC (CWI) made significant progress in 2013 dispositioning transuranic (TRU) waste and helping ship it out of Idaho.

262

EIS-0026-S2: Waste Isolation Pilot Plant Disposal Phase, Carlsbad, New Mexico  

Broader source: Energy.gov [DOE]

SEIS-II evaluates environmental impacts resulting from the various treatment options; the transportation of TRU waste to WIPP using truck, a combination of truck and regular rail service, and a...

263

2012 Annual Planning Summary for Legacy Management  

Broader source: Energy.gov [DOE]

The ongoing and projected Environmental Assessments and Environmental Impact Statements for 2012 and 2013 within Legacy Management.

264

Long-range master plan for defense transuranic waste management  

SciTech Connect (OSTI)

The Long Range Master Plan for the Defense Transuranic Waste Program (DTWP), or ''Master Plan,'' details current TRU waste management plans and serves as a framework for the DTWP. Not all final decisions concerning activities presented in the Master Plan have been made (e.g., land withdrawal legislation, the WIPP Compliance and Operational Plan and the TRUPACT Certificate of Compliance). It is the goal of the DTWP to end interim storage and achieve permanent disposal of TRU waste. To accomplish this goal, as much TRU waste as possible will be certified to meet the WIPP Acceptance Criteria (WAC). The certified waste will then be disposed of at WIPP. The small quantity of waste which is not practical to certify will be disposed of via alternative methods that require DOE Headquarters approval and shall comply with the National Environmental Policy Act requirements and EPA/State Regulations. The definition of TRU waste is ''without regard to source or form, waste that is contaminated with alpha-emitting transuranium radionuclides with half-lives greater than 20 years and concentrations greater than 100 nanocuries/gram (nCi/g) at the time of assay. Heads of Field Elements can determine that other alpha contaminated wastes, peculiar to a specific site, must be managed as transuranic waste.''

Not Available

1988-12-01T23:59:59.000Z

265

Hanford site transuranic waste sampling plan  

SciTech Connect (OSTI)

This sampling plan (SP) describes the selection of containers for sampling of homogeneous solids and soil/gravel and for visual examination of transuranic and mixed transuranic (collectively referred to as TRU) waste generated at the U.S. Department of Energy (DOE) Hanford Site. The activities described in this SP will be conducted under the Hanford Site TRU Waste Certification Program. This SP is designed to meet the requirements of the Transuranic Waste Characterization Quality Assurance Program Plan (CAO-94-1010) (DOE 1996a) (QAPP), site-specific implementation of which is described in the Hanford Site Transuranic Waste Characterization Program Quality Assurance Project Plan (HNF-2599) (Hanford 1998b) (QAPP). The QAPP defines the quality assurance (QA) requirements and protocols for TRU waste characterization activities at the Hanford Site. In addition, the QAPP identifies responsible organizations, describes required program activities, outlines sampling and analysis strategies, and identifies procedures for characterization activities. The QAPP identifies specific requirements for TRU waste sampling plans. Table 1-1 presents these requirements and indicates sections in this SP where these requirements are addressed.

GREAGER, T.M.

1999-05-13T23:59:59.000Z

266

Waste acceptance and waste loading for vitrified Oak Ridge tank waste  

SciTech Connect (OSTI)

The Office of Science and Technology of the DOE has funded a joint project between the Oak Ridge National Laboratory (ORNL) and the Savannah River Technology Center (SRTC) to evaluate vitrification and grouting for the immobilization of sludge from ORNL tank farms. The radioactive waste is from the Gunite and Associated Tanks (GAAT), the Melton Valley Storage Tanks (MVST), the Bethel Valley Evaporator Service Tanks (BVEST), and the Old Hydrofractgure Tanks (OHF). Glass formulation development for sludge from these tanks is discussed in an accompanying article for this conference (Andrews and Workman). The sludges contain transuranic radionuclides at levels which will make the glass waste form (at reasonable waste loadings) TRU. Therefore, one of the objectives for this project was to ensure that the vitrified waste form could be disposed of at the Waste Isolation Pilot Plant (WIPP). In order to accomplish this, the waste form must meet the WIPP Waste Acceptance Criteria (WAC). An alternate pathway is to send the glass waste forms for disposal at the Nevada Test Site (NTS). A sludge waste loading in the feed of 6 wt percent will lead to a waste form which is non-TRU and could potentially be disposed of at NTS. The waste forms would then have to meet the requirements of the NTS WAC. This paper presents SRTC`s efforts at demonstrating that the glass waste form produced as a result of vitrification of ORNL sludge will meet all the criteria of the WIPP WAC or NTS WAC.

Harbour, J.R.; Andrews, M.K.

1997-06-06T23:59:59.000Z

267

The Second Opening of the Waste Isolation Pilot Plant? Review of Salient Characteristics and Unique Operational Considerations for Remote Handled Transuranic Waste  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE) intends to dispose of remote handled (RH) transuranic (TRU) waste at the Waste Isolation Pilot Plant (WIPP) beginning in 2005. (1) Four principle regulatory agencies are involved in the process of approving the RH TRU waste activities. The DOE is responsible for operational activities. The U. S. Nuclear Regulatory Commission (NRC) approves the design and use of shipping containers. The U.S. Environmental Protection Agency (EPA) is responsible for assuring safe and environmentally effective long-term disposal of the radioactive component of the waste and operational environmental monitoring. The New Mexico Environment Department (NMED) is responsible for the handling and the disposal of the non-radioactive hazardous component of the waste. The Environmental Evaluation Group (EEG) is responsible for performing independent technical oversight of all WIPP activities, and will comment on documents and practices for the various regulated RH TRU waste activities. The DOE has already obtained the necessary approvals from the NRC, and has submitted a Class 3 Modification request to the NMED. On December 16, 2002 the DOE Carlsbad Field Office (CBFO) provided the EPA with a notice of proposed change, in accordance with 40 CFR 194.4 (b) (3), to receive and dispose of remote handled transuranic waste. (2) WIPP procedures for the management of RH TRU waste at the site are being developed. While there are no issues with current NRC Certificates of Compliance for the RH TRU waste shipping containers, it is likely that there will be some controversy over other aspects of the currently planned RH TRU waste program. These issues may include: (1) the published RH TRU waste inventory, (2) the characterization of the radionuclide portion of the waste, for which one planned method is to use dose-to-Curie conversions, and (3) the plans to use bounding estimates for the hazardous portion of the WIPP waste, rather than measuring VOCs on a container-by-container basis or by representative sampling as is done for contact handled transuranic (CH TRU) waste. This paper discusses the currently planned process and the possible issues related to the DOE's efforts to dispose RH TRU waste at the WIPP.

Anastas, G.; Walker, B.A.

2003-02-24T23:59:59.000Z

268

Nuclear waste management. Quarterly progress report, April-June 1980  

SciTech Connect (OSTI)

The status of the following programs is reported: high-level waste immobilization; alternative waste forms; Nuclear Waste Materials Characterization Center; TRU waste immobilization; TRU waste decontamination; krypton solidification; thermal outgassing; iodine-129 fixation; monitoring and physical characterization of unsaturated zone transport; well-logging instrumentation development; mobility of organic complexes of fission products in soils; waste management system studies; waste management safety studies; assessment of effectiveness of geologic isolation systems; waste/rock interactions technology; systems study on engineered barriers; criteria for defining waste isolation; spent fuel and fuel pool component integrity program; analysis of spent fuel policy implementation; asphalt emulsion sealing of uranium tailings; application of long-term chemical biobarriers for uranium tailings; and development of backfill material.

Platt, A.M.; Powell, J.A. (comps.)

1980-09-01T23:59:59.000Z

269

Nuclear waste management. Quarterly progress report, October through December 1980  

SciTech Connect (OSTI)

Progress reports and summaries are presented under the following headings: high-level waste process development; alternative waste forms; nuclear waste materials characterization center; TRU waste immobilization; TRU waste decontamination; krypton solidification; thermal outgassing; iodine-129 fixation; monitoring and physical characterization of unsaturated zone transport; well-logging instrumentation development; mobility of organic complexes of radionuclides in soils; waste management system studies; waste management safety studies; assessment of effectiveness of geologic isolation systems; waste/rock interactions technology; high level waste form preparation; development of backfill material; development of structural engineered barriers; ONWI disposal charge analysis; spent fuel and fuel component integrity program; analysis of spent fuel policy implementation; analysis of postulated criticality events in a storage array of spent LWR fuel; asphalt emulsion sealing of uranium tailings; liner evaluation for uranium mill tailings; multilayer barriers for sealing of uranium tailings; application of long-term chemical biobarriers for uranium tailings; revegetation of inactive uranium tailing sites; verification instrument development.

Chikalla, T.D.; Powell, J.A. (comps.)

1981-03-01T23:59:59.000Z

270

Waste Isolation Pilot Plant Safety Analysis Report  

SciTech Connect (OSTI)

The following provides a summary of the specific issues addressed in this FY-95 Annual Update as they relate to the CH TRU safety bases: Executive Summary; Site Characteristics; Principal Design and Safety Criteria; Facility Design and Operation; Hazards and Accident Analysis; Derivation of Technical Safety Requirements; Radiological and Hazardous Material Protection; Institutional Programs; Quality Assurance; and Decontamination and Decommissioning. The System Design Descriptions`` (SDDS) for the WIPP were reviewed and incorporated into Chapter 3, Principal Design and Safety Criteria and Chapter 4, Facility Design and Operation. This provides the most currently available final engineering design information on waste emplacement operations throughout the disposal phase up to the point of permanent closure. Also, the criteria which define the TRU waste to be accepted for disposal at the WIPP facility were summarized in Chapter 3 based on the WAC for the Waste Isolation Pilot Plant.`` This Safety Analysis Report (SAR) documents the safety analyses that develop and evaluate the adequacy of the Waste Isolation Pilot Plant Contact-Handled Transuranic Wastes (WIPP CH TRU) safety bases necessary to ensure the safety of workers, the public and the environment from the hazards posed by WIPP waste handling and emplacement operations during the disposal phase and hazards associated with the decommissioning and decontamination phase. The analyses of the hazards associated with the long-term (10,000 year) disposal of TRU and TRU mixed waste, and demonstration of compliance with the requirements of 40 CFR 191, Subpart B and 40 CFR 268.6 will be addressed in detail in the WIPP Final Certification Application scheduled for submittal in October 1996 (40 CFR 191) and the No-Migration Variance Petition (40 CFR 268.6) scheduled for submittal in June 1996. Section 5.4, Long-Term Waste Isolation Assessment summarizes the current status of the assessment.

NONE

1995-11-01T23:59:59.000Z

271

Resource Conservation and Recovery Act, Part B permit application [for the Waste Isolation Pilot Plant (WIPP)]. Volume 3, Chapter C, Appendix C3 (conclusion)--Chapter C, Appendix C9: Revision 3  

SciTech Connect (OSTI)

This volume contains appendices for the following: results of extraction procedure (EP) toxicity data analyses; summary of headspace gas analysis in Rocky Flats Plant sampling program-FY 1988; waste drum gas generation sampling program at Rocky Flats Plant during FY 1988; TRU waste sampling program waste characterization; summary of headspace gas analyses in TRU waste sampling program; summary of volatile organic compounds analyses in TRU waste sampling program; totals analysis versus toxicity characteristic leaching procedure; Waste Isolation Pilot Plant waste characterization sampling and analysis methods; Waste Isolation Pilot Plant waste characterization analytical methods; data reduction, validation and reporting; examples of waste screening checklists; and Waste Isolation Pilot Plant generator/storage site waste screening and acceptance audit program.

Not Available

1993-03-01T23:59:59.000Z

272

Waste Management Program. Technical progress report, Aporil-June 1983  

SciTech Connect (OSTI)

This quarterly report provides current information on operations and development programs for the management of radioactive wastes from operation of the Savannah River Plant. The studies on environmental and safety assessments, process and equipment development, TRU waste, and low-level waste are a part of the Long-Term Waste Management Technology Program. The following studies are reported for the SR Interim Waste Operations Program: surveillance and maintenance, waste concentration, low-level effluent waste, tank replacement/waste transfer, and solid waste storage and related activities.

None

1984-02-01T23:59:59.000Z

273

Transuranic waste baseline inventory report. Revision No. 3  

SciTech Connect (OSTI)

The Transuranic Waste Baseline Inventory Report (TWBIR) establishes a methodology for grouping wastes of similar physical and chemical properties from across the U.S. Department of Energy (DOE) transuranic (TRU) waste system into a series of {open_quotes}waste profiles{close_quotes} that can be used as the basis for waste form discussions with regulatory agencies. The purpose of Revisions 0 and 1 of this report was to provide data to be included in the Sandia National Laboratories/New Mexico (SNL/NM) performance assessment (PA) processes for the Waste Isolation Pilot Plant (WIPP). Revision 2 of the document expanded the original purpose and was also intended to support the WIPP Land Withdrawal Act (LWA) requirement for providing the total DOE TRU waste inventory. The document included a chapter and an appendix that discussed the total DOE TRU waste inventory, including nondefense, commercial, polychlorinated biphenyls (PCB)-contaminated, and buried (predominately pre-1970) TRU wastes that are not planned to be disposed of at WIPP.

NONE

1996-06-01T23:59:59.000Z

274

Hanford`s remote-handled transuranic and transuranic mixed waste volume assessment  

SciTech Connect (OSTI)

This study documents the results of an assessment of each Hanford program`s potential RH-TRU(M) waste forecast volumes. Of this 3,470 m{sup 3} of remote-handled transuranic and transuranic mixed (RH-TRU[M]) forecast waste, the Environmental Restoration program is the only program generating waste (360 m{sup 3}) after the closure of the WIPP in FY 2033. Previous forecast assessments have estimated Hanford`s RH-TRU(M) waste volumes to range from 4,000 m{sup 3} to 45,000 m{sup 3}. In FY 1995, the RH-TRU(M) waste forecast was approximately 22,200 m{sup 3} (BIR), which exceeds the WIPP remote-handled capacity. The FY-1996 Solid Waste Integrated Life-Cycle Forecast Volume Summary (WHC-EP-0900) published in February 1996 stated that the baseline RH-TRU(M) waste volume was 13,350 m{sup 3}. The primary reason for the three different estimates results from two programmatic baseline revisions: Tank Waste Remediation Systems (TWRS) and Environmental Restoration (EM-40). The difference in the TWRS programmatic baseline is due to a revised programmatic baseline for the disposition of the long-length equipment currently present in the tanks. The difference in the Environmental Restoration programmatic baseline is due to an assessment based on recent experience that many of the facilities at Hanford will not contain RH-TRU(M) waste during decontamination and decommissioning and that for many other facilities, the RH-TRU(M) waste volumes will not be as great as previously estimated.

Templeton, K.J.; DeForest, T.J.; Hladek, K.L.

1996-03-01T23:59:59.000Z

275

Turing's Legacy Cambridge University Press  

E-Print Network [OSTI]

View list of contributors... Hardback (ISBN-13: 9781107043480) c. £60.00 #12; Alan Turing's ideas in logic Rod Downey; 1. Computability and analysis: the legacy of Alan Turing Jeremy Avigad and Vasco Brattka; 2. Alan Turing and the other theory of computation (expanded) Lenore Blum; 3. Turing

Harizanov, Valentina S.

276

Environmental assessment, finding of no significant impact, and response to comments. Radioactive waste storage  

SciTech Connect (OSTI)

The Department of Energy`s (DOE) Rocky Flats Environmental Technology Site (the Site), formerly known as the Rocky Flats Plant, has generated radioactive, hazardous, and mixed waste (waste with both radioactive and hazardous constituents) since it began operations in 1952. Such wastes were the byproducts of the Site`s original mission to produce nuclear weapons components. Since 1989, when weapons component production ceased, waste has been generated as a result of the Site`s new mission of environmental restoration and deactivation, decontamination and decommissioning (D&D) of buildings. It is anticipated that the existing onsite waste storage capacity, which meets the criteria for low-level waste (LL), low-level mixed waste (LLM), transuranic (TRU) waste, and TRU mixed waste (TRUM) would be completely filled in early 1997. At that time, either waste generating activities must cease, waste must be shipped offsite, or new waste storage capacity must be developed.

NONE

1996-04-01T23:59:59.000Z

277

Melter development needs assessment for RWMC buried wastes  

SciTech Connect (OSTI)

This report presents a survey and initial assessment of the existing state-of-the-art melter technology necessary to thermally treat (stabilize) buried TRU waste, by producing a highly leach resistant glass/ceramic waste form suitable for final disposal. Buried mixed transuranic (TRU) waste at the Idaho National Engineering Laboratory (INEL) represents an environmental hazard requiring remediation. The Environmental Protection Agency (EPA) placed the INEL on the National Priorities List in 1989. Remediation of the buried TRU-contaminated waste via the CERCLA decision process is required to remove INEL from the National Priorities List. A Waste Technology Development (WTD) Preliminary Systems Design and Thermal Technologies Screening Study identified joule-heated and plasma-heated melters as the most probable thermal systems technologies capable of melting the INEL soil and waste to produce the desired final waste form (Iron-Enriched Basalt (IEB) glass/ceramic). The work reported herein then surveys the state of existing melter technology and assesses it within the context of processing INEL buried TRU wastes and contaminated soils. Necessary technology development work is recommended.

Donaldson, A.D.; Carpenedo, R.J.; Anderson, G.L.

1992-02-01T23:59:59.000Z

278

Melter development needs assessment for RWMC buried wastes  

SciTech Connect (OSTI)

This report presents a survey and initial assessment of the existing state-of-the-art melter technology necessary to thermally treat (stabilize) buried TRU waste, by producing a highly leach resistant glass/ceramic waste form suitable for final disposal. Buried mixed transuranic (TRU) waste at the Idaho National Engineering Laboratory (INEL) represents an environmental hazard requiring remediation. The Environmental Protection Agency (EPA) placed the INEL on the National Priorities List in 1989. Remediation of the buried TRU-contaminated waste via the CERCLA decision process is required to remove INEL from the National Priorities List. A Waste Technology Development (WTD) Preliminary Systems Design and Thermal Technologies Screening Study identified joule-heated and plasma-heated melters as the most probable thermal systems technologies capable of melting the INEL soil and waste to produce the desired final waste form [Iron-Enriched Basalt (IEB) glass/ceramic]. The work reported herein then surveys the state of existing melter technology and assesses it within the context of processing INEL buried TRU wastes and contaminated soils. Necessary technology development work is recommended.

Donaldson, A.D.; Carpenedo, R.J.; Anderson, G.L.

1992-02-01T23:59:59.000Z

279

Fire hazards analysis for solid waste burial grounds  

SciTech Connect (OSTI)

This document comprises the fire hazards analysis for the solid waste burial grounds, including TRU trenches, low-level burial grounds, radioactive mixed waste trenches, etc. It analyzes fire potential, and fire damage potential for these facilities. Fire scenarios may be utilized in future safety analysis work, or for increasing the understanding of where hazards may exist in the present operation.

McDonald, K.M.

1995-09-28T23:59:59.000Z

280

CHARACTERIZATION THROUGH DATA QUALITY OBJECTIVES AND CERTIFICATION OF REMOTE-HANDLED TRANSURANIC WASTE GENERATOR/STORAGE SITES FOR SHIPMENT TO THE WIPP  

SciTech Connect (OSTI)

The Waste Isolation Pilot Plant (WIPP) is operating to receive and dispose of contact-handled (CH) transuranic (TRU) waste. The Department of Energy (DOE) Carlsbad Field Office (CBFO) is seeking approval from the Environmental Protection Agency (EPA) and the New Mexico Environment Department (NMED) of the remote-handled (RH) TRU characterization plan to allow disposal of RH TRU waste in the WIPP repository. In addition, the DOE-CBFO has received approval from the Nuclear Regulatory Commission (NRC) to use two shipping casks for transporting RH TRU waste. Each regulatory agency (i.e., EPA, NMED, and NRC) has different requirements that will have to be met through the use of information collected by characterizing the RH TRU waste. Therefore, the DOE-CBFO has developed a proposed characterization program for obtaining the RH TRU waste information necessary to demonstrate that the waste meets the applicable regulatory requirements. This process involved the development of a comprehensive set of Data Quality Objectives (DQOs) comprising the various regulatory requirements. The DOE-CBFO has identified seven DQOs for use in the RH TRU waste characterization program. These DQOs are defense waste determination, TRU waste determination, RH TRU determination, activity determination, RCRA physical and chemical properties, prohibited item determination, and EPA physical and chemical properties. The selection of the DQOs were based on technical, legal and regulatory drivers that assure the health and safety of the workers, the public, to protect the environment, and to comply with the requirements of the regulatory agencies. The DOE-CBFO also has the responsibility for the certification of generator/storage sites to ship RH TRU mixed waste to the WIPP for disposal. Currently, thirteen sites across the DOE complex are generators of RH TRU waste or store the waste at their location for other generators. Generator/storage site certification involves review and approval of site-specific programmatic documents that demonstrate compliance with the WIPP waste characterization and transportation requirements. Additionally, procedures must be developed to implement programmatic requirements and adequacy of those procedures determined. Finally, on-site audits evaluate the technical and administrative implementation and effectiveness of the operating procedures.

Spangler, L.R.; Most, Wm.A.; Kehrman, R.F.; Gist, C.S.

2003-02-27T23:59:59.000Z

Note: This page contains sample records for the topic "legacy tru waste" 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

Foreign programs for the storage of spent nuclear power plant fuels, high-level waste canisters and transuranic wastes  

SciTech Connect (OSTI)

The various national programs for developing and applying technology for the interim storage of spent fuel, high-level radioactive waste, and TRU wastes are summarized. Primary emphasis of the report is on dry storage techniques for uranium dioxide fuels, but data are also provided concerning pool storage.

Harmon, K.M.; Johnson, A.B. Jr.

1984-04-01T23:59:59.000Z

282

HOLDUP MEASUREMENTS FOR THREE VISUAL EXAMINATION AND TRU REMEDIATION GLOVEBOX FACILITIES AT THE SAVANNAH RIVER SITE  

SciTech Connect (OSTI)

Visual Examination (VE) gloveboxes are used to remediate transuranic waste (TRU) drums at three separate facilities at the Savannah River Site. Noncompliant items are removed before the drums undergo further characterization in preparation for shipment to the Waste Isolation Pilot Plant (WIPP). Maintaining the flow of drums through the remediation process is critical to the program's seven-days-per-week operation. Conservative assumptions are used to ensure that glovebox contamination from this continual operation is below acceptable limits. Holdup measurements using cooled HPGe spectrometers are performed in order to confirm that these assumptions are conservative. {sup 239}Pu is the main nuclide of interest; however, {sup 241}Pu, equilibrium {sup 237}Np/{sup 233}Pa and {sup 238}Pu (if detected) are typically assayed. At the Savannah River National Laboratory (SRNL) facility {sup 243,244,245}Cm are also generally observed and are always reported at either finite levels or at limits of detection. A complete assay at each of the three facilities includes a measure of TRU content in the gloveboxes and HEPA filters in the glovebox exhaust. This paper includes a description of the {gamma}-PHA acquisitions, of the modeling, and of the calculations of nuclide content. Because each of the remediation facilities is unique and ergonomically unfavorable to {gamma}-ray acquisitions, we have constructed custom detector support devices specific to each set of acquisitions. This paper includes a description and photographs of these custom devices. The description of modeling and calculations include determination and application of container and matrix photon energy dependent absorption factors and also determination and application of geometry factors relative to our detector calibration geometry. The paper also includes a discussion of our measurements accuracy using off-line assays of two SRNL HEPA filters. The comparison includes assay of the filters inside of 55-gallon drums using the SRNL Q{sup 2} assay system and separately using off-line assay with an acquisition configuration unique from the original in-situ acquisitions.

Dewberry, R; Donald Pak, D

2007-05-04T23:59:59.000Z

283

WIPP Project Plan Descriptions Waste Characterization (LANL, SRS, Oak Ridge) Baseline Inspections  

E-Print Network [OSTI]

farm in Hanford, WA. As part of the 2006 WIPP Recertification Decision, DOE committed to implement a process for evaluating whether Hanford tank waste, and possibly other wastes, meets the definition of TRU (NMED). o For recertification purposes, the Hanford tank waste in question has been removed from

284

Characterization of 618-11 solid waste burial ground, disposed waste, and description of the waste generating facilities  

SciTech Connect (OSTI)

The 618-11 (Wye or 318-11) burial ground received transuranic (TRTJ) and mixed fission solid waste from March 9, 1962, through October 2, 1962. It was then closed for 11 months so additional burial facilities could be added. The burial ground was reopened on September 16, 1963, and continued operating until it was closed permanently on December 31, 1967. The burial ground received wastes from all of the 300 Area radioactive material handling facilities. The purpose of this document is to characterize the 618-11 solid waste burial ground by describing the site, burial practices, the disposed wastes, and the waste generating facilities. This document provides information showing that kilogram quantities of plutonium were disposed to the drum storage units and caissons, making them transuranic (TRU). Also, kilogram quantities of plutonium and other TRU wastes were disposed to the three trenches, which were previously thought to contain non-TRU wastes. The site burial facilities (trenches, caissons, and drum storage units) should be classified as TRU and the site plutonium inventory maintained at five kilograms. Other fissile wastes were also disposed to the site. Additionally, thousands of curies of mixed fission products were also disposed to the trenches, caissons, and drum storage units. Most of the fission products have decayed over several half-lives, and are at more tolerable levels. Of greater concern, because of their release potential, are TRU radionuclides, Pu-238, Pu-240, and Np-237. TRU radionuclides also included slightly enriched 0.95 and 1.25% U-231 from N-Reactor fuel, which add to the fissile content. The 618-11 burial ground is located approximately 100 meters due west of Washington Nuclear Plant No. 2. The burial ground consists of three trenches, approximately 900 feet long, 25 feet deep, and 50 feet wide, running east-west. The trenches constitute 75% of the site area. There are 50 drum storage units (five 55-gallon steel drums welded together) buried in three rows in the northeast comer. In addition, five eight-foot diameter caissons are located at the west end of the center row of the drum storage units. Initially, wastes disposed to the caissons and drum storage units were from the 325 and 327 building hot cells. Later, a small amount of remote-handled (RH) waste from the 309 building Plutonium Recycle Test Reactor (PRTR) cells, and the newly built 324 building hot cells, was disposed at the site.

Hladek, K.L.

1997-10-07T23:59:59.000Z

285

A little here, a little there, a fairly big problem everywhere: Small quantity site transuranic waste disposition alternatives  

SciTech Connect (OSTI)

Small quantities of transuranic (TRU) waste represent a significant challenge to the waste disposition and facility closure plans of several sites in the Department of Energy (DOE) complex. This paper presents the results of a series of evaluations, using a systems engineering approach, to identify the preferred alternative for dispositioning TRU waste from small quantity sites (SQSs). The TRU waste disposition alternatives evaluation used semi-quantitative data provided by the SQSs, potential receiving sites, and the Waste Isolation Pilot Plant (WIPP) to select and recommend candidate sites for waste receipt, interim storage, processing, and preparation for final disposition of contact-handled (CH) and remote-handled (RH) TRU waste. The evaluations of only four of these SQSs resulted in potential savings to the taxpayer of $33 million to $81 million, depending on whether mobile systems could be used to characterize, package, and certify the waste or whether each site would be required to perform this work. Small quantity shipping sites included in the evaluation included the Battelle Columbus Laboratory (BCL), University of Missouri Research Reactor (MURR), Energy Technology Engineering Center (ETEC), and Mound Laboratory. Candidate receiving sites included the Idaho National Engineering and Environmental Laboratory (INEEL), the Savannah River Site (SRS), Los Alamos National Laboratory (LANL), Oak Ridge (OR), and Hanford. At least 14 additional DOE sites having TRU waste may be able to save significant money if cost savings are similar to the four evaluated thus far.

D. Luke; D. Parker; J. Moss; T. Monk (INEEL); L. Fritz (DOE-ID); B. Daugherty (SRS); K. Hladek (WM Federal Services Hanford); S. Kosiewicx (LANL)

2000-02-27T23:59:59.000Z

286

A Little Here, A Little There, A Fairly Big Problem Everywhere: Small Quantity Site Transuranic Waste Disposition Alternatives  

SciTech Connect (OSTI)

Small quantities of transuranic (TRU) waste represent a significant challenge to the waste disposition and facility closure plans of several sites in the Department of Energy (DOE) complex. This paper presents the results of a series of evaluations, using a systems engineering approach, to identify the preferred alternative for dispositioning TRU waste from small quantity sites (SQSs). The TRU waste disposition alternatives evaluation used semi-quantitative data provided by the SQSs, potential receiving sites, and the Waste Isolation Pilot Plant (WIPP) to select and recommend candidate sites for waste receipt, interim storage, processing, and preparation for final disposition of contact-handled (CH) and remote-handled (RH) TRU waste. The evaluations of only four of these SQSs resulted in potential savings to the taxpayer of $33 million to $81 million, depending on whether mobile systems could be used to characterize, package, and certify the waste or whether each site would be required to perform this work. Small quantity shipping sites included in the evaluation included the Battelle Columbus Laboratory (BCL), University of Missouri Research Reactor (MURR), Energy Technology Engineering Center (ETEC), and Mound. Candidate receiving sites included the Idaho National Engineering and Environmental Laboratory (INEEL), the Savannah River Site (SRS), Los Alamos National Laboratory (LANL), Oak Ridge (OR), and Hanford. At least 14 additional DOE sites having TRU waste may be able to save significant money if cost savings are similar to the four evaluated thus far.

Luke, Dale Elden; Parker, Douglas Wayne; Moss, J.; Monk, Thomas Hugh; Fritz, Lori Lee; Daugherty, B.; Hladek, K.; Kosiewicx, S.

2000-03-01T23:59:59.000Z

287

DOE assay methods used for characterization of contact-handled transuranic waste  

SciTech Connect (OSTI)

US Department of Energy methods used for characterization of contact-handled transuranic (CH-TRU) waste prior to shipment to the Waste Isolation Pilot Plant (WIPP) are described and listed by contractor site. The methods described are part of the certification process. All CH-TRU waste must be assayed for determination of fissile material content and decay heat values prior to shipment and prior to storage on-site. Both nondestructive assay (NDA) and destructive assay methods are discussed, and new NDA developments such as passive-action neutron (PAN) crate counter improvements and neutron imaging are detailed. Specifically addressed are assay method physics; applicability to CH-TRU wastes; calibration standards and implementation; operator training requirements and practices; assay procedures; assay precision, bias, and limit of detection; and assay limitation. While PAN is a new technique and does not yet have established American Society for Testing and Materials. American National Standards Institute, or Nuclear Regulatory Commission guidelines or methods describing proper calibration procedures, equipment setup, etc., comparisons of PAN data with the more established assay methods (e.g., segmented gamma scanning) have demonstrated its reliability and accuracy. Assay methods employed by DOE have been shown to reliable and accurate in determining fissile, radionuclide, alpha-curie content, and decay heat values of CH-TRU wastes. These parameters are therefore used to characterize packaged waste for use in certification programs such as that used in shipment of CH-TRU waste to the WIPP. 36 refs., 10 figs., 7 tabs.

Schultz, F.J. (Oak Ridge National Lab., TN (United States)); Caldwell, J.T. (Pajarito Scientific Corp., Los Alamos, NM (United States))

1991-08-01T23:59:59.000Z

288

Nondestructive characterization of low-level transuranic waste  

SciTech Connect (OSTI)

The use of nondestructive evaluation (NDE) methods is proposed for characterization of transuranic (TRU) waste stored at the Radioactive Waste Management Complex. These NDE methods include real-time x-ray radiography, real-time neutron radiography, x-ray and neutron computed tomography, thermal imaging, container weighing, visual examination, and acoustic measurements. An integrated NDE system is proposed for characterization and certification of TRU waste destined for eventual shipment to the Waste Isolation Pilot Plant in New Mexico. Methods for automating both the classification waste and control of a complete nondestructive evaluation/nondestructive assay system are presented. Feasibility testing of the different NDE methods, including real-time x-ray radiography, and development of automated waste classification techniques are covered as part of a five year effort designed to yield a production waste characterization system.

Barna, B.A.; Reinhardt, W.W.

1981-10-01T23:59:59.000Z

289

Linking Legacies: Connecting the Cold War Nuclear Weapons Production...  

Energy Savers [EERE]

Linking Legacies: Connecting the Cold War Nuclear Weapons Production Processes to Their Environmental Consequences Linking Legacies: Connecting the Cold War Nuclear Weapons...

290

Effects of Intermediate Ethanol Blends on Legacy Vehicles and...  

Energy Savers [EERE]

Effects of Intermediate Ethanol Blends on Legacy Vehicles and Small Non-Road Engines, Report 1 Updated Feb 2009 Effects of Intermediate Ethanol Blends on Legacy Vehicles and...

291

Energy Department Awards Small Business Contract for Legacy Management...  

Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

Business Contract for Legacy Management Work to S.M. Stoller Corporation Energy Department Awards Small Business Contract for Legacy Management Work to S.M. Stoller...

292

Oak Ridge National Laboratory TRU Waste Processing Center Tank Waste Processing Supernate Processing System  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of Energy Power.pdf11-161-LNG |September 15, 2010 PrintingNeed|3 ANNUAL REPORT3 ORSSABSafetySource TermORNL

293

Solid waste 30-year volume summary  

SciTech Connect (OSTI)

A 30-year forecast of the solid waste volumes to be generated or received at the US Department of Energy Hanford Site is described in this report. The volumes described are low-level mixed waste (LLMW) and transuranic/transuranic mixed (TRU/TRUM) waste that will require treatment, storage, and disposal at Hanford`s Solid Waste Operations Complex (SWOC) during the 30-year period from FY 1994 through FY 2023. The data used to complete this document were collected from onsite and offsite waste generators who currently, or are planning to, ship solid wastes to the Hanford Site. An analysis of the data suggests that over 300,000 m{sup 3} of LLMW and TRU/TRUM waste will be managed at Hanford`s SWOC over the next 30 years. An extensive effort was made this year to collect this information. The 1993 solid waste forecast was used as a starting point, which identified approximately 100,000 m{sup 3} of LLMW and TRU/TRUM waste to be sent to the SWOC. After analyzing the forecast waste volume, it was determined that additional waste was expected from the tank waste remediation system (TWRS), onsite decontamination and decommissioning (D&D) activities, and onsite remedial action (RA) activities. Data presented in this report establish a starting point for solid waste management planning. It is recognized that forecast estimates will vary (typically increasing) as facility planning and missions continue to change and become better defined, but the information presented still provides useful insight into Hanford`s future solid waste management requirements.

Valero, O.J.; Armacost, L.L.; DeForest, T.J.; Templeton, K.J.; Williams, N.C.

1994-06-01T23:59:59.000Z

294

LWR First Recycle of TRU with Thorium Oxide for Transmutation and Cross Sections  

SciTech Connect (OSTI)

Thorium has been considered as an option to uranium-based fuel, based on considerations of resource utilization (thorium is approximately three times more plentiful than uranium) and as a result of concerns about proliferation and waste management (e.g. reduced production of plutonium, etc.). Since the average composition of natural Thorium is dominated (100%) by the fertile isotope Th-232, Thorium is only useful as a resource for breeding new fissile materials, in this case U-233. Consequently a certain amount of fissile material must be present at the start-up of the reactor in order to guarantee its operation. The thorium fuel can be used in both once-through and recycle options, and in both fast and thermal spectrum systems. The present study has been aimed by the necessity of investigating the option of using reprocessed plutonium/TRU, from a once-through reference LEU scenario (50 GWd/ tIHM), mixed with natural thorium and the need of collect data (mass fractions, cross-sections etc.) for this particular fuel cycle scenario. As previously pointed out, the fissile plutonium is needed to guarantee the operation of the reactor. Four different scenarios have been considered: • Thorium – recycled Plutonium; • Thorium – recycled Plutonium/Neptunium; • Thorium – recycled Plutonium/Neptunium/Americium; • Thorium – recycled Transuranic. The calculations have been performed with SCALE6.1-TRITON.

Andrea Alfonsi; Gilles Youinou

2012-07-01T23:59:59.000Z

295

LWR First Recycle of TRU with Thorium Oxide for Transmutation and Cross Sections  

SciTech Connect (OSTI)

Thorium has been considered as an option to uranium-based fuel, based on considerations of resource utilization (thorium is approximately three times more plentiful than uranium) and as a result of concerns about proliferation and waste management (e.g. reduced production of plutonium, etc.). Since the average composition of natural Thorium is dominated (100%) by the fertile isotope Th-232, Thorium is only useful as a resource for breeding new fissile materials, in this case U-233. Consequently a certain amount of fissile material must be present at the start-up of the reactor in order to guarantee its operation. The thorium fuel can be used in both once-through and recycle options, and in both fast and thermal spectrum systems. The present study has been aimed by the necessity of investigating the option of using reprocessed plutonium/TRU, from a once-through reference LEU scenario (50 GWd/ tIHM), mixed with natural thorium and the need of collect data (mass fractions, cross-sections etc.) for this particular fuel cycle scenario. As previously pointed out, the fissile plutonium is needed to guarantee the operation of the reactor. Four different scenarios have been considered: • Thorium – recycled Plutonium; • Thorium – recycled Plutonium/Neptunium; • Thorium – recycled Plutonium/Neptunium/Americium; • Thorium – recycled Transuranic. The calculations have been performed with SCALE6.1-TRITON.

Andrea Alfonsi; Gilles Youinou; Sonat Sen

2013-02-01T23:59:59.000Z

296

Management activities for retrieved and newly generated transuranic waste, Savannah River Plant  

SciTech Connect (OSTI)

The purpose of this Environmental Assessment (EA) is to assess the potential environmental impacts of the retrieval and processing of retrieved and newly generated transuranic (TRU) radioactive waste at the Savannah River Plant (SRP), including the transportation of the processes TRU waste to the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. A new TRU Waste Facility (TWF) will be constructed at SRP to retrieve and process the SRP TRU waste in interim storage to meet WIPP criteria. This EA has been prepared in compliance with the National Environmental Policy Act (NEPA) of 1969, as amended, and the requirements of the Council of Environmental Quality Regulations for implementing NEPA (40 CFR Parts 1500--1508). The National Environmental Policy Act (NEPA) requires the assessment of environmental consequences of all major federal actions that may affect the quality of the human environment. This document describes the environmental impact of constructing and operating the TWF facility for processing and shipment of the TRU waste to WIPP and considers alternatives to the proposed action. 40 refs., 12 figs., 12 tabs.

Not Available

1988-08-01T23:59:59.000Z

297

Contact-Handled Transuranic Waste Acceptance Criteria for the Waste Isolation Pilot Plant  

SciTech Connect (OSTI)

The purpose of this document is to summarize the waste acceptance criteria applicable to the transportation, storage, and disposal of contact-handled transuranic (CH-TRU) waste at the Waste Isolation Pilot Plant (WIPP). These criteria serve as the U.S. Department of Energy's (DOE) primary directive for ensuring that CH-TRU waste is managed and disposed of in a manner that protects human health and safety and the environment.The authorization basis of WIPP for the disposal of CH-TRU waste includes the U.S.Department of Energy National Security and Military Applications of Nuclear EnergyAuthorization Act of 1980 (reference 1) and the WIPP Land Withdrawal Act (LWA;reference 2). Included in this document are the requirements and associated criteriaimposed by these acts and the Resource Conservation and Recovery Act (RCRA,reference 3), as amended, on the CH-TRU waste destined for disposal at WIPP.|The DOE TRU waste sites must certify CH-TRU waste payload containers to thecontact-handled waste acceptance criteria (CH-WAC) identified in this document. Asshown in figure 1.0, the flow-down of applicable requirements to the CH-WAC istraceable to several higher-tier documents, including the WIPP operational safetyrequirements derived from the WIPP CH Documented Safety Analysis (CH-DSA;reference 4), the transportation requirements for CH-TRU wastes derived from theTransuranic Package Transporter-Model II (TRUPACT-II) and HalfPACT Certificates ofCompliance (references 5 and 5a), the WIPP LWA (reference 2), the WIPP HazardousWaste Facility Permit (reference 6), and the U.S. Environmental Protection Agency(EPA) Compliance Certification Decision and approval for PCB disposal (references 7,34, 35, 36, and 37). The solid arrows shown in figure 1.0 represent the flow-down of allapplicable payload container-based requirements. The two dotted arrows shown infigure 1.0 represent the flow-down of summary level requirements only; i.e., the sitesmust reference the regulatory source documents from the U.S. Nuclear RegulatoryCommission (NRC) and the New Mexico Environment Department (NMED) for acomprehensive and detailed listing of the requirements.This CH-WAC does not address the subject of waste characterization relating to adetermination of whether the waste is hazardous; rather, the sites are referred to theWaste Analysis Plan (WAP) contained in the WIPP Hazardous Waste Facility Permit fordetails of the sampling and analysis protocols to be used in determining compliance withthe required physical and chemical properties of the waste. Requirements andassociated criteria pertaining to a determination of the radiological properties of thewaste, however, are addressed in appendix A of this document. The collectiveinformation obtained from waste characterization records and acceptable knowledge(AK) serves as the basis for sites to certify that their CH-TRU waste satisfies the WIPPwaste acceptance criteria listed herein.

Washington TRU Solutions LLC

2005-12-29T23:59:59.000Z

298

Quality assurance program plan for cesium legacy project  

SciTech Connect (OSTI)

This Quality Assurance Program Plan (QAPP) provides information on how the Quality Assurance Program is implemented for the Cesium Legacy Project. It applies to those items and tasks which affect the completion of activities identified in the work breakdown structure of the Project Management Plan (PMP). These activities include all aspects of cask transportation, project related operations within the 324 Building, and waste management as it relates to the specific activities of this project. General facility activities (i.e. 324 Building Operations, Central Waste Complex Operations, etc.) are covered in other appropriate QAPPs. The 324 Building is currently transitioning from being a Pacific Northwest National Laboratory (PNNL) managed facility to a B and W Hanford Company (BWHC) managed facility. During this transition process existing PNNL procedures and documents will be utilized until replaced by BWHC procedures and documents.

Tanke, J.M.

1997-05-22T23:59:59.000Z

299

Identification of potential transuranic waste tanks at the Hanford Site  

SciTech Connect (OSTI)

The purpose of this document is to identify potential transuranic (TRU) material among the Hanford Site tank wastes for possible disposal at the Waste Isolation Pilot Plant (WIPP) as an alternative to disposal in the high-level waste (HLW) repository. Identification of such material is the initial task in a trade study suggested in WHC-EP-0786, Tank Waste Remediation System Decisions and Risk Assessment (Johnson 1994). The scope of this document is limited to the identification of those tanks that might be segregated from the HLW for disposal as TRU, and the bases for that selection. It is assumed that the tank waste will be washed to remove soluble inert material for disposal as low-level waste (LLW), and the washed residual solids will be vitrified for disposal. The actual recommendation of a disposal strategy for these materials will require a detailed cost/benefit analysis and is beyond the scope of this document.

Colburn, R.P.

1995-05-05T23:59:59.000Z

300

"TRU" Success: SRS Recovery Act Prepares to Complete Shipment...  

Broader source: Energy.gov (indexed) [DOE]

More Than 5,000 Cubic Meters of Nuclear Waste to WIPP More Documents & Publications TRUPACT-III Quick Facts EIS-0026-SA-06: Supplement Analysis Waste Isolation Pilot Plant Update...

Note: This page contains sample records for the topic "legacy tru waste" 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

Overview of the Government of Canada Nuclear Legacy Liabilities Program - 13551  

SciTech Connect (OSTI)

Nuclear legacy liabilities have resulted from more than 60 years of nuclear research and development carried out on behalf of Canada. The liabilities are located at Atomic Energy of Canada Limited's (AECL) Chalk River Laboratories in Ontario and Whiteshell Laboratories in Manitoba, as well as three shutdown prototype reactors in Ontario and Quebec that are being maintained in a safe storage state. Estimated at about $7.4 billion (current day dollars), these liabilities consist of disused nuclear facilities and associated infrastructure, a wide variety of buried and stored waste, and contaminated lands. In 2006, the Government of Canada adopted a long-term strategy to deal with the nuclear legacy liabilities and initiated a five-year, $520 million start-up phase, thereby creating the Nuclear Legacy Liabilities Program (NLLP). The Government of Canada renewed the NLLP in 2011 with a $439-million three-year second phase that ends March 31, 2014. The projects and activities carried out under the Program focus on infrastructure decommissioning, environmental restoration, improving the management of legacy radioactive waste, and advancing the long-term strategy. The NLLP is being implemented through a Memorandum of Understanding between Natural Resources Canada (NRCan) and AECL whereby NRCan is responsible for policy direction and oversight, including control of funding, and AECL is responsible for implementing the program of work and holding and administering all licences, facilities and lands. (authors)

Metcalfe, D.; McCauley, D. [Natural Resources Canada, Ottawa, Ontario, K1A 0E4 (Canada)] [Natural Resources Canada, Ottawa, Ontario, K1A 0E4 (Canada); Miller, J.; Brooks, S. [Atomic Energy of Canada Limited, Chalk River, Ontario, K0J 1J0 (Canada)] [Atomic Energy of Canada Limited, Chalk River, Ontario, K0J 1J0 (Canada)

2013-07-01T23:59:59.000Z

302

Los Alamos National Laboratory transuranic waste quality assurance project plan. Revision 1  

SciTech Connect (OSTI)

This Transuranic (TRU) Waste Quality Assurance Project Plan (QAPjP) serves as the quality management plan for the characterization of transuranic waste in preparation for certification and transportation. The Transuranic Waste Characterization/Certification Program (TWCP) consists of personnel who sample and analyze waste, validate and report data; and provide project management, quality assurance, audit and assessment, and records management support, all in accordance with established requirements for disposal of TRU waste at the Waste Isolation Pilot Plant (WIPP) facility. This QAPjP addresses how the TWCP meets the quality requirements of the Carlsbad Area Office (CAO) Quality Assurance Program Description (QAPD) and the technical requirements of the Transuranic Waste Characterization Quality Assurance Program Plan (QAPP). The TWCP characterizes and certifies retrievably stored and newly generated TRU waste using the waste selection, testing, sampling, and analytical techniques and data quality objectives (DQOs) described in the QAPP, the Los Alamos National Laboratory Transuranic Waste Certification Plan (Certification Plan), and the CST Waste Management Facilities Waste Acceptance Criteria and Certification [Los Alamos National Laboratory (LANL) Waste Acceptance Criteria (WAC)]. At the present, the TWCP does not address remote-handled (RH) waste.

NONE

1997-04-14T23:59:59.000Z

303

Los Alamos Transuranic Waste Size Reduction Facility  

SciTech Connect (OSTI)

The Los Alamos Transuranic (TRU) Waste Size Reduction Facility (SRF) is a production oriented prototype. The facility is operated to remotely cut and repackage TRU contaminated metallic wastes (e.g., glove boxes, ducting and pipes) for eventual disposal at the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. The resulting flat sections are packaged into a tested Department of Transportation Type 7A metal container. To date, the facility has successfully processed stainless steel glove boxes (with and without lead shielding construction) and retention tanks. We have found that used glove boxes generate more cutting fumes than do unused glove boxes or metal plates - possibly due to deeply embedded chemical residues from years of service. Water used as a secondary fluid with the plasma arc cutting system significantly reduces visible fume generation during the cutting of used glove boxes and lead-lined glove boxes. 2 figs., 1 tab.

Harper, J.; Warren, J.

1987-06-01T23:59:59.000Z

304

Application of Fully Ceramic Microencapsulated Fuel for Transuranic Waste Recycling in PWRs  

SciTech Connect (OSTI)

Presented is an investigation of the utilization of Tristructural-Isotropic (TRISO) particle-based fuel designs for the recycling of transuranic (TRU) wastes in typical Westinghouse four-loop pressurized water reactors (PWRs). Though numerous studies have evaluated the recycling of TRU in light water reactors (LWRs), this work differentiates itself by employing TRU-loaded TRISO particles embedded within a SiC matrix and formed into pellets that can be loaded into standard 17 x 17 fuel element cladding. This approach provides the capability of TRU recycling and, by virtue of the TRISO particle design, will allow for greater burnup (i.e., removal of the need for UO2 mixing) and improved fuel reliability. In this study, a variety of assembly layouts and core loading patterns were analyzed to demonstrate the feasibility of TRU-loaded TRISO fuel. The assembly and core design herein reported are a work in progress, so they still require some fine-tuning to further flatten power peaks; however, the progress achieved thus far strongly supports the conclusion that with further rod/assembly/core loading and placement optimization, TRU-loaded TRISO fuel and core designs that are capable of balancing TRU production and destruction can be designed within the standard constraints for thermal and reactivity performance in PWRs.

Gentry, Cole A [ORNL; Maldonado, G Ivan [ORNL; Terrani, Kurt A [ORNL; Gehin, Jess C [ORNL; Godfrey, Andrew T [ORNL

2012-01-01T23:59:59.000Z

305

Controlling Beryllium Contaminated Material And Equipment For The Building 9201-5 Legacy Material Disposition Project  

SciTech Connect (OSTI)

This position paper addresses the management of beryllium contamination on legacy waste. The goal of the beryllium management program is to protect human health and the environment by preventing the release of beryllium through controlling surface contamination. Studies have shown by controlling beryllium surface contamination, potential airborne contamination is reduced or eliminated. Although there are areas in Building 9201-5 that are contaminated with radioactive materials and mercury, only beryllium contamination is addressed in this management plan. The overall goal of this initiative is the compliant packaging and disposal of beryllium waste from the 9201-5 Legacy Material Removal (LMR) Project to ensure that beryllium surface contamination and any potential airborne release of beryllium is controlled to levels as low as practicable in accordance with 10 CFR 850.25.

Reynolds, T. D.; Easterling, S. D.

2010-10-01T23:59:59.000Z

306

DOE Exercises 5 Year Option on Washington TRU Solutions Contract...  

Office of Environmental Management (EM)

and operating the Department's Waste Isolation Pilot Plant (WIPP), located in New Mexico. The option DOE exercised is a part of the WIPP contract that was competitively...

307

Lessons Learned and Present Day Challenges of Addressing 20th Century Radiation Legacies of Russia and the United States  

SciTech Connect (OSTI)

The decommissioning of nuclear submarines, disposal of highly-enriched uranium and weapons-grade plutonium, and processing of high-level radioactive wastes represent the most challenging issues facing the cleanup of 20th century radiation legacy wastes and facilities. The US and Russia are the two primary countries dealing with these challenges, because most of the world's fissile inventory is being processed and stored at multiple industrial sites and nuclear weapons production facilities in these countries.

KRISTOFZSKI, J.G.

2000-10-26T23:59:59.000Z

308

Complications Associated with Long-Term Disposition of Newly-Generated Transuranic Waste: A National Laboratory Perspective  

SciTech Connect (OSTI)

The Idaho National Laboratory (INL) is a multipurpose national laboratory delivering specialized science and engineering solutions for the U.S. Department of Energy (DOE). Sponsorship of INL was formally transferred to the DOE Office of Nuclear Energy, Science and Technology (NE) by Secretary Spencer Abraham in July 2002. The move to NE, and designation as the DOE lead nuclear energy laboratory for reactor technology, supports the nation’s expanding nuclear energy initiatives, placing INL at the center of work to develop advanced Generation IV nuclear energy systems; nuclear energy/hydrogen coproduction technology; advanced nuclear energy fuel cycle technologies; and providing national security answers to national infrastructure needs. As a result of the Laboratory’s NE mission, INL generates both contact-handled and remote-handled transuranic (TRU) waste from ongoing operations. Generation rates are relatively small and fluctuate based on specific programs and project activities being conducted; however, the Laboratory will continue to generate TRU waste well into the future in association with the NE mission. Currently, plans and capabilities are being established to transfer INL’s contact-handled TRU waste to the Advanced Mixed Waste Treatment Plant (AMWTP) for certification and disposal to the Waste Isolation Pilot Plant (WIPP). Remote-handled TRU waste is currently placed in storage at the Materials and Fuels Complex (MFC). In an effort to minimize future liabilities associated with the INL NE mission, INL is evaluating and assessing options for the management and disposition of all its TRU waste on a real-time basis at time of generation. This paper summarizes near-term activities to minimize future re handling of INL’s TRU waste, as well as, potential complications associated with the long-term disposition of newly-generated TRU waste. Potential complications impacting the disposition of INL newly-generated TRU waste include, but are not limited to: 1) required remote-handled TRU packaging configuration(s) vs. current facility capabilities, 2) long-term NE mission activities, 3) WIPP certification requirements, and 4) budget considerations.

B.J. Orchard; L.A. Harvego; T.L. Carlson; R.P. Grant

2009-03-01T23:59:59.000Z

309

Long-Term Performance of Transuranic Waste Inadvertently Disposed in a Shallow Land Burial Trench at the Nevada Test Site  

SciTech Connect (OSTI)

In 1986, 21 m3 of transuranic (TRU) waste was inadvertently disposed in a shallow land burial trench at the Area 5 Radioactive Waste Management Site on the Nevada Test Site. U.S. Department of Energy (DOE) TRU waste must be disposed in accordance with Title 40, Code of Federal Regulations (CFR), Part 191, Environmental Radiation Protection Standard for Management and Disposal of Spent Nuclear Fuel, High-Level, and Transuranic Radioactive Wastes. The Waste Isolation Pilot Plant is the only facility meeting these requirements. The National Research Council, however, has found that exhumation of buried TRU waste for disposal in a deep geologic repository may not be warranted when the effort, exposures, and expense of retrieval are not commensurate with the risk reduction achieved. The long-term risks of leaving the TRU waste in-place are evaluated in two probabilistic performance assessments. A composite analysis, assessing the dose from all disposed waste and interacting sources of residual contamination, estimates an annual total effective dose equivalent (TEDE) of 0.01 mSv, or 3 percent of the dose constraint. A 40 CFR 191 performance assessment also indicates there is reasonable assurance of meeting all requirements. The 40 CFR 191.15 annual mean TEDE for a member of the public is estimated to reach a maximum of 0.055 mSv at 10,000 years, or approximately 37 percent of the 0.15 mSv individual protection requirement. In both assessments greater than 99 percent of the dose is from co-disposed low-level waste. The simulated probability of the 40 CFR 191.13 cumulative release exceeding 1 and 10 times the release limit is estimated to be 0.0093 and less than 0.0001, respectively. Site characterization data and hydrologic process modeling support a conclusion of no groundwater pathway within 10,000 years. Monte Carlo uncertainty analysis indicates that there is reasonable assurance of meeting all regulatory requirements. Sensitivity analysis indicates that the results are insensitive to TRU waste-related parameters. Limited quantities of TRU waste in a shallow land burial trench can meet DOE performance objectives for disposal of TRU waste and contribute negligibly to disposal site risk. Leaving limited quantities of buried TRU waste in-place may be preferred over retrieval for disposal in a deep geologic repository.

Gregory J. Shott; Vefa Yucel

2009-07-16T23:59:59.000Z

310

Los Alamos National Laboratory Waste Management Program  

SciTech Connect (OSTI)

Los Alamos National Laboratory's (LANL) waste management program is responsible for disposition of waste generated by many of the LANL programs and operations. LANL generates liquid and solid waste that can include radioactive, hazardous, and other constituents. Where practical, LANL hazardous and mixed wastes are disposed through commercial vendors; low-level radioactive waste (LLW) and radioactive asbestos-contaminated waste are disposed on site at LANL's Area G disposal cells, transuranic (TRU) waste is disposed at the Waste Isolation Pilot Plant (WIPP), and high-activity mixed wastes are disposed at the Nevada Test Site (NTS) after treatment by commercial vendors. An on-site radioactive liquid waste treatment facility (RLWTF) removes the radioactive constituents from liquid wastes and treated water is released through an NPDES permitted outfall. LANL has a very successful waste minimization program. Routine hazardous waste generation has been reduced over 90% since 1993. LANL has a DOE Order 450.1-compliant environmental management system (EMS) that is ISO 14001 certified; waste minimization is integral to setting annual EMS improvement objectives. Looking forward, under the new LANL management and operating contractor, Los Alamos National Security (LANS) LLC, a Zero Liquid Discharge initiative is being planned that should eliminate flow to the RLWTF NPDES-permitted outfall. The new contractor is also taking action to reduce the number of permitted waste storage areas, to charge generating programs directly for the cost to disposition waste, and to simplify/streamline the waste system. (authors)

Lopez-Escobedo, G.M.; Hargis, K.M.; Douglass, C.R. [Los Alamos National Laboratory, NM (United States)

2007-07-01T23:59:59.000Z

311

Waste Acceptance for Vitrified Sludge from Oak Ridge Tank Farms  

SciTech Connect (OSTI)

The Tanks Focus Area of the DOE`s Office of Science and Technology (EM-50) has funded the Savannah River Technology Center (SRTC) to develop formulations which can incorporate sludges from Oak Ridge Tank Farms into immobilized glass waste forms. The four tank farms included in this study are: Melton Valley Storage Tanks (MVST), Bethel Valley Evaporation Service Tanks (BVEST), Gunite and Associated Tanks (GAAT), and Old Hydrofracture Tanks (OHF).The vitrified waste forms must be sent for disposal either at the Waste Isolation Pilot Plant (WIPP) or the Nevada Test Site (NTS). Waste loading in the glass is the major factor in determining where the waste will be sent and whether the waste will be remote-handled (RH) or contact-handled (CH). In addition, the waste loading significantly impacts the costs of vitrification operations and transportation to and disposal within the repository.This paper focuses on disposal options for the vitrified Oak Ridge Tank sludge waste as determined by the WIPP (1) and NTS (2) Waste Acceptance Criteria (WAC). The concentrations for both Transuranic (TRU) and beta/gamma radionuclides in the glass waste form will be presented a a function of sludge waste loading. These radionuclide concentrations determine whether the waste forms will be TRU (and therefore disposed of at WIPP) and whether the waste forms will be RH or CH.

Harbour, J.R. [Westinghouse Savannah River Company, AIKEN, SC (United States); Andrews, M.K.

1998-03-01T23:59:59.000Z

312

Description of processes for the immobilization of selected transuranic wastes  

SciTech Connect (OSTI)

Processed sludge and incinerator-ash wastes contaminated with transuranic (TRU) elements may require immobilization to prevent the release of these elements to the environment. As part of the TRU Waste Immobilization Program sponsored by the Department of Energy (DOE), the Pacific Northwest Laboratory is developing applicable waste-form and processing technology that may meet this need. This report defines and describes processes that are capable of immobilizing a selected TRU waste-stream consisting of a blend of three parts process sludge and one part incinerator ash. These selected waste streams are based on the compositions and generation rates of the waste processing and incineration facility at the Rocky Flats Plant. The specific waste forms that could be produced by the described processes include: in-can melted borosilicate-glass monolith; joule-heated melter borosilicate-glass monolith or marble; joule-heated melter aluminosilicate-glass monolith or marble; joule-heated melter basaltic-glass monolith or marble; joule-heated melter glass-ceramic monolith; cast-cement monolith; pressed-cement pellet; and cold-pressed sintered-ceramic pellet.

Timmerman, C.L.

1980-12-01T23:59:59.000Z

313

Waste Isolation Pilot Plant Annual Site Enviromental Report for 2008  

SciTech Connect (OSTI)

The purpose of the Waste Isolation Pilot Plant Annual Site Environmental Report for 2008 (ASER) is to provide information required by U.S. Department of Energy (DOE) Order 231.1A, Environment, Safety, and Health Reporting. Specifically, the ASER presents summary environmental data to characterize site environmental management performance; summarize environmental occurrences and responses reported during the calendar year; confirm compliance with environmental standards and requirements; highlight significant facility programs and efforts; and describe how compliance and environmental improvement is accomplished through the WIPP Environmental Management System (EMS). The DOE Carlsbad Field Office (CBFO) and the management and operating contractor (MOC), Washington TRU Solutions LLC (WTS), maintain and preserve the environmental resources at the Waste Isolation Pilot Plant (WIPP). DOE Order 231.1A; DOE Order 450.1A, Environmental Protection Program; and DOE Order 5400.5, Radiation Protection of the Public and the Environment, require that the affected environment at and near DOE facilities be monitored to ensure the safety and health of the public and workers, and preservation of the environment. This report was prepared in accordance with DOE Order 231.1A, which requires that DOE facilities submit an ASER to the DOE Headquarters Chief Health, Safety, and Security Officer. The WIPP Hazardous Waste Facility Permit (HWFP) Number NM4890139088-TSDF (treatment, storage, and disposal facility) further requires that the ASER be provided to the New Mexico Environment Department (NMED). The WIPP mission is to safely dispose of transuranic (TRU) radioactive waste generated by the production of nuclear weapons and other activities related to the national defense of the United States. In 2008, 5,265 cubic meters (m3) of TRU waste were disposed of at the WIPP facility, including 5,216 m3 of contact-handled (CH) TRU waste and 49 m3 of remote-handled (RH) TRU waste. From the first receipt of waste in March 1999 through the end of 2008, 57,873 m3 of TRU waste had been disposed of at the WIPP facility.

Washington Regulatory and Enviromnetal Services

2009-09-21T23:59:59.000Z

314

A new DOE standard for transuranic waste nuclear safety analysis  

SciTech Connect (OSTI)

The DOE Office of Environmental Management (EM) observed through onsite assessments and a review of site-specific lessons learned that transuranic (TRU) waste operations could benefit from standardization of assumptions and approaches used to analyze hazards and select controls. EM collected and compared safety analysis information from DOE sites, including a comparison of the type of TRU waste accidents evaluated and controls selected, as well as specific Airborne Release Fractions (ARFs), Respirable Fractions (RFs), and Damage Ratios (DRs) assumed in accident analyses. This paper recounts the efforts by the DOE and its contractors to bring consistency to the safety analysis process supporting TRU waste operations through an integrated re-engineering effort. EM embarked on a process to re-engineer and standardize TRU safety analysis activities complex-wide. The effort involved DOE headquarters, field offices, and contractors. Five teams were formed to analyze and develop the necessary technical basis for a DOE Technical Standard. The teams looked at general issues including Safety Basis (SB), drum integrity and inspection criteria, hazard controls and analysis, safety analysis review and approval process, and implementation of hazard controls. (authors)

Triay, I.; Chung, D. [U.S. Department of Energy, Washington, D.C. (United States); Woody, J. [Atlas Consulting, Knoxville, TN (United States); Foppe, T. [Carlsbad Technical Assistance Contractor, Carlsbad, NM (United States); Mewhinney, C. [Sandia National Laboratories, Carlsbad, NM (United States); Jennings, S. [Los Alamos National Laboratories, Carlsbad, NM (United States)

2007-07-01T23:59:59.000Z

315

Wrapper-Based Evolution of Legacy Information Systems  

E-Print Network [OSTI]

Wrapper-Based Evolution of Legacy Information Systems PHILIPPE THIRAN and JEAN-LUC HAINAUT Facult Universit´e Claude Bernard, Lyon System evolution most often implies the integration of legacy components file model versus OO model). In addition, neither the legacy DBMS (too weak to address integrity issues

Houben, Geert-Jan

316

COLORADO STATE-WIDE FOREST LEGACY ASSESSMENT OF NEED  

E-Print Network [OSTI]

for property owners. These ten criteria were developed through a survey conducted as part of this AON and for identification of Forest Legacy Areas (FLA's) within the state. Section 1 of this document presents information of which influence Forest Legacy Program implementation. Section 2 presents the Forest Legacy Area (FLA

317

PUBLIC AND REGULATORY ACCEPTANCE OF BLENDING OF RADIOACTIVE WASTE VS DILUTION  

SciTech Connect (OSTI)

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

318

Nuclear waste management technical support in the development of nuclear waste form criteria for the NRC. Task 1. Waste package overview  

SciTech Connect (OSTI)

In this report the current state of waste package development for high level waste, transuranic waste, and spent fuel in the US and abroad has been assessed. Specifically, reviewed are recent and on-going research on various waste forms, container materials and backfills and tentatively identified those which are likely to perform most satisfactorily in the repository environment. Radiation effects on the waste package components have been reviewed and the magnitude of these effects has been identified. Areas requiring further research have been identified. The important variables affecting radionuclide release from the waste package have been described and an evaluation of regulatory criteria for high level waste and spent fuel is presented. Finally, for spent fuel, high level, and TRU waste, components which could be used to construct a waste package having potential to meet NRC performance requirements have been described and identified.

Dayal, R.; Lee, B.S.; Wilke, R.J.; Swyler, K.J.; Soo, P.; Ahn, T.M.; McIntyre, N.S.; Veakis, E.

1982-02-01T23:59:59.000Z

319

DOE complex buried waste characterization assessment  

SciTech Connect (OSTI)

The work described in this report was conducted by Pacific Northwest Laboratory to provide information to the Buried Waste Integrated Demonstration (BWID) program. The information in this report is intended to provide a complex-wide planning base for th.e BWID to ensure that BWID activities are appropriately focused to address the range of remediation problems existing across the US Department of Energy (DOE) complex. This report contains information characterizing the 2.1 million m[sup 3] of buried and stored wastes and their associated sites at six major DOE facilities. Approximately 85% of this waste is low-level waste, with about 12% TRU or TRU mixed waste; the remaining 3% is low-level mixed waste. In addition, the report describes soil contamination sites across the complex. Some of the details that would be useful in further characterizing the buried wastes and contaminated soil sites across the DOE complex are either unavailable or difficult to locate. Several options for accessing this information and/or improving the information that is available are identified in the report. This document is a companion to Technology Needs for Remediation: Hanford and Other DOE Sites, PNL-8328 (Stapp 1993).

Kaae, P.S.; Holter, G.M.; Garrett, S.M.K.

1993-01-01T23:59:59.000Z

320

Characterization of the BVEST waste tanks located at ORNL  

SciTech Connect (OSTI)

During the fall of 1996 there was a major effort to sample and analyze the Active Liquid Low-Level Waste (LLLW) tanks at ORNL which include the Melton Valley Storage Tanks (MVST) and the Bethel Valley Evaporator Service Tanks (BVEST). The characterization data summarized in this report was needed to address waste processing options, address concerns dealing with the performance assessment (PA) data for the Waste Isolation Pilot Plant (WIPP), evaluate the waste characteristics with respect to the waste acceptance criteria (WAC) for WIPP and Nevada Test Site (NTS), address criticality concerns, and meet DOT requirements for transporting the waste. This report discusses the analytical characterization data for the supernatant and sludge in the BVEST waste tanks W-21, W-22, and W-23. The isotopic data presented in this report supports the position that fissile isotopes of uranium and plutonium were denatured as required by the administrative controls stated in the ORNL LLLW waste acceptance criteria (WAC). In general, the BVEST sludge was found to be hazardous based on RCRA characteristics and the transuranic alpha activity was well above the 100 nCi/g limit for TRU waste. The characteristics of the BVEST sludge relative to the WIPP WAC limits for fissile gram equivalent, plutonium equivalent activity, and thermal power from decay heat were estimated from the data in this report and found to be far below the upper boundary for any of the remote-handled transuranic waste (RH-TRU) requirements for disposal of the waste in WIPP.

Keller, J.M.; Giaquinto, J.M.; Meeks, A.M.

1997-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "legacy tru waste" 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.


321

Process Knowledge Summary Report for Advanced Test Reactor Complex Contact-Handled Transuranic Waste Drum TRA010029  

SciTech Connect (OSTI)

This Process Knowledge Summary Report summarizes information collected to satisfy the transportation and waste acceptance requirements for the transfer of one drum containing contact-handled transuranic (TRU) actinide standards generated by the Idaho National Laboratory at the Advanced Test Reactor (ATR) Complex to the Advanced Mixed Waste Treatment Project (AMWTP) for storage and subsequent shipment to the Waste Isolation Pilot Plant for final disposal. The drum (i.e., Integrated Waste Tracking System Bar Code Number TRA010029) is currently stored at the Materials and Fuels Complex. The information collected includes documentation that addresses the requirements for AMWTP and applicable sections of their Resource Conservation and Recovery Act permits for receipt and disposal of this TRU waste generated from ATR. This Process Knowledge Summary Report includes information regarding, but not limited to, the generation process, the physical form, radiological characteristics, and chemical contaminants of the TRU waste, prohibited items, and packaging configuration. This report, along with the referenced supporting documents, will create a defensible and auditable record for this TRU waste originating from ATR.

B. R. Adams; R. P. Grant; P. R. Smith; J. L. Weisgerber

2013-09-01T23:59:59.000Z

322

Waste Isolation Pilot Plant 2005 Site Environmental Report  

SciTech Connect (OSTI)

The purpose of this report is to provide information needed by the DOE to assess WIPP's environmental performance and to make WIPP environmental information available to stakeholders and members of the public. This report has been prepared in accordance with DOE Order 231.1A and DOE guidance. This report documents WIPP's environmental monitoring programs and their results for 2004. The WIPP Project is authorized by the DOE National Security and Military Applications of Nuclear Energy Authorization Act of 1980 (Pub. L. 96-164). After more than 20 years of scientific study and public input, WIPP received its first shipment of waste on March 26, 1999. Located in southeastern New Mexico, WIPP is the nation's first underground repository permitted to safely and permanently dispose of TRU radioactive and mixed waste (as defined in the WIPP LWA) generated through defense activities and programs. TRU waste is defined, in the WIPP LWA, as radioactive waste containing more than 100 nanocuries (3,700 becquerels [Bq]) of alpha-emitting TRU isotopes per gram of waste, with half-lives greater than 20 years except for high-level waste, waste that has been determined not to require the degree of isolation required by the disposal regulations, and waste the U.S. Nuclear Regulatory Commission (NRC) has approved for disposal. Most TRU waste is contaminated industrial trash, such as rags and old tools; sludges from solidified liquids; glass; metal; and other materials from dismantled buildings. TRU waste is eligible for disposal at WIPP if it has been generated in whole or in part by one or more of the activities listed in the Nuclear Waste Policy Act of 1982 (42 United States Code [U.S.C.] §10101, et seq.), including naval reactors development, weapons activities, verification and control technology, defense nuclear materials production, defense nuclear waste and materials by-products management,defense nuclear materials security and safeguards and security investigations, and defense research and development. The waste must also meet the WIPP Waste Acceptance Criteria. When TRU waste arrives at WIPP, it is transported into the Waste Handling Building. The waste containers are removed from the shipping containers, placed on the waste hoist, and lowered to the repository level of 655 m (2,150 ft; approximately 0.5 mi) below the surface. Next, the containers of waste are removed from the hoist and placed in excavated disposal rooms in the Salado Formation, a thick sequence of evaporite beds deposited approximately 250 million years ago (Figure 1.1). After each panel of seven rooms has been filled with waste, specially designed closures are emplaced. When all of WIPP's panels have been filled, at the conclusion of WIPP operations, seals will be placed in the shafts. One of the main attributes of salt, as a rock formation in which to isolate radioactive waste, is the ability of the salt to creep, that is, to deform continuously over time. Excavations into which the waste-filled drums are placed will close eventually, flowing around the drums and sealing them within the formation.

Washington Regulatory and Environmental Services

2006-10-13T23:59:59.000Z

323

CRAD, Safety Basis- Oak Ridge National Laboratory TRU ALPHA LLWT Project  

Broader source: Energy.gov [DOE]

A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a November 2003 assessment of the Safety Basis portion of an Operational Readiness Review of the Oak Ridge National Laboratory TRU ALPHA LLWT Project.

324

CRAD, Conduct of Operations- Oak Ridge National Laboratory TRU ALPHA LLWT Project  

Broader source: Energy.gov [DOE]

A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a November, 2003 assessment of the Conduct of Operations Program portion of an Operational Readiness Review of the Oak Ridge National Laboratory, TRU ALPHA LLWT Project.

325

THe heartTruTH Heart disease is the #1 killer of  

E-Print Network [OSTI]

THe heartTruTH® #12;Heart disease is the #1 killer of women, but many women do not know they are at risk. The Heart Truth® campaign aims to give women a personal and urgent wake-up call about their risk of heart disease. The red Dress® is the national symbol for women and heart disease awareness introduced

Baker, Chris I.

326

CRAD, Radiological Controls- Oak Ridge National Laboratory TRU ALPHA LLWT Project  

Broader source: Energy.gov [DOE]

A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a November 2003 assessment of the Radiation Protection Program portion of an Operational Readiness Review of the Oak Ridge National Laboratory TRU ALPHA LLWT Project.

327

CRAD, Quality Assurance- Oak Ridge National Laboratory TRU ALPHA LLWT Project  

Broader source: Energy.gov [DOE]

A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a November 2003 assessment of the Quality Assurance Program portion of an Operational Readiness Review of the Oak Ridge National Laboratory TRU ALPHA LLWT Project.

328

Transuranic waste characterization sampling and analysis methods manual  

SciTech Connect (OSTI)

The Transuranic Waste Characterization Sampling and Analysis Methods Manual (Methods Manual) provides a unified source of information on the sampling and analytical techniques that enable Department of Energy (DOE) facilities to comply with the requirements established in the current revision of the Transuranic Waste Characterization Quality Assurance Program Plan (QAPP) for the Waste Isolation Pilot Plant (WIPP) Transuranic (TRU) Waste Characterization Program (the Program). This Methods Manual includes all of the testing, sampling, and analytical methodologies accepted by DOE for use in implementing the Program requirements specified in the QAPP.

NONE

1995-05-01T23:59:59.000Z

329

CARBON DIOXIDE AND OUR OCEAN LEGACY  

E-Print Network [OSTI]

is a biologist at the California State Univer- sity San Marcos, with expertise in the effects of carbon dioxideCARBON DIOXIDE AND OUR OCEAN LEGACY G Carbon Dioxide: Our Role The United States is the single. Every day the average American adds about 118 pounds of carbon dioxide to the atmos- phere, due largely

330

In Lewes, a legacy of service  

E-Print Network [OSTI]

In Lewes, a legacy of service to agriculture PAGE 31 Bridgeville's Newton family has deep ties offering programs in Bethany Beach. 7 Cape stars. Rebecca Pepper and Jacki Coveleski have taken their love research. Delaware is the number two producer of lima beans in the U.S., and a research project could put

Firestone, Jeremy

331

The Economic Legacy of Mahmoud Ahmadinejad  

E-Print Network [OSTI]

The Economic Legacy of Mahmoud Ahmadinejad Prof. Nader Habibi Mahmoud Ahmadinejad, Iran's sixth and working-class Iranians. His campaign promises regarding redistributing wealth, enlarging economic, during his two terms in office, Ahmadinejad indeed implemented a number of important economic reforms

Snider, Barry B.

332

Heavy metal inventory and fuel sustainability of recycling TRU in FBR design  

SciTech Connect (OSTI)

Nuclear fuel materials from spent fuel of light water reactors have a potential to be used for destructive devices with very huge energy release or in the same time, it can be utilized as a peaceful energy or civil applications, for generating electricity, desalination of water, medical application and others applications. Several research activities showed some recycled spent fuel can be used as additional fuel loading for increasing fuel breeding capability as well as improving intrinsic aspect of nuclear non-proliferation. The present investigation intends to evaluate the composition of heavy metals inventories and fuel breeding capability in the FBR design based on the loaded fuel of light water reactor (LWR) spent fuel (SF) of 33 GWd/t with 5 years cooling time by adopting depletion code of ORIGEN. Whole core analysis of FBR design is performed by adopting and coupling codes such as SLAROM code, JOINT and CITATION codes. Nuclear data library, JFS-3-J-3.2R which is based on the JENDL 3.2 has been used for nuclear data analysis. JSFR design is the basis design reference which basically adopted 800 days cycle length for 4 batches system. Higher inventories of plutonium of MOX fuel and TRU fuel types at equilibrium composition than initial composition have been shown. Minor actinide (MA) inventory compositions obtain a different inventory trends at equilibrium composition for both fuel types. Higher Inventory of MA is obtained by MOX fuel and less MA inventory for TRU fuel at equilibrium composition than initial composition. Some different MA inventories can be estimated from the different inventory trend of americium (Am). Higher americium inventory for MOX fuel and less americium inventory for TRU fuel at equilibrium condition. Breeding ratio of TRU fuel is relatively higher compared with MOX fuel type. It can be estimated from relatively higher production of Pu-238 (through converted MA) in TRU fuel, and Pu-238 converts through neutron capture to produce Pu-239. Higher breeding ratio of MOX fuel and TRU fuel types at equilibrium condition are estimated from converted fertile material during reactor operation into fissile material of plutonium such as converted uranium fuel (converted U-238 into Pu-239) or additional converted fuel from MA into Pu-238 and changes into Pu-239 by capturing neutron. Loading LWR SF gives better fuel breeding capability and increase inventory of MA for doping material of MOX fuel; however, it requires more supply MA inventory for TRU fuel type.

Permana, Sidik; Suzuki, Mitsutoshi; Su'ud, Zaki [Department of Science and Technology for Nuclear Material Management (STNM), Japan Atomic Energy Agency (JAEA), 2-4 Shirane, Shirakata, Tokai Mura, Naka-gun, Ibaraki 319-1195 Nuclear Physics and Bio (Indonesia); Department of Science and Technology for Nuclear Material Management (STNM), Japan Atomic Energy Agency (JAEA), 2-4 Shirane, Shirakata, Tokai Mura, Naka-gun, Ibaraki 319-1195 (Japan); Nuclear Physics and Bio Physics Research Group, Department of Physics, Bandung Institute of Technology, Gedung Fisika, Jl. Ganesha 10, Bandung 40132 (Indonesia)

2012-06-06T23:59:59.000Z

333

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

SciTech Connect (OSTI)

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

334

Avoidable waste management costs  

SciTech Connect (OSTI)

This report describes the activity based costing method used to acquire variable (volume dependent or avoidable) waste management cost data for routine operations at Department of Energy (DOE) facilities. Waste volumes from environmental restoration, facility stabilization activities, and legacy waste were specifically excluded from this effort. A core team consisting of Idaho National Engineering Laboratory, Los Alamos National Laboratory, Rocky Flats Environmental Technology Site, and Oak Ridge Reservation developed and piloted the methodology, which can be used to determine avoidable waste management costs. The method developed to gather information was based on activity based costing, which is a common industrial engineering technique. Sites submitted separate flow diagrams that showed the progression of work from activity to activity for each waste type or treatability group. Each activity on a flow diagram was described in a narrative, which detailed the scope of the activity. Labor and material costs based on a unit quantity of waste being processed were then summed to generate a total cost for that flow diagram. Cross-complex values were calculated by determining a weighted average for each waste type or treatability group based on the volume generated. This study will provide DOE and contractors with a better understanding of waste management processes and their associated costs. Other potential benefits include providing cost data for sites to perform consistent cost/benefit analysis of waste minimization and pollution prevention (WMIN/PP) options identified during pollution prevention opportunity assessments and providing a means for prioritizing and allocating limited resources for WMIN/PP.

Hsu, K.; Burns, M.; Priebe, S.; Robinson, P.

1995-01-01T23:59:59.000Z

335

Conversion of transuranic waste to low level waste by decontamination: a technical and economic evaluation  

SciTech Connect (OSTI)

A study was conducted to evaluate the technical and economic feasibility of using in-situ decontamination techniques to convert glove boxes and other large TRU-contaminated components directly into LLW. The results of the technical evaluation indicate that in-situ decontamination of these types of components to non-TRU levels is technically feasible. Applicable decontamination techniques include electropolishing, hand scrubbing, chemical washes/sprays, strippable coatings and Freon spray-cleaning. The removal of contamination from crevices and other holdup areas remains a problem, but may be solved through further advances in decontamination technology. Also, the increase in the allowable maximum TRU level from 10 nCi/g to 100 nCi/g as defined in DOE Order 5820.2 reduces the removal requirement and facilitates measurement of the remaining quantities. The major emphasis of the study was on a cost/benefit evaluation that included a review and update of previous analyses and evaluations of TRU-waste volume reduction and conversion options. The results of the economic evaluation show, for the assumptions used, that there is a definite cost incentive to size reduce large components, and that decontamination of sectioned material has become cost competitive with the size reduction options. In-situ decontamination appears to be the lowest cost option when based on routine-type operations conducted by well-trained and properly equipped personnel. 16 references, 1 figure, 7 tables.

Allen, R.P.; Hazelton, R.F.

1984-12-01T23:59:59.000Z

336

NR-SRS TRU Waste Shipments Milestone June 4 2013.docx  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

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337

New Facility Aids in Lab's Capability to Ship TRU Waste to WIPP |  

Office of Environmental Management (EM)

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338

Retrieval and Repackaging of RH-TRU Waste - General Presentation Modular Hot Cell Technology  

Office of Environmental Management (EM)

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339

LANL Shatters Records in First Year of Accelerated TRU Waste Shipping  

Office of Environmental Management (EM)

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340

Training Underway for TRU Waste Employees Hired For Recovery Act Project |  

Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

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Note: This page contains sample records for the topic "legacy tru waste" 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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341

Total Measurement Uncertainty (TMU) for Nondestructive Assay of Transuranic (TRU) Waste at the WRAP Facility  

SciTech Connect (OSTI)

This report examines the contributing factors to NDA measurement uncertainty at WRAP The significance of each factor on the TMU is analyzed and a final method is given for determining the TMU for NDA measurements at WRAP. As more data becomes available and WRAP gains in operational experience this report will be reviewed semi annually and updated as necessary.

WILLS, C.E.

2000-01-06T23:59:59.000Z

342

Content-Handled Transuranic (CH-TRU) Waste Content Codes (CH-TRUCON) |  

Office of Environmental Management (EM)

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343

EA-1962: Analysis for Below Grade Suspect Transuranic (TRU) Waste at  

Energy Savers [EERE]

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344

Microsoft Word - DOE Exceeds TRU Waste Cleanup Goal at LANL.doc  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

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345

Settlement Agreement on TRU Mixed Waste Storage at Nevada Test Site  

Office of Environmental Management (EM)

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346

Settlement Agreement on TRU Mixed Waste Storage at Nevada Test Site Summary  

Office of Environmental Management (EM)

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347

Environmental impact statement for initiation of transuranic waste disposal at the waste isolation pilot plant  

SciTech Connect (OSTI)

WIPP`s long-standing mission is to demonstrate the safe disposal of TRU waste from US defense activities. In 1980, to comply with NEPA, US DOE completed its first environmental impact statement (EIS) which compared impacts of alternatives for TRU waste disposal. Based on this 1980 analysis, DOE decided to construct WIPP in 1981. In a 1990 decision based on examination of alternatives in a 1990 Supplemental EIS, DOE decided to continue WIPP development by proceeding with a testing program to examine WIPP`s suitability as a TRU waste repository. Now, as DOE`s Carlsbad Area Office (CAO) attempts to complete its regulatory obligations to begin WIPP disposal operations, CAO is developing WIPP`s second supplemental EIS (SEIS-II). To complete the SEIS-II, CAO will have to meet a number of challenges. This paper explores both the past and present EISs prepared to evaluate the suitability of WIPP. The challenges in completing an objective comparison of alternatives, while also finalizing other critical-path compliance documents, controlling costs, and keeping stakeholders involved during the decision-making process are addressed.

Johnson, H.E. [U.S. Dept. of Energy, Carlsbad, NM (United States) Carlsbad Area Office; Whatley, M.E. [Westinghouse Electric Corp., Carlsbad, NM (United States). Waste Isolation Div.

1996-08-01T23:59:59.000Z

348

Characterization of past and present solid waste streams from the plutonium finishing plant  

SciTech Connect (OSTI)

During the next two decades the transuranic (TRU) wastes now stored in the burial trenches and storage facilities at the Hanford Site are to be retrieved, processed at the Waste Receiving and Processing (WRAP) Facility, and shipped to the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico for final disposal. Over 50% of the TRU waste to be retrieved for shipment to the WIPP has been generated at the Plutonium Finishing Plant (PFP), also known as the Plutonium Processing and Storage Facility and Z Plant. The purpose of this report is to characterize the radioactive solid wastes generated by the PFP since its construction in 1947 using process knowledge, existing records, and history-obtained from interviews. The PFP is currently operated by Westinghouse Hanford Company (WHC) for the US Department of Energy (DOE).

Duncan, D R; Mayancsik, B A [Westinghouse Hanford Co., Richland, WA (United States)] [Westinghouse Hanford Co., Richland, WA (United States); Pottmeyer, J A; Vejvoda, E J; Reddick, J A; Sheldon, K M; Weyns, M I [Los Alamos Technical Associates, Kennewick, WA (United States)] [Los Alamos Technical Associates, Kennewick, WA (United States)

1993-02-01T23:59:59.000Z

349

DOE complex buried waste characterization assessment. Buried Waste Integrated Demonstration Program  

SciTech Connect (OSTI)

The work described in this report was conducted by Pacific Northwest Laboratory to provide information to the Buried Waste Integrated Demonstration (BWID) program. The information in this report is intended to provide a complex-wide planning base for th.e BWID to ensure that BWID activities are appropriately focused to address the range of remediation problems existing across the US Department of Energy (DOE) complex. This report contains information characterizing the 2.1 million m{sup 3} of buried and stored wastes and their associated sites at six major DOE facilities. Approximately 85% of this waste is low-level waste, with about 12% TRU or TRU mixed waste; the remaining 3% is low-level mixed waste. In addition, the report describes soil contamination sites across the complex. Some of the details that would be useful in further characterizing the buried wastes and contaminated soil sites across the DOE complex are either unavailable or difficult to locate. Several options for accessing this information and/or improving the information that is available are identified in the report. This document is a companion to Technology Needs for Remediation: Hanford and Other DOE Sites, PNL-8328 (Stapp 1993).

Kaae, P.S.; Holter, G.M.; Garrett, S.M.K.

1993-01-01T23:59:59.000Z

350

Investigations to site a radioactive waste repository in Cumbria: Evidence against proceeding to MRWS Stage 4  

E-Print Network [OSTI]

Investigations to site a radioactive waste repository in Cumbria: Evidence against proceeding to MRWS Stage 4 Radioactive waste repository in Cumbria: Evidence against proceeding to MRWS Stage 4 s the UK radioactive waste legacy comprises difficult material which is complex, of mixed origin

351

General Atomics Final Drum of Legacy Mixed Wastes.  

Office of Legacy Management (LM)

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352

Westinghouse TRU Solutions LLC Earns Corporate Award for Mining Operations  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

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353

Westinghouse TRU Solutions LLC Earns Small Business Program Award  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

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354

Westinghouse TRU Solutions LLC Earns Superior Star Award for Safety  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

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355

Economic evaluation of volume reduction for Defense transuranic waste  

SciTech Connect (OSTI)

This study evaluates the economics of volume reduction of retrievably stored and newly generated DOE transuranic waste by comparing the costs of reduction of the waste with the savings possible in transportation and disposal of the waste. The report develops a general approach to the comparison of TRU waste volume reduction costs and cost savings, establishes an initial set of cost data, and develops conclusions to support selecting technologies and facilities for the disposal of DOE transuranic waste. Section I outlines the analysis which considers seven types of volume reduction from incineration and compaction of combustibles to compaction, size reduction, shredding, melting, and decontamination of metals. The study considers the volume reduction of contact-handled newly generated, and retrievably stored DOE transuranic waste. Section II of this report describes the analytical approach, assumptions, and flow of waste material through sites. Section III presents the waste inventories, disposal, and transportation savings with volume reduction and the volume reduction techniques and savings.

Brown, C.M.

1981-07-01T23:59:59.000Z

356

Solvent extraction and recovery of the transuranic elements from waste solutions using the TRUEX process  

SciTech Connect (OSTI)

High-level liquid waste is produced during the processing of irradiated nuclear fuel by the PUREX process. In some cases the treatment of metallurgical scrap to recover the plutonium values also generates a nitric acid waste solution. Both waste solutions contain sufficient concentrations of transuranic elements (mostly /sup 241/Am) to require handling and disposal as a TRU waste. This paper describes a recently developed solvent extraction/recovery process called TRUEX (transuranium extraction) which is designed to reduce the TRU concentration in nitric waste solutions to <100 nCi/g of disposed form (1,2). (In the USA, non-TRU waste is defined as <100 nCi of TRU/g of disposed form.) The process utilizes PUREX process solvent (TBP in a normal paraffinic hydrocarbon or carbon tetrachloride) modified by a small concentration of octyl(phenyl)-N,N-diisobutylcarbamoylmethylphosphine oxide (abbrev. CMPO). The presence of CMPO enables the modified PUREX process solvent to extract trivalent actinides as well as tetra- and hexavalent actinides. A major feature of the TRUEX process is that is is applicable to waste solutions containing a wide range of nitric acid, salt, and fission product concentrations and at the same time is very compatible with existing liquid-liquid extraction technology as usually practiced in a fuel reprocessing plant. To date the process has been tested on two different types of synthetic waste solutions. The first solution is a typical high-level nitric acid waste and the second a typical waste solution generated in metallurgical scrap processing. Results are discussed. 4 refs., 1 fig., 4 tabs.

Horwitz, E.P.; Schulz, W.W.

1985-01-01T23:59:59.000Z

357

Analyzing Losses: Transuranics into Waste and Fission Products into Recycled Fuel  

SciTech Connect (OSTI)

All mass streams from separations and fuel fabrication are products that must meet criteria. Those headed for disposal must meet waste acceptance criteria (WAC) for the eventual disposal sites corresponding to their waste classification. Those headed for reuse must meet fuel or target impurity limits. A “loss” is any material that ends up where it is undesired. The various types of losses are linked in the sense that as the loss of transuranic (TRU) material into waste is reduced, often the loss or carryover of waste into TRU or uranium is increased. We have analyzed four separation options and two fuel fabrication options in a generic fuel cycle. The separation options are aqueous uranium extraction plus (UREX+1), electrochemical, Atomics International reduction oxidation separation (AIROX), and melt refining. UREX+1 and electrochemical are traditional, full separation techniques. AIROX and melt refining are taken as examples of limited separations, also known as minimum fuel treatment. The fuels are oxide and metal. To define a generic fuel cycle, a fuel recycling loop is fed from used light water reactor (LWR) uranium oxide fuel (UOX) at 51 MWth-day/kg-iHM burnup. The recycling loop uses a fast reactor with TRU conversion ratio (CR) of 0.50. Excess recovered uranium is put into storage. Only waste, not used fuel, is disposed – unless the impurities accumulate to a level so that it is impossible to make new fuel for the fast reactor. Impurities accumulate as dictated by separation removal and fission product generation. Our model approximates adjustment to fast reactor fuel stream blending of TRU and U products from incoming LWR UOX and recycling FR fuel to compensate for impurity accumulation by adjusting TRU:U ratios. Our mass flow model ignores postulated fuel impurity limits; we compare the calculated impurity values with those limits to identify elements of concern. AIROX and melt refining cannot be used to separate used LWR UOX-51 because they cannot separate U from TRU, it is then impossible to make X% TRU for fast reactors with UOX-51 used fuel with 1.3% TRU. AIROX and melt refining can serve in the recycle loop for about 3 recycles, at which point the accumulated impurities displace fertile uranium and the fuel can no longer be as critical as the original fast reactor fuel recipe. UREX+1 and electrochemical can serve in either capacity; key impurities appear to be lanthanides and several transition metals.

Steven J. Piet; Nick R. Soelberg; Samuel E. Bays; Robert E. Cherry; Layne F. Pincock; Eric L. Shaber; Melissa C. Teague; Gregory M. Teske; Kurt G. Vedros; Candido Pereira; Denia Djokic

2010-11-01T23:59:59.000Z

358

Proposed Changes to EPA's Transuranic Waste Characterization Approval Process  

SciTech Connect (OSTI)

This paper describes the changes to the waste characterization (WC) approval process proposed in August 2002 by the U.S. Environmental Protection Agency (EPA or the Agency or we). EPA regulates the disposal of transuranic (TRU) waste at the Waste Isolation Pilot Plant (WIPP) repository in Carlsbad, New Mexico. EPA regulations require that waste generator/storage sites seek EPA approval of WC processes used to characterize TRU waste destined for disposal at WIPP. The regulations also require that EPA verify, through site inspections, characterization of each waste stream or group of waste streams proposed for disposal at the WIPP. As part of verification, the Agency inspects equipment, procedures, and interviews personnel to determine if the processes used by a site can adequately characterize the waste in order to meet the waste acceptance criteria for WIPP. The paper discusses EPA's mandate, current regulations, inspection experience, and proposed changes. We expect that th e proposed changes will provide equivalent or improved oversight. Also, they would give EPA greater flexibility in scheduling and conducting inspections, and should clarify the regulatory process of inspections for both Department of Energy (DOE) and the public.

Joglekar. R. D.; Feltcorn, E. M.; Ortiz, A. M.

2003-02-25T23:59:59.000Z

359

Nuclear waste management. Quarterly progress report, January-March, 1981  

SciTech Connect (OSTI)

Reports and summaries are provided for the following programs: high-level waste process development; alternative waste forms; nuclear waste materials characterization center; TRU waste immobilization; TRU waste decontamination; krypton solidification; thermal outgassing; iodine-129 fixation; NWVP off-gas analysis; monitoring and physical characterization of unsaturated zone transport; well-logging instrumentation development; verification instrument development; mobility of organic complexes of radionuclide in soils; low-level waste generation reduction handbook; waste management system studies; assessment of effectiveness of geologic isolation systems; waste/rock interactions technology program; high-level waste form preparation; development of backfill materials; development of structural engineered barriers; disposal charge analysis; analysis of spent fuel policy implementation; spent fuel and pool component integrity program; analysis of postulated criticality events in a storage array of spent LWR fuel; asphalt emulsion sealing of uranium mill tailings; liner evaluation for uranium mill tailings; multilayer barriers for sealing of uranium tailings; application of long-term chemical biobarriers for uranium tailings; and revegetation of inactive uranium tailings sites.

Chikalla, T.D.; Powell, J.A. (comp.)

1981-06-01T23:59:59.000Z

360

Assessment of alternatives for management of ORNL retrievable transuranic waste. Nuclear Waste Program: transuranic waste (Activity No. AR 05 15 15 0; ONL-WT04)  

SciTech Connect (OSTI)

Since 1970, solid waste with TRU or U-233 contamination in excess of 10 ..mu..Ci per kilogram of waste has been stored in a retrievable fashion at ORNL, such as in ss drums, concrete casks, and ss-lined wells. This report describes the results of a study performed to identify and evaluate alternatives for management of this waste and of the additional waste projected to be stored through 1995. The study was limited to consideration of the following basic strategies: Strategy 1: Leave waste in place as is; Strategy 2: Improve waste confinement; and Strategy 3: Retrieve waste and process for shipment to a Federal repository. Seven alternatives were identified and evaluated, one each for Strategies 1 and 2 and five for Strategy 3. Each alternative was evaluated from the standpoint of technical feasibility, cost, radiological risk and impact, regulatory factors and nonradiological environmental impact.

Not Available

1980-10-01T23:59:59.000Z

Note: This page contains sample records for the topic "legacy tru waste" 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.


361

Legacy Environmental Solutions | Open Energy Information  

Open Energy Info (EERE)

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362

LM-04-XXXX Office of Legacy Management  

Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

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363

Compliance status report for the Waste Isolation Pilot Plant  

SciTech Connect (OSTI)

The US Department of Energy (DOE) is responsible for the disposition of transuranic (TRU) waste generated through national defense-related activities. Approximately 53,700 m{sup 2} of these wastes have been generated and are currently stored at government defense installations across the country. The Waste Isolation Pilot Plant (WIPP), located in southeastern New Mexico, has been sited and constructed to meet the criteria established by the scientific and regulatory community for the safe, long-term disposal of TRU and TRU-mixed wastes. This Compliance Status Report (CSR) provides an assessment of the progress of the WIPP Program toward compliance with long-term disposal regulations, set forth in Title 40 CFR 191 (EPA, 1993a), Subparts B and C, and Title 40 CFR {section}268.6 (EPA, 1993b), in order to focus on-going and future experimental and engineering activities. The CSR attempts to identify issues associated with the performance of the WIPP as a long-term repository and to focus on the resolution of these issues. This report will serve as a tool to focus project resources on the areas necessary to ensure complete, accurate, and timely submittal of the compliance application. This document is not intended to constitute a statement of compliance or a demonstration of compliance.

Not Available

1994-03-31T23:59:59.000Z

364

Linking Legacies: Connecting the Cold War Nuclear Weapons Production...  

Broader source: Energy.gov (indexed) [DOE]

prior to 1992 as a result of weapons production. Linking Legacies - Connecting the Cold War Nuclear Weapons Production Processes to Their Environmental Consequences More Documents...

365

Legacy Management Work Progresses on Defense-Related Uranium...  

Broader source: Energy.gov (indexed) [DOE]

Most recently, LM visited 84 defense-related legacy uranium mine sites located within 11 uranium mining districts in 6 western states. At these sites, photographs and global...

366

amateur sport legacies: Topics by E-print Network  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

The first instrumental musical organization on campus was a 12 383 Wrapper-Based Evolution of Legacy Information Systems Computer Technologies and Information Sciences...

367

Standing by Ohio: Cleaning Up our Environmental Legacy  

Broader source: Energy.gov [DOE]

Deputy Secretary of Energy Dan Poneman visits Ohio to mark a milestone in the Department’s efforts to clean up our environmental legacy.

368

Final environmental impact statement. Waste Isolation Pilot Plant  

SciTech Connect (OSTI)

In accordance with the National Environmental Policy Act (NEPA) of 1969, the US Department of Energy (DOE) has prepared this document as environmental input to future decisions regarding the Waste Isolation Pilot Plant (WIPP), which would include the disposal of transuranic waste, as currently authorized. The alternatives covered in this document are the following: (1) Continue storing transuranic (TRU) waste at the Idaho National Engineering Laboratory (INEL) as it is now or with improved confinement. (2) Proceed with WIPP at the Los Medanos site in southeastern New Mexico, as currently authorized. (3) Dispose of TRU waste in the first available repository for high-level waste. The Los Medanos site would be investigated for its potential suitability as a candidate site. This is administration policy and is the alternative preferred by the DOE. (4) Delay the WIPP to allow other candidate sites to be evaluated for TRU-waste disposal. This environmental impact statement is arranged in the following manner: Chapter 1 is an overall summary of the analysis contained in the document. Chapters 2 and 4 set forth the objectives of the national waste-management program and analyze the full spectrum of reasonable alternatives for meeting these objectives, including the WIPP. Chapter 5 presents the interim waste-acceptance criteria and waste-form alternatives for the WIPP. Chapters 6 through 13 provide a detailed description and environmental analysis of the WIPP repository and its site. Chapter 14 describes the permits and approvals necessary for the WIPP and the interactions that have taken place with Federal, State, and local authorities, and with the general public in connection with the repository. Chapter 15 analyzes the many comments received on the DEIS and tells what has been done in this FEIS in response. The appendices contain data and discussions in support of the material in the text.

Not Available

1980-10-01T23:59:59.000Z

369

EIS-0113: Disposal of Hanford Defense High-Level, Transuranic and Tank Waste, Hanford Site, Richland, Washington  

Broader source: Energy.gov [DOE]

The U.S. Department of Energy developed this EIS to examine the potential environmental impacts of final disposal options for legacy and future radioactive defense wastes stored at the Hanford Site.

370

Revised Draft Hanford Site Solid (Radioactive and Hazardous) Waste Program Environmental Impact Statement, Richland, Washington  

SciTech Connect (OSTI)

This ''Revised Draft Hanford Site Solid (Radioactive and Hazardous) Waste Program Environmental Impact Statement'' (HSW EIS) covers three primary aspects of waste management at Hanford--waste treatment, storage, and disposal. It also addresses four kinds of solid waste--low-level waste (LLW), mixed (radioactive and chemically hazardous) low-level waste (MLLW), transuranic (TRU) waste, and immobilized low-activity waste (ILAW). It fundamentally asks the question: how should we manage the waste we have now and will have in the future? This EIS analyzes the impacts of the LLW, MLLW, TRU waste, and ILAW we currently have in storage, will generate, or expect to receive at Hanford. The HSW EIS is intended to help us determine what specific facilities we will continue to use, modify, or construct to treat, store, and dispose of these wastes (Figure S.1). Because radioactive and chemically hazardous waste management is a complex, technical, and difficult subject, we have made every effort to minimize the use of acronyms (making an exception for our four waste types listed above), use more commonly understood words, and provide the ''big picture'' in this summary. An acronym list, glossary of terms, and conversions for units of measure are provided in a readers guide in Volume 1 of this EIS.

N /A

2003-04-11T23:59:59.000Z

371

Safety Analysis Report for Packaging (SARP) of the Oak Ridge National Laboratory TRU Californium Shipping Container  

SciTech Connect (OSTI)

An analytical evaluation of the Oak Ridge National Laboratory TRU Californium Shipping Container was made in order to demonstrate its compliance with the regulations governing off-site shipment of packages that contain radioactive material. The evaluation encompassed five primary categories: structural integrity, thermal resistance, radiation shielding, nuclear criticality safety, and quality assurance. The results of this evaluation demonstrate that the container complies with the applicable regulations.

Box, W.D.; Shappert, L.B.; Seagren, R.D.; Klima, B.B.; Jurgensen, M.C.; Hammond, C.R.; Watson, C.D.

1980-01-01T23:59:59.000Z

372

E-Print Network 3.0 - arecibo legacy fast Sample Search Results  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

LSI+61 303 Project Collection: Physics 27 Legacy System Evolution towards Service-Oriented Architecture Summary: Legacy System Evolution towards Service-Oriented Architecture...

373

Performance demonstration program plan for RCRA constituent analysis of solidified wastes  

SciTech Connect (OSTI)

Performance Demonstration Programs (PDPS) are designed to help ensure compliance with the Quality Assurance Objectives (QAOs) for the Waste Isolation Pilot Plant (WIPP). The PDPs are intended for use by the Department of Energy (DOE) Carlsbad Area Office (CAO) to assess and approve the laboratories and other measurement facilities supplying services for the characterization of WIPP TRU waste. The PDPs may also be used by CAO in qualifying laboratories proposing to supply additional analytical services that are required for other than waste characterization, such as WIPP site operations. The purpose of this PDP is to test laboratory performance for the analysis of solidified waste samples for TRU waste characterization. This performance will be demonstrated by the successful analysis of blind audit samples of simulated, solidified TRU waste according to the criteria established in this plan. Blind audit samples (hereinafter referred to as PDP samples) will be used as an independent means to assess laboratory performance regarding compliance with the QAOs. The concentration of analytes in the PDP samples will address levels of regulatory concern and will encompass the range of concentrations anticipated in actual waste characterization samples. Analyses that are required by the WIPP to demonstrate compliance with various regulatory requirements and which are included in the PDP must be performed by laboratories that demonstrate acceptable performance in the PDP. These analyses are referred to as WIPP analyses and the samples on which they are performed are referred to as WIPP samples for the balance of this document.

NONE

1995-06-01T23:59:59.000Z

374

Economic comparison of centralizing or decentralizing processing facilities for defense transuranic waste  

SciTech Connect (OSTI)

This study is part of a set of analyses under direction of the Transuranic Waste Management Program designed to provide comprehensive, systematic methodology and support necessary to better understand options for national long-term management of transuranic (TRU) waste. The report summarizes activities to evaluate the economics of possible alternatives in locating facilities to process DOE-managed transuranic waste. The options considered are: (1) Facilities located at all major DOE TRU waste generating sites. (2) Two or three regional facilities. (3) Central processing facility at only one DOE site. The study concludes that processing at only one facility is the lowest cost option, followed, in order of cost, by regional then individual site processing.

Brown, C M

1980-07-01T23:59:59.000Z

375

INEL test plan for evaluating waste assay systems  

SciTech Connect (OSTI)

A test bed is being established at the Idaho National Engineering Laboratory (INEL) Radioactive Waste Management Complex (RWMC). These tests are currently focused on mobile or portable radioassay systems. Prior to disposal of TRU waste at the Waste Isolation Pilot Plant (WIPP), radioassay measurements must meet the quality assurance objectives of the TRU Waste Characterization Quality Assurance Program Plan. This test plan provides technology holders with the opportunity to assess radioassay system performance through a three-tiered test program that consists of: (a) evaluations using non-interfering matrices, (b) surrogate drums with contents that resemble the attributes of INEL-specific waste forms, and (c) real waste tests. Qualified sources containing a known mixture and range of radionuclides will be used for the non-interfering and surrogate waste tests. The results of these tests will provide technology holders with information concerning radioassay system performance and provide the INEL with data useful for making decisions concerning alternative or improved radioassay systems that could support disposal of waste at WIPP.

Mandler, J.W.; Becker, G.K.; Harker, Y.D.; Menkhaus, D.E.; Clements, T.L. Jr.

1996-09-01T23:59:59.000Z

376

Sodium-Bearing Waste Treatment Alternatives Implementation Study  

SciTech Connect (OSTI)

The purpose of this document is to discuss issues related to the implementation of each of the five down-selected INEEL/INTEC radioactive liquid waste (sodium-bearing waste - SBW) treatment alternatives and summarize information in three main areas of concern: process/technical, environmental permitting, and schedule. Major implementation options for each treatment alternative are also identified and briefly discussed. This report may touch upon, but purposely does not address in detail, issues that are programmatic in nature. Examples of these include how the SBW will be classified with respect to the Nuclear Waste Policy Act (NWPA), status of Waste Isolation Pilot Plant (WIPP) permits and waste storage availability, available funding for implementation, stakeholder issues, and State of Idaho Settlement Agreement milestones. It is assumed in this report that the SBW would be classified as a transuranic (TRU) waste suitable for disposal at WIPP, located in New Mexico, after appropriate treatment to meet transportation requirements and waste acceptance criteria (WAC).

Charles M. Barnes; James B. Bosley; Clifford W. Olsen

2004-07-01T23:59:59.000Z

377