Powered by Deep Web Technologies
Note: This page contains sample records for the topic "activity waste law" 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.


1

Hanford Low Activity Waste (LAW) Fluidized Bed Steam Reformer...  

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

Hanford Low Activity Waste (LAW) Fluidized Bed Steam Reformer (FBSR) Na-Al-Si (NAS) Waste Form Qualification C.M. Jantzen and E.M. Pierce November 18, 2010 2 Participating...

2

Hanford Low Activity Waste (LAW) Fluidized Bed Steam Reformer (FBSR) Na-Al-Si (NAS) Waste Form Qualification  

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

Hanford Low Activity Waste (LAW) Fluidized Bed Steam Hanford Low Activity Waste (LAW) Fluidized Bed Steam Reformer (FBSR) Na-Al-Si (NAS) Waste Form Qualification C.M. Jantzen and E.M. Pierce November 18, 2010 2 Participating Organizations 3 Incentive and Objectives FBSR sodium-aluminosilicate (NAS) waste form has been identified as a promising supplemental treatment technology for Hanford LAW Objectives: Reduce the risk associated with implementing the FBSR NAS waste form as a supplemental treatment technology for Hanford LAW Conduct test with actual tank wastes Use the best science to fill key data gaps Linking previous and new results together 4 Outline FBSR NAS waste form processing scales FBSR NAS waste form data/key assumptions FBSR NAS key data gaps FBSR NAS testing program 5 FBSR NAS Waste Form Processing

3

Louisiana Hazardous Waste Control Law (Louisiana)  

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

The Louisiana Department of Environmental Quality is responsible for administering the Louisiana Hazardous Waste Control Law and the regulations created under that law.

4

Louisiana Solid Waste Management and Resource Recovery Law (Louisiana) |  

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

Louisiana Solid Waste Management and Resource Recovery Law Louisiana Solid Waste Management and Resource Recovery Law (Louisiana) Louisiana Solid Waste Management and Resource Recovery Law (Louisiana) < Back Eligibility Agricultural Construction Developer Industrial Investor-Owned Utility Municipal/Public Utility Rural Electric Cooperative Utility Program Info State Louisiana Program Type Environmental Regulations Provider Louisiana Department of Environmental Quality The Louisiana Department of Environmental Quality manages solid waste for the state of Louisiana under the authority of the Solid Waste Management and Resource Recover Law. The Department makes rules and regulations that establish standards governing the storage, collection, processing, recovery and reuse, and disposal of solid waste; implement a management program that

5

Georgia Waste Control Law (Georgia) | Department of Energy  

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

Waste Control Law (Georgia) Waste Control Law (Georgia) Georgia Waste Control Law (Georgia) < Back Eligibility Agricultural Commercial Construction Developer Fed. Government Fuel Distributor General Public/Consumer Industrial Installer/Contractor Institutional Investor-Owned Utility Local Government Low-Income Residential Multi-Family Residential Municipal/Public Utility Nonprofit Residential Retail Supplier Rural Electric Cooperative Schools State/Provincial Govt Systems Integrator Transportation Tribal Government Utility Savings Category Alternative Fuel Vehicles Hydrogen & Fuel Cells Buying & Making Electricity Water Home Weatherization Solar Wind Program Info State Georgia Program Type Environmental Regulations Provider Georgia Department of Natural Resources The Waste Control Law makes it unlawful to dump waste in any lakes, streams

6

Office of Enforcement and Oversight's Office of Safety and Emergency Management Evaluations Activity Report for Observation of Waste Treatment and Immobilization Plant LAW Melter and Melter Off-gas Process System Hazards Analysis _Oct 21-31  

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

HSS Independent Activity Report - HSS Independent Activity Report - Rev. 0 Report Number: HIAR-WTP-2013-10-21 Site: Hanford Site Subject: Office of Enforcement and Oversight's Office of Safety and Emergency Management Evaluations Activity Report for Observation of Waste Treatment and Immobilization Plant Low Activity Waste Melter and Melter Off-gas Process System Hazards Analysis Activities Dates of Activity : 10/21/13 - 10/31/13 Report Preparer: James O. Low Activity Description/Purpose: The Office of Health, Safety and Security (HSS), Office of Safety and Emergency Management Evaluations (Independent Oversight) reviewed the Insight software hazard evaluation (HE) tables for hazard analysis (HA) generated to date for the Waste Treatment and Immobilization Plant (WTP) Low Activity Waste (LAW) Melter and Off-gas systems, observed a

7

Waste Sorting Activity Introduction  

E-Print Network (OSTI)

Waste Sorting Activity Introduction: This waste sorting game was originally designed to be one have completed the waste sorting activity quickly, no team was able to complete the waste sorting task who were unfamiliar with Dalhousie's waste management system. Goals: The primary goal of the activity

Beaumont, Christopher

8

Summary - WTP Analytical Lab, BOF and LAW Waste Vitrification Facilities  

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

Wa Wa Schem DOE is Immob site's t facilitie Balanc Activity of this techno facilitie are su WTP d Readin The as along w Level ( * Tw 1. 2. The Ele Site: H roject: W Report Date: M ited States aste Trea Labo Why DOE matic of Laser Ab s constructing bilization Plant tank wastes. T es including an ces of Facilities y Waste (LAW assessment w ology elements es (LAB, BOF, fficiently matur design, which n ness Level of 6 What th ssessment team with each elem (TRL) for the L wo LAB system . Autosamplin Laser ablati AES/LA-ICP To view the full T http://www.em.doe. objective of a Tech ements (CTEs), usin Hanford/ORP Waste Treatme March 2007 Departmen atment a oratory, B E-EM Did This blation Analytical a Waste Treat (WTP) at Hanf The WTP is com n Analytical Lab s (BOF) operat ) Vitrification F was to identify t s (CTEs) in the

9

Missouri Hazardous Waste Management Law (Missouri)  

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

The Hazardous Waste Program, administered by the Hazardous Waste Management Commission in the Department of Natural Resources, regulates the processing, transportation, and disposal of hazardous...

10

HANFORD'S SIMULATED LOW ACTIVITY WASTE CAST STONE PROCESSING  

SciTech Connect

Cast Stone is undergoing evaluation as the supplemental treatment technology for Hanford’s (Washington) high activity waste (HAW) and low activity waste (LAW). This report will only cover the LAW Cast Stone. The programs used for this simulated Cast Stone were gradient density change, compressive strength, and salt waste form phase identification. Gradient density changes show a favorable outcome by showing uniformity even though it was hypothesized differently. Compressive strength exceeded the minimum strength required by Hanford and greater compressive strength increase seen between the uses of different salt solution The salt waste form phase is still an ongoing process as this time and could not be concluded.

Kim, Y.

2013-08-20T23:59:59.000Z

11

Waste to Energy Time Activities  

E-Print Network (OSTI)

SEMINAR Waste to Energy Time Activities 9:30-9:40 Brief introduction of participants 9:40-10:10 Presentation of Dr. Kalogirou, "Waste to Energy: An Integral Part of Worldwide Sustainable Waste Management" 10. Sofia Bethanis, "Production of synthetic aggregates for use in structural concrete from waste to energy

Columbia University

12

Partitioning of Rhenium during Melting of Low-activity Waste Glass ...  

Science Conference Proceedings (OSTI)

Abstract Scope, Volatile loss of radioactive 99Tc to offgas is a concern with processing the low-activity waste (LAW) at Hanford site in to a ...

13

Independent Oversight Activity Report, Hanford Waste Treatment and  

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

Waste Treatment and Waste Treatment and Immobilization Plant - July 2013 Independent Oversight Activity Report, Hanford Waste Treatment and Immobilization Plant - July 2013 July 2013 Operational Awareness of Waste Treatment and Immobilization Plant Low Activity Waste Melter Process System Hazards Analysis Activity [HIAR-WTP-2013-07-31] This Independent Activity Report documents an oversight activity conducted by the Office of Health, Safety and Security's (HSS) Office of Safety and Emergency Management Evaluations from July 31 - August 5, 2013, at the Hanford Waste Treatment and Immobilization Plant (WTP). The activity consisted of HSS staff observing a limited portion of the hazards analysis (HA) for WTP Low Activity Waste (LAW) Melter Process system. The primary purpose of this HSS field activity was to observe and

14

Independent Oversight Activity Report, Hanford Waste Treatment and  

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

Hanford Waste Treatment and Hanford Waste Treatment and Immobilization Plant - June 2013 Independent Oversight Activity Report, Hanford Waste Treatment and Immobilization Plant - June 2013 June 2013 Hanford Waste Treatment and Immobilization Plant Low Activity Waste Melter Off-gas Process System Hazards Analysis Activity Observation [HIAR-WTP-2013-05-13] This Independent Activity Report documents an oversight activity conducted by the Office of Health, Safety and Security's (HSS) Office of Safety and Emergency Management Evaluations from May 13 - June 28, 2013, at the Hanford Waste Treatment and Immobilization Plant (WTP). The activity consisted of HSS staff observing a limited portion of the start of the hazard analysis (HA) for WTP Low Activity Waste (LAW) Primary Off-gas System. The primary purpose of this HSS field activity was to observe and

15

Independent Activity Report, Waste Treatment and Immobilization Plant -  

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

Waste Treatment and Immobilization Waste Treatment and Immobilization Plant - March 2013 Independent Activity Report, Waste Treatment and Immobilization Plant - March 2013 March 2013 Follow-up of Waste Treatment and Immobilization Plant Low Activity Waste Melter Process System Hazards Analysis Activity Review [HIAR-WTP-2013-03-18] The Office of Health, Safety and Security (HSS) staff observed a limited portion of the restart of the Hazard Analysis (HA) for the Waste Treatment and Immobilization Plant (WTP) Low Activity Waste (LAW) Melter Process (LMP) System. The primary purpose of this HSS field activity, on March 18-21, 2013, was to observe and understand the revised approach implemented by Bechtel National, Inc. (BNI), the contractor responsible for the design and construction of WTP for the U.S. Department of Energy (DOE) Office of

16

Summary - WTP Analytical Lab, BOF and LAW Waste Vitrification...  

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

an acilities No BOF syst Five LAW sy 1. LAW Me 2. LAW Me 3. LAW Of (TRL6) 4. LAW Co and 5. LAW De e team conclud ature to continu What the e assessment Testing the L Emission Sp...

17

Law and Order, or Counterintelligence Activities  

E-Print Network (OSTI)

assign responsibilities for carrying of firearms and the use of force by DoD personnel engaged in security, law and order, or counterintelligence activities. b. Cancels Deputy Secretary of Defense Memorandum (Reference (b)). c. Implements section 1585 of title 10, United States Code (U.S.C.) (Reference (c)), which authorizes civilian officers and employees of the Department of Defense to carry firearms or other appropriate weapons while assigned investigative duties or such other duties as the Secretary of Defense may prescribe, under regulations to be prescribed by the Secretary. d. Provides requirements, authorizations, and restrictions for carrying firearms and the use of force to protect DoD installations, property, and personnel, and to enforce law and order in accordance with DoD Instruction (DoDI) 5200.08 and DoD 5200.08-R (References (d) and (e)). e. Provides overarching guidance for developing DoD Component policies, regulations, and procedures.

unknown authors

2011-01-01T23:59:59.000Z

18

Independent Oversight Activity Report, Hanford Waste Treatment and  

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

October 2013 October 2013 Independent Oversight Activity Report, Hanford Waste Treatment and Immobilization Plant - October 2013 October 2013 Observation of Waste Treatment and Immobilization Plant Low Activity Waste Melter and Melter Off-gas Process System Hazards Analysis Activities [HIAR-WTP-2013-10-21] This Independent Activity Report documents an oversight activity conducted by the Office of Health, Safety and Security's (HSS) Office of Safety and Emergency Management Evaluations from October 21-31, 2013, at the Hanford Waste Treatment and Immobilization Plant (WTP). The activity consisted of HSS staff reviewing the Insight software hazard evaluation (HE) tables for hazard analysis (HA) generated to date for the WTP Low Activity Waste (LAW) Melter and Off-gas systems, observed a limited portion of the HA for the

19

Activity Report for Hanford WTP LAW Melter HA Development, July 31 - August 5, 2013  

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

HSS Independent Activity Report HSS Independent Activity Report Report Number: HIAR-WTP-2013-07-31 Site: Hanford Site Subject: Office of Enforcement and Oversight's Office of Safety and Emergency Management Evaluations Activity Report for Operational Awareness of Waste Treatment and Immobilization Plant Low Activity Waste Melter Process System Hazards Analysis Activity Dates of Activity : 07/31/13 - 08/05/13 Report Preparer: James O. Low Activity Description/Purpose: The Office of Health, Safety and Security (HSS) staff observed a limited portion of the hazards analysis (HA) for the Waste Treatment and Immobilization Plant (WTP) Low Activity Waste (LAW) Melter Process (LMP) system. The primary purpose of this HSS field activity, conducted from July 31 to August 5, 2013, was to observe and

20

Activity Report for Hanford WTP LAW Melter HA Development, July 31 - August 5, 2013  

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

HSS Independent Activity Report HSS Independent Activity Report Report Number: HIAR-WTP-2013-07-31 Site: Hanford Site Subject: Office of Enforcement and Oversight's Office of Safety and Emergency Management Evaluations Activity Report for Operational Awareness of Waste Treatment and Immobilization Plant Low Activity Waste Melter Process System Hazards Analysis Activity Dates of Activity : 07/31/13 - 08/05/13 Report Preparer: James O. Low Activity Description/Purpose: The Office of Health, Safety and Security (HSS) staff observed a limited portion of the hazards analysis (HA) for the Waste Treatment and Immobilization Plant (WTP) Low Activity Waste (LAW) Melter Process (LMP) system. The primary purpose of this HSS field activity, conducted from July 31 to August 5, 2013, was to observe and

Note: This page contains sample records for the topic "activity waste law" 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

Followup of Waste Treatment and Immobilization Plant Low Activity Waste Melter Process Systems Hazards Analysis Activity Review, March 2013  

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

HSS Independent Activity Report - HSS Independent Activity Report - Rev. 0 Report Number: HIAR-WTP-2013-03-18 Site: Hanford Site Subject: Office of Enforcement and Oversight's Office of Safety and Emergency Management Evaluations Activity Report for Follow-up of Waste Treatment and Immobilization Plant Low Activity Waste Melter Process System Hazards Analysis Activity Review Dates of Activity : 03/18/13 - 03/21/13 Report Preparer: James O. Low Activity Description/Purpose: The Office of Health, Safety and Security (HSS) staff observed a limited portion of the restart of the Hazard Analysis (HA) for the Waste Treatment and Immobilization Plant (WTP) Low Activity Waste (LAW) Melter Process (LMP) System. The primary purpose of this HSS field activity, on March 18-21, 2013, was to observe and understand the revised approach

22

Followup of Waste Treatment and Immobilization Plant Low Activity Waste Melter Process Systems Hazards Analysis Activity Review, March 2013  

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

HSS Independent Activity Report - HSS Independent Activity Report - Rev. 0 Report Number: HIAR-WTP-2013-03-18 Site: Hanford Site Subject: Office of Enforcement and Oversight's Office of Safety and Emergency Management Evaluations Activity Report for Follow-up of Waste Treatment and Immobilization Plant Low Activity Waste Melter Process System Hazards Analysis Activity Review Dates of Activity : 03/18/13 - 03/21/13 Report Preparer: James O. Low Activity Description/Purpose: The Office of Health, Safety and Security (HSS) staff observed a limited portion of the restart of the Hazard Analysis (HA) for the Waste Treatment and Immobilization Plant (WTP) Low Activity Waste (LAW) Melter Process (LMP) System. The primary purpose of this HSS field activity, on March 18-21, 2013, was to observe and understand the revised approach

23

Independent Activity Report, Hanford Waste Treatment Plant -...  

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

Independent Activity Report, Hanford Waste Treatment Plant - February 2011 February 2011 Hanford Waste Treatment Plant Construction Quality Assurance Review ARPT-WTP-2011-002...

24

WASTE TREATMENT TECHNOLOGY PROCESS DEVELOPMENT PLAN FOR HANFORD WASTE TREATMENT PLANT LOW ACTIVITY WASTE RECYCLE  

SciTech Connect

The purpose of this Process Development Plan is to summarize the objectives and plans for the technology development activities for an alternative path for disposition of the recycle stream that will be generated in the Hanford Waste Treatment Plant Low Activity Waste (LAW) vitrification facility (LAW Recycle). This plan covers the first phase of the development activities. The baseline plan for disposition of this stream is to recycle it to the WTP Pretreatment Facility, where it will be concentrated by evaporation and returned to the LAW vitrification facility. Because this stream contains components that are volatile at melter temperatures and are also problematic for the glass waste form, they accumulate in the Recycle stream, exacerbating their impact on the number of LAW glass containers. Approximately 32% of the sodium in Supplemental LAW comes from glass formers used to make the extra glass to dilute the halides to acceptable concentrations in the LAW glass, and reducing the halides in the Recycle is a key component of this work. Additionally, under possible scenarios where the LAW vitrification facility commences operation prior to the WTP Pretreatment facility, this stream does not have a proven disposition path, and resolving this gap becomes vitally important. This task seeks to examine the impact of potential future disposition of this stream in the Hanford tank farms, and to develop a process that will remove radionuclides from this stream and allow its diversion to another disposition path, greatly decreasing the LAW vitrification mission duration and quantity of glass waste. The origin of this LAW Recycle stream will be from the Submerged Bed Scrubber (SBS) and the Wet Electrostatic Precipitator (WESP) from the LAW melter off-gas system. The stream is expected to be a dilute salt solution with near neutral pH, and will likely contain some insoluble solids from melter carryover or precipitates of scrubbed components (e.g. carbonates). The soluble components are mostly sodium and ammonium salts of nitrate, chloride, and fluoride. This stream has not been generated yet, and will not be available until the WTP begins operation, causing uncertainty in its composition, particularly the radionuclide content. This plan will provide an estimate of the likely composition and the basis for it, assess likely treatment technologies, identify potential disposition paths, establish target treatment limits, and recommend the testing needed to show feasibility. Two primary disposition options are proposed for investigation, one is concentration for storage in the tank farms, and the other is treatment prior to disposition in the Effluent Treatment Facility. One of the radionuclides that is volatile and expected to be in high concentration in this LAW Recycle stream is Technetium-99 ({sup 99}Tc), a long-lived radionuclide with a half-life of 210,000 years. Technetium will not be removed from the aqueous waste in the Hanford Waste Treatment and Immobilization Plant (WTP), and will primarily end up immobilized in the LAW glass, which will be disposed in the Integrated Disposal Facility (IDF). Because {sup 99}Tc has a very long half-life and is highly mobile, it is the largest dose contributor to the Performance Assessment (PA) of the IDF. Other radionuclides that are also expected to be in appreciable concentration in the LAW Recycle are {sup 129}I, {sup 90}Sr, {sup 137}Cs, and {sup 241}Am. The concentrations of these radionuclides in this stream will be much lower than in the LAW, but they will still be higher than limits for some of the other disposition pathways currently available. Although the baseline process will recycle this stream to the Pretreatment Facility, if the LAW facility begins operation first, this stream will not have a disposition path internal to WTP. One potential solution is to return the stream to the tank farms where it can be evaporated in the 242- A evaporator, or perhaps deploy an auxiliary evaporator to concentrate it prior to return to the tank farms. In either case, testing is needed to evalua

McCabe, Daniel J.; Wilmarth, William R.; Nash, Charles A.

2013-08-29T23:59:59.000Z

25

Hanford Tank Waste - Near Source Treatment of Low Activity Waste  

SciTech Connect

Treatment and disposition of Hanford Site waste as currently planned consists of I 00+ waste retrievals, waste delivery through up to 8+ miles of dedicated, in-ground piping, centralized mixing and blending operations- all leading to pre-treatment combination and separation processes followed by vitrification at the Hanford Tank Waste Treatment and Immobilization Plant (WTP). The sequential nature of Tank Farm and WTP operations requires nominally 15-20 years of continuous operations before all waste can be retrieved from many Single Shell Tanks (SSTs). Also, the infrastructure necessary to mobilize and deliver the waste requires significant investment beyond that required for the WTP. Treating waste as closely as possible to individual tanks or groups- as allowed by the waste characteristics- is being investigated to determine the potential to 1) defer, reduce, and/or eliminate infrastructure requirements, and 2) significantly mitigate project risk by reducing the potential and impact of single point failures. The inventory of Hanford waste slated for processing and disposition as LAW is currently managed as high-level waste (HLW), i.e., the separation of fission products and other radionuclides has not commenced. A significant inventory ofthis waste (over 20M gallons) is in the form of precipitated saltcake maintained in single shell tanks, many of which are identified as potential leaking tanks. Retrieval and transport (as a liquid) must be staged within the waste feed delivery capability established by site infrastructure and WTP. Near Source treatment, if employed, would provide for the separation and stabilization processing necessary for waste located in remote farms (wherein most ofthe leaking tanks reside) significantly earlier than currently projected. Near Source treatment is intended to address the currently accepted site risk and also provides means to mitigate future issues likely to be faced over the coming decades. This paper describes the potential near source treatment and waste disposition options as well as the impact these options could have on reducing infrastructure requirements, project cost and mission schedule.

Ramsey, William Gene

2013-08-15T23:59:59.000Z

26

SOLIDIFICATION OF THE HANFORD LAW WASTE STREAM PRODUCED AS A RESULT OF NEAR-TANK CONTINUOUS SLUDGE LEACHING AND SODIUM HYDROXIDE RECOVERY  

Science Conference Proceedings (OSTI)

The U.S. Department of Energy (DOE), Office of River Protection (ORP), is responsible for the remediation and stabilization of the Hanford Site tank farms, including 53 million gallons of highly radioactive mixed wasted waste contained in 177 underground tanks. The plan calls for all waste retrieved from the tanks to be transferred to the Waste Treatment Plant (WTP). The WTP will consist of three primary facilities including pretreatment facilities for Low Activity Waste (LAW) to remove aluminum, chromium and other solids and radioisotopes that are undesirable in the High Level Waste (HLW) stream. Removal of aluminum from HLW sludge can be accomplished through continuous sludge leaching of the aluminum from the HLW sludge as sodium aluminate; however, this process will introduce a significant amount of sodium hydroxide into the waste stream and consequently will increase the volume of waste to be dispositioned. A sodium recovery process is needed to remove the sodium hydroxide and recycle it back to the aluminum dissolution process. The resulting LAW waste stream has a high concentration of aluminum and sodium and will require alternative immobilization methods. Five waste forms were evaluated for immobilization of LAW at Hanford after the sodium recovery process. The waste forms considered for these two waste streams include low temperature processes (Saltstone/Cast stone and geopolymers), intermediate temperature processes (steam reforming and phosphate glasses) and high temperature processes (vitrification). These immobilization methods and the waste forms produced were evaluated for (1) compliance with the Performance Assessment (PA) requirements for disposal at the IDF, (2) waste form volume (waste loading), and (3) compatibility with the tank farms and systems. The iron phosphate glasses tested using the product consistency test had normalized release rates lower than the waste form requirements although the CCC glasses had higher release rates than the quenched glasses. However, the waste form failed to meet the vapor hydration test criteria listed in the WTP contract. In addition, the waste loading in the phosphate glasses were not as high as other candidate waste forms. Vitrification of HLW waste as borosilicate glass is a proven process; however the HLW and LAW streams at Hanford can vary significantly from waste currently being immobilized. The ccc glasses show lower release rates for B and Na than the quenched glasses and all glasses meet the acceptance criterion of < 4 g/L. Glass samples spiked with Re{sub 2}O{sub 7} also passed the PCT test. However, further vapor hydration testing must be performed since all the samples cracked and the test could not be performed. The waste loading of the iron phosphate and borosilicate glasses are approximately 20 and 25% respectively. The steam reforming process produced the predicted waste form for both the high and low aluminate waste streams. The predicted waste loadings for the monolithic samples is approximately 39%, which is higher than the glass waste forms; however, at the time of this report, no monolithic samples were made and therefore compliance with the PA cannot be determined. The waste loading in the geopolymer is approximately 40% but can vary with the sodium hydroxide content in the waste stream. Initial geopolymer mixes revealed compressive strengths that are greater than 500 psi for the low aluminate mixes and less than 500 psi for the high aluminate mixes. Further work testing needs to be performed to formulate a geopolymer waste form made using a high aluminate salt solution. A cementitious waste form has the advantage that the process is performed at ambient conditions and is a proven process currently in use for LAW disposal. The Saltstone/Cast Stone formulated using low and high aluminate salt solutions retained at least 97% of the Re that was added to the mix as a dopant. While this data is promising, additional leaching testing must be performed to show compliance with the PA. Compressive strength tests must also be performed on the Cast Ston

Reigel, M.; Johnson, F.; Crawford, C.; Jantzen, C.

2011-09-20T23:59:59.000Z

27

RADIOACTIVE DEMONSTRATIONS OF FLUIDIZED BED STEAM REFORMING (FBSR) WITH HANFORD LOW ACTIVITY WASTES  

SciTech Connect

Several supplemental technologies for treating and immobilizing Hanford low activity waste (LAW) are being evaluated. One immobilization technology being considered is Fluidized Bed Steam Reforming (FBSR) which offers a low temperature (700-750°C) continuous method by which wastes high in organics, nitrates, sulfates/sulfides, or other aqueous components may be processed into a crystalline ceramic (mineral) waste form. The granular waste form produced by co-processing the waste with kaolin clay has been shown to be as durable as LAW glass. The FBSR granular product will be monolithed into a final waste form. The granular component is composed of insoluble sodium aluminosilicate (NAS) feldspathoid minerals such as sodalite. Production of the FBSR mineral product has been demonstrated both at the industrial, engineering, pilot, and laboratory scales on simulants. Radioactive testing at SRNL commenced in late 2010 to demonstrate the technology on radioactive LAW streams which is the focus of this study.

Jantzen, C.; Crawford, C.; Burket, P.; Bannochie, C.; Daniel, G.; Nash, C.; Cozzi, A.; Herman, C.

2012-10-22T23:59:59.000Z

28

Radioactive Demonstrations Of Fluidized Bed Steam Reforming (FBSR) With Hanford Low Activity Wastes  

Science Conference Proceedings (OSTI)

Several supplemental technologies for treating and immobilizing Hanford low activity waste (LAW) are being evaluated. One immobilization technology being considered is Fluidized Bed Steam Reforming (FBSR) which offers a low temperature (700-750?C) continuous method by which wastes high in organics, nitrates, sulfates/sulfides, or other aqueous components may be processed into a crystalline ceramic (mineral) waste form. The granular waste form produced by co-processing the waste with kaolin clay has been shown to be as durable as LAW glass. The FBSR granular product will be monolithed into a final waste form. The granular component is composed of insoluble sodium aluminosilicate (NAS) feldspathoid minerals such as sodalite. Production of the FBSR mineral product has been demonstrated both at the industrial, engineering, pilot, and laboratory scales on simulants. Radioactive testing at SRNL commenced in late 2010 to demonstrate the technology on radioactive LAW streams which is the focus of this study.

Jantzen, C. M.; Crawford, C. L.; Burket, P. R.; Bannochie, C. J.; Daniel, W. G.; Nash, C. A.; Cozzi, A. D.; Herman, C. C.

2012-10-22T23:59:59.000Z

29

RADIOACTIVE DEMONSTRATIONS OF FLUIDIZED BED STEAM REFORMING AS A SUPPLEMENTARY TREATMENT FOR HANFORD'S LOW ACTIVITY WASTE AND SECONDARY WASTES  

SciTech Connect

The U.S. Department of Energy's Office of River Protection (ORP) is responsible for the retrieval, treatment, immobilization, and disposal of Hanford's tank waste. Currently there are approximately 56 million gallons of highly radioactive mixed wastes awaiting treatment. A key aspect of the River Protection Project (RPP) cleanup mission is to construct and operate the Waste Treatment and Immobilization Plant (WTP). The WTP will separate the tank waste into high-level and low-activity waste (LAW) fractions, both of which will subsequently be vitrified. The projected throughput capacity of the WTP LAW Vitrification Facility is insufficient to complete the RPP mission in the time frame required by the Hanford Federal Facility Agreement and Consent Order, also known as the Tri-Party Agreement (TPA), i.e. December 31, 2047. Therefore, Supplemental Treatment is required both to meet the TPA treatment requirements as well as to more cost effectively complete the tank waste treatment mission. The Supplemental Treatment chosen will immobilize that portion of the retrieved LAW that is not sent to the WTP's LAW Vitrification facility into a solidified waste form. The solidified waste will then be disposed on the Hanford site in the Integrated Disposal Facility (IDF). In addition, the WTP LAW vitrification facility off-gas condensate known as WTP Secondary Waste (WTP-SW) will be generated and enriched in volatile components such as Cs-137, I-129, Tc-99, Cl, F, and SO4 that volatilize at the vitrification temperature of 1150 C in the absence of a continuous cold cap. The current waste disposal path for the WTP-SW is to recycle it to the supplemental LAW treatment to avoid a large steady state accumulation in the pretreatment-vitrification loop. Fluidized Bed Steam Reforming (FBSR) offers a moderate temperature (700-750 C) continuous method by which LAW and/or WTP-SW wastes can be processed irrespective of whether they contain organics, nitrates, sulfates/sulfides, chlorides, fluorides, volatile radionuclides or other aqueous components. The FBSR technology can process these wastes into a crystalline ceramic (mineral) waste form. The mineral waste form that is produced by co-processing waste with kaolin clay in an FBSR process has been shown to be as durable as LAW glass. Monolithing of the granular FBSR product is being investigated to prevent dispersion during transport or burial/storage but is not necessary for performance. A Benchscale Steam Reformer (BSR) was designed and constructed at the Savannah River National Laboratory (SRNL) to treat actual radioactive wastes to confirm the findings of the non-radioactive FBSR pilot scale tests and to qualify the waste form for applications at Hanford. Radioactive testing commenced in 2010 with a demonstration of Hanford's WTP-SW where Savannah River Site (SRS) High Level Waste (HLW) secondary waste from the Defense Waste Processing Facility (DWPF) was shimmed with a mixture of I-125/129 and Tc-99 to chemically resemble WTP-SW. Ninety six grams of radioactive product were made for testing. The second campaign commenced using SRS LAW chemically trimmed to look like Hanford's LAW. Six hundred grams of radioactive product were made for extensive testing and comparison to the non-radioactive pilot scale tests. The same mineral phases were found in the radioactive and non-radioactive testing.

Jantzen, C.; Crawford, C.; Cozzi, A.; Bannochie, C.; Burket, P.; Daniel, G.

2011-02-24T23:59:59.000Z

30

(FBSR) with Hanford Low Activity Wastes - Programmaster.org  

Science Conference Proceedings (OSTI)

... of Fluidized Bed Steam Reforming (FBSR) with Hanford Low Activity Wastes ... Level Waste at the Defense Waste Processing Facility through Sludge Batch 7b.

31

Idaho Chemical Processing Plant low-activity waste grout stabilization development program FY-97 status report  

SciTech Connect

The general purpose of the Grout Development Program is to solidify and stabilize the liquid low-activity wastes (LAW) generated at the Idaho Chemical Processing Plant (ICPP). It is anticipated that LAW will be produced from the following: (1) chemical separation of the tank farm high-activity sodium-bearing waste, (2) retrieval, dissolution, and chemical separation of the aluminum, zirconium, and sodium calcines, (3) facility decontamination processes, and (4) process equipment waste. Grout formulation studies for sodium-bearing LAW, including decontamination and process equipment waste, continued this fiscal year. A second task was to develop a grout formulation to solidify potential process residual heels in the tank farm vessels when the vessels are closed.

Herbst, A.K.; Marshall, D.W.; McCray, J.A.

1998-02-01T23:59:59.000Z

32

Summary - System Planning for Low-Activity Waste Treatment at Hanford  

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

Hanford Hanford EM Project: WTP ETR Report Date: November 2008 ETR-18 United States Department of Energy Office of Environmental Management (DOE-EM) External Technical Review of System Planning for Low-Activity Waste Treatment at Hanford Why DOE-EM Did This Review Construction of the facilities of the Hanford site's Waste Treatment Plant (WTP) are scheduled for completion in 2017, with radioactive waste processing scheduled to begin in 2019. An estimated 23 to 35 years will then be required to complete high-level waste (HLW) vitrification. However, vitrification of low-activity waste (LAW) may extend the WTP mission duration by decades more if supplemental LAW processing beyond the capacity of the present facility is not incorporated. The purpose of this independent review was to

33

Independent Activity Report, Waste Treatment and Immobilization Plant- March 2013  

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

Follow-up of Waste Treatment and Immobilization Plant Low Activity Waste Melter Process System Hazards Analysis Activity Review [HIAR-WTP-2013-03-18

34

Activity Report for Waste Treatment and Immobilizationi Plant...  

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

and Oversight's Office of Safety and Emergency Management Evaluations Activity Report for Waste Treatment and Immobilization Plant Low Activity Waste Melter Off-gas Process...

35

WASTE LOADING ENHANCEMENTS FOR HANFORD LAW GLASSES VLS-10R1790-1 FINAL REPORT REV 0 12/1/2010  

SciTech Connect

About 50 million gallons of high-level mixed waste is currently stored in underground tanks at The United States Department of Energy's (DOE's) Hanford site in the State of Washington. The Hanford Tank Waste Treatment and Immobilization Plant (WTP) will provide DOE's Office of River Protection (ORP) with a means of treating this waste by vitrification for subsequent disposal. The tank waste will be separated into low- and high-activity waste fractions, which will then be vitrified respectively into Immobilized Low Activity Waste (ILAW) and Immobilized High Level Waste (IHLW) products. The ILAW product will be disposed in an engineered facility on the Hanford site while the IHLW product will likely be directed to a national deep geological disposal facility for high-level nuclear waste. The ILAW and IHLW products must meet a variety of requirements with respect to protection of the environment before they can be accepted for disposal. The Office of River Protection is currently examining options to optimize the Low Activity Waste (LAW) Facility and LAW glass waste form. One option under evaluation is to enhance the waste processing rate of the vitrification plant currently under construction. It is likely that the capacity of the LAW vitrification plant can be increased incrementally by implementation of a variety of low-risk, high-probability changes, either separately or in combination. These changes include: (1) Operating at the higher processing rates demonstrated at the LAW pilot melter; (2) Increasing the glass pool surface area within the existing external melter envelope; (3) Increasing the glass waste loading; and (4) Operating the melter at a slightly higher temperature. The Vitreous State Laboratory (VSL) of The Catholic University of America (CUA) and Energy Solutions, Inc. have evaluated several of these potential incremental improvements for ORP in support of its evaluation of WTP LAW facility optimization. Some of these incremental improvements have been tested at VSL including increasing the waste loading, increasing the processing temperature, and increasing the fraction of the sulfur in the feed that is partitioned to the off-gas (in the event that a decision is made to break the present WTP recycle loop). These approaches successfully demonstrated increases in glass production rates and significant increases in sulfate incorporation at the nominal melter operating temperature of 1150 C and at slightly higher than nominal glass processing temperatures. Subsequent tests demonstrated further enhancement of glass formulations for all of the LAW waste envelopes, thereby reducing the amount of glass to be produced by the WTP for the same amount of waste processed. The next phase of testing determined the applicability of these improvements over the expected range of sodium and sulfur concentrations for Hanford LAW. This approach was subsequently applied to an even wider range of LAW wastes types, including those with high potassium concentration. The feasibility of formulating higher waste loading glasses using SnO{sub 2} and V{sub 2}O{sub 5} in place of Fe{sub 2}O{sub 3} and TiO{sub 2} as glass former additives was also evaluated. The present report provides data from investigation of the effects of magnesium content (up to {approx}10 wt%) on LAW glass properties and from work to identify improved high waste loading glass formulations that meets all processing and product quality requirements for two waste compositions. The scope of testing is detailed in the Test Plan for this work. A glass composition previously developed and tested at VSL for LAW from tank AN-105 (LAWA187) was varied by substituting Mg for other glass former additives such as Ca, B and Si in an attempt to formulate a glass with improved properties, such as higher waste loading and greater sulfur tolerance. The results were used to reformulate another glass (ORPLG9) developed for LAW from tank AP-101 that contains high concentrations of alkalis (Na and K). Glass formulation goals for this waste were to increase the sulfur tolerance of the

KRUGER AA; MULLER IS; JOSEPH I; MATLACK KS; GAN H; PEGG IL

2010-12-28T23:59:59.000Z

36

WASTE LOADING ENHANCEMENTS FOR HANFORD LAW GLASSES VLS-10R1790-1 FINAL REPORT REV 0 12/1/2010  

Science Conference Proceedings (OSTI)

About 50 million gallons of high-level mixed waste is currently stored in underground tanks at The United States Department of Energy's (DOE's) Hanford site in the State of Washington. The Hanford Tank Waste Treatment and Immobilization Plant (WTP) will provide DOE's Office of River Protection (ORP) with a means of treating this waste by vitrification for subsequent disposal. The tank waste will be separated into low- and high-activity waste fractions, which will then be vitrified respectively into Immobilized Low Activity Waste (ILAW) and Immobilized High Level Waste (IHLW) products. The ILAW product will be disposed in an engineered facility on the Hanford site while the IHLW product will likely be directed to a national deep geological disposal facility for high-level nuclear waste. The ILAW and IHLW products must meet a variety of requirements with respect to protection of the environment before they can be accepted for disposal. The Office of River Protection is currently examining options to optimize the Low Activity Waste (LAW) Facility and LAW glass waste form. One option under evaluation is to enhance the waste processing rate of the vitrification plant currently under construction. It is likely that the capacity of the LAW vitrification plant can be increased incrementally by implementation of a variety of low-risk, high-probability changes, either separately or in combination. These changes include: (1) Operating at the higher processing rates demonstrated at the LAW pilot melter; (2) Increasing the glass pool surface area within the existing external melter envelope; (3) Increasing the glass waste loading; and (4) Operating the melter at a slightly higher temperature. The Vitreous State Laboratory (VSL) of The Catholic University of America (CUA) and Energy Solutions, Inc. have evaluated several of these potential incremental improvements for ORP in support of its evaluation of WTP LAW facility optimization. Some of these incremental improvements have been tested at VSL including increasing the waste loading, increasing the processing temperature, and increasing the fraction of the sulfur in the feed that is partitioned to the off-gas (in the event that a decision is made to break the present WTP recycle loop). These approaches successfully demonstrated increases in glass production rates and significant increases in sulfate incorporation at the nominal melter operating temperature of 1150 C and at slightly higher than nominal glass processing temperatures. Subsequent tests demonstrated further enhancement of glass formulations for all of the LAW waste envelopes, thereby reducing the amount of glass to be produced by the WTP for the same amount of waste processed. The next phase of testing determined the applicability of these improvements over the expected range of sodium and sulfur concentrations for Hanford LAW. This approach was subsequently applied to an even wider range of LAW wastes types, including those with high potassium concentration. The feasibility of formulating higher waste loading glasses using SnO{sub 2} and V{sub 2}O{sub 5} in place of Fe{sub 2}O{sub 3} and TiO{sub 2} as glass former additives was also evaluated. The present report provides data from investigation of the effects of magnesium content (up to {approx}10 wt%) on LAW glass properties and from work to identify improved high waste loading glass formulations that meets all processing and product quality requirements for two waste compositions. The scope of testing is detailed in the Test Plan for this work. A glass composition previously developed and tested at VSL for LAW from tank AN-105 (LAWA187) was varied by substituting Mg for other glass former additives such as Ca, B and Si in an attempt to formulate a glass with improved properties, such as higher waste loading and greater sulfur tolerance. The results were used to reformulate another glass (ORPLG9) developed for LAW from tank AP-101 that contains high concentrations of alkalis (Na and K). Glass formulation goals for this waste were to increase the sulfur tolerance of the

KRUGER AA; MULLER IS; JOSEPH I; MATLACK KS; GAN H; PEGG IL

2010-12-28T23:59:59.000Z

37

Vitrification of Three Low-Activity Radioactive Waste Streams from Hanford  

Science Conference Proceedings (OSTI)

As part of a demonstration for British Nuclear Fuels Limited, Incorporated (BNFL), the Immobilization Technology Section (ITS) of the Savannah River Technology Center (SRTC) has produced and characterized three low-activity waste (LAW) glasses from Hanford radioactive waste samples. The three LAW glasses were produced from radioactive supernate samples that had been treated by the Waste Processing Technology Section (WPTS) at SRTC to remove most of the radionuclides. These three glasses were produced by mixing the waste streams with between four and nine glass-forming chemicals in platinum/gold crucibles and heating the mixture to between 1120 and 1150 degrees C. Compositions of the resulting glass waste forms were close to the target compositions. Low concentrations of radionuclides in the LAW feed streams and, therefore, in the glass waste forms supported WPTS conclusions that pretreatment had been successful. No crystals were detected in the LAW glasses. In addition, all glass waste forms passed the leach tests that were performed. These included a 20 degrees C Product Consistency Test (PCT) and a modified version of the United States Environmental Protection Agency Toxicity Characteristic Leaching Procedure (TCLP).

Ferrara, D.M.; Crawford, C.L.; Ha, B.C.; Bibler, N.E.

1998-09-01T23:59:59.000Z

38

RADIOACTIVE DEMONSTRATIONS OF FLUIDIZED BED STEAM REFORMING WITH ACUTAL HANFORD LOW ACTIVITY WASTES VERIFYING FBSR AS A SUPPLEMENTARY TREATMENT  

SciTech Connect

The U.S. Department of Energy's Office of River Protection is responsible for the retrieval, treatment, immobilization, and disposal of Hanford's tank waste. Currently there are approximately 56 million gallons of highly radioactive mixed wastes awaiting treatment. A key aspect of the River Protection Project cleanup mission is to construct and operate the Waste Treatment and Immobilization Plant (WTP). The WTP will separate the tank waste into high-level waste (HLW) and low-activity waste (LAW) fractions, both of which will subsequently be vitrified. The projected throughput capacity of the WTP LAW Vitrification Facility is insufficient to complete the cleanup mission in the time frame required by the Hanford Federal Facility Agreement and Consent Order, also known as the Tri-Party Agreement (TPA). Therefore, Supplemental Treatment is required both to meet the TPA treatment requirements as well as to more cost effectively complete the tank waste treatment mission. Fluidized Bed Steam Reforming (FBSR) is one of the supplementary treatments being considered. FBSR offers a moderate temperature (700-750 C) continuous method by which LAW and other secondary wastes can be processed irrespective of whether they contain organics, nitrates/nitrites, sulfates/sulfides, chlorides, fluorides, and/or radio-nuclides like I-129 and Tc-99. Radioactive testing of Savannah River LAW (Tank 50) shimmed to resemble Hanford LAW and actual Hanford LAW (SX-105 and AN-103) have produced a ceramic (mineral) waste form which is the same as the non-radioactive waste simulants tested at the engineering scale. The radioactive testing demonstrated that the FBSR process can retain the volatile radioactive components that cannot be contained at vitrification temperatures. The radioactive and nonradioactive mineral waste forms that were produced by co-processing waste with kaolin clay in an FBSR process are shown to be as durable as LAW glass.

Jantzen, C.; Crawford, C.; Burket, P.; Bannochie, C.; Daniel, G.; Nash, C.; Cozzi, A.; Herman, C.

2012-01-12T23:59:59.000Z

39

Waste Treatment and Immobilization Plant (WTP) Analytical Laboratory (LAB),  

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

Immobilization Plant (WTP) Analytical Immobilization Plant (WTP) Analytical Laboratory (LAB), Balance of Facilities (BOF) and Low-Activity Waste Vitrification Facilities (LAW) Waste Treatment and Immobilization Plant (WTP) Analytical Laboratory (LAB), Balance of Facilities (BOF) and Low-Activity Waste Vitrification Facilities (LAW) Full Document and Summary Versions are available for download Waste Treatment and Immobilization Plant (WTP) Analytical Laboratory (LAB), Balance of Facilities (BOF) and Low-Activity Waste Vitrification Facilities (LAW) Summary - WTP Analytical Lab, BOF and LAW Waste Vitrification Facilities More Documents & Publications Waste Treatment and Immobilation Plant HLW Waste Vitrification Facility Waste Treatment and Immobilation Plant Pretreatment Facility Compilation of TRA Summaries

40

Independent Activity Report, Hanford Waste Treatment Plant - February 2011  

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

Activity Report, Hanford Waste Treatment Plant - Activity Report, Hanford Waste Treatment Plant - February 2011 Independent Activity Report, Hanford Waste Treatment Plant - February 2011 February 2011 Hanford Waste Treatment Plant Construction Quality Assurance Review [ARPT-WTP-2011-002] The purpose of the visit was to perform a review of construction quality assurance at the Waste Treatment Plant (WTP) site activities concurrently with the Department of Energy (DOE) WTP staff. One focus area for this visit was piping and pipe support installations. Independent Activity Report, Hanford Waste Treatment Plant - February 2011 More Documents & Publications Independent Oversight Review, Waste Treatment and Immobilization Plant - August 2011 Independent Oversight Review, Waste Treatment and Immobilization Plant -

Note: This page contains sample records for the topic "activity waste law" 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

Single Pass Flow-Through (SPFT) Test Results of Fluidized Bed Steam Reforming (FBSR) Waste Forms used for LAW Immobilization  

Science Conference Proceedings (OSTI)

Several supplemental technologies for treating and immobilizing Hanford low activity waste (LAW) are being evaluated. One such immobilization technology being considered is the Fluidized Bed Steam Reforming (FBSR) granular product. The FBSR granular product is composed of insoluble sodium aluminosilicate (NAS) feldspathoid minerals. Production of the FBSR mineral product has been demonstrated both at the industrial and laboratory scale. Single-Pass Flow-Through (SPFT) tests at various flow rates have been conducted with the granular products fabricated using these two methods. Results show that the materials exhibit a relatively low forward dissolution rate on the order of 10-3 g/(m2d) with the material made in the laboratory giving slightly higher values.

Neeway, James J.; Qafoku, Nikolla; Williams, Benjamin D.; Valenta, Michelle M.; Cordova, Elsa A.; Strandquist, Sara C.; Dage, DeNomy C.; Brown, Christopher F.

2012-03-20T23:59:59.000Z

42

Technology development activities supporting tank waste remediation  

Science Conference Proceedings (OSTI)

This document summarizes work being conducted under the U.S. Department of Energy`s Office of Technology Development (EM-50) in support of the Tank Waste Remediation System (TWRS) Program. The specific work activities are organized by the following categories: safety, characterization, retrieval, barriers, pretreatment, low-level waste, and high-level waste. In most cases, the activities presented here were identified as supporting tank remediation by EM-50 integrated program or integrated demonstration lead staff and the selections were further refined by contractor staff. Data sheets were prepared from DOE-HQ guidance to the field issued in September 1993. Activities were included if a significant portion of the work described provides technology potentially needed by TWRS; consequently, not all parts of each description necessarily support tank remediation.

Bonner, W.F.; Beeman, G.H.

1994-06-01T23:59:59.000Z

43

Nonlinear Wave-Activity Conservation Laws and Hamiltonian Structure for the Two-Dimensional Anelastic Equations  

Science Conference Proceedings (OSTI)

Exact, finite-amplitude, local wave-activity conservation laws are derived for disturbances to steady flows in the context of the two-dimensional anelastic equations. The conservation laws are expressed entirely in terms of Eulerian quantities, ...

J. F. Scinocca; T. G. Shepherd

1992-01-01T23:59:59.000Z

44

THE TREATMENT OF LOW ACTIVITY AQUEOUS WASTES  

SciTech Connect

The equipment and treatment methods for processing low-activity aqueous wastes at the Latina nuclear power station are discussed. The effluent treatment plant serves two purposes: purification of cooling pond water and decontamination of aqueous wastes from such outlets as regenerant solutions, active laundry and change houses, decontamination center, coffin washing, and charge machine washing. The treatment process consists of chemical precipitation followed by filtration of the sludges thus produced. The process is then followed by ion exchange on a natural inorganic material such as vermiculite and evaporation. This process produces a decontamination factor of l0/sup 3/ to 10/ sup 4/. (N.W.R.)

Cartwright, A.C.

1962-01-01T23:59:59.000Z

45

DEVELOPMENT QUALIFICATION AND DISPOSAL OF AN ALTERNATIVE IMMOBILIZED LOW-ACTIVITY WASTE FORM AT THE HANFORD SITE  

SciTech Connect

Demonstrating that a waste form produced by a given immobilization process is chemically and physically durable as well as compliant with disposal facility acceptance criteria is critical to the success of a waste treatment program, and must be pursued in conjunction with the maturation of the waste processing technology. Testing of waste forms produced using differing scales of processing units and classes of feeds (simulants versus actual waste) is the crux of the waste form qualification process. Testing is typically focused on leachability of constituents of concern (COCs), as well as chemical and physical durability of the waste form. A principal challenge regarding testing immobilized low-activity waste (ILAW) forms is the absence of a standard test suite or set of mandatory parameters against which waste forms may be tested, compared, and qualified for acceptance in existing and proposed nuclear waste disposal sites at Hanford and across the Department of Energy (DOE) complex. A coherent and widely applicable compliance strategy to support characterization and disposal of new waste forms is essential to enhance and accelerate the remediation of DOE tank waste. This paper provides a background summary of important entities, regulations, and considerations for nuclear waste form qualification and disposal. Against this backdrop, this paper describes a strategy for meeting and demonstrating compliance with disposal requirements emphasizing the River Protection Project (RPP) Integrated Disposal Facility (IDF) at the Hanford Site and the fluidized bed steam reforming (FBSR) mineralized low-activity waste (LAW) product stream.

SAMS TL; EDGE JA; SWANBERG DJ; ROBBINS RA

2011-01-13T23:59:59.000Z

46

Initial Selection of Supplemental Treatment Technologies for Hanford's Low-Activity Tank Waste  

Science Conference Proceedings (OSTI)

In 2002, the U.S. Department of Energy (DOE) documented a plan for accelerating cleanup of the Hanford Site, located in southeastern Washington State, by at least 35 years (DOE 2002). A key element of the accelerated cleanup plan was a strategic initiative for acceleration of the tank waste program and completion of "tank waste treatment by 2028 by increasing the capacity of the planned Waste Treatment Plant (ETP) and using supplemental technologies for waste treatment and immobilization." The plan identified specific technologies to be evaluated for supplemental treatment of as much as 70% of the low-activity waste (LAW). The objective was to complete required testing and evaluation that would "...bring an appropriate combination of the above technologies to deployment to supplement LAW treatment and immobilization in the WTP to achieve the completion of tank waste treatment by 2028." In concert with this acceleration plan, DOE, the U.S. Environmental Protection Agency, and the Washington State Department of Ecology have proposed to accelerate from 2012 to 2005 the Hanford Federal Facility Compliance Agreement (Tri-Party Agreement) milestone (M-62-08) associated with a final decision on treatment of the balance of tank waste that is beyond the capacity of the currently designed WTP.

Raymond, Richard E.; Powell, Roger W.; Hamilton, Dennis W.; Kitchen, William A.; Mauss, Billie M.; Brouns, Thomas M.

2004-07-15T23:59:59.000Z

47

RADIOACTIVE DEMONSTRATION OF MINERALIZED WASTE FORMS MADE FROM HANFORD LOW ACTIVITY WASTE (TANK FARM BLEND) BY FLUIDIZED BED STEAM REFORMATION (FBSR)  

Science Conference Proceedings (OSTI)

The U.S. Department of Energy’s Office of River Protection (ORP) is responsible for the retrieval, treatment, immobilization, and disposal of Hanford’s tank waste. A key aspect of the River Protection Project (RPP) cleanup mission is to construct and operate the Hanford Tank Waste Treatment and Immobilization Plant (WTP). The WTP will separate the tank waste into high-level and low-activity waste (LAW) fractions, both of which will subsequently be vitrified. The projected throughput capacity of the WTP LAW Vitrification Facility is insufficient to complete the RPP mission in the time frame required by the Hanford Federal Facility Agreement and Consent Order, also known as the Tri-Party Agreement (TPA), i.e. December 31, 2047. Supplemental Treatment is likely to be required both to meet the TPA treatment requirements as well as to more cost effectively complete the tank waste treatment mission. The Supplemental Treatment chosen will immobilize that portion of the retrieved LAW that is not sent to the WTP’s LAW Vitrification facility into a solidified waste form. The solidified waste will then be disposed on the Hanford site in the Integrated Disposal Facility (IDF). Fluidized Bed Steam Reforming (FBSR) offers a moderate temperature (700-750°C) continuous method by which LAW can be processed irrespective of whether the waste contain organics, nitrates, sulfates/sulfides, chlorides, fluorides, volatile radionuclides or other aqueous components. The FBSR technology can process these wastes into a crystalline ceramic (mineral) waste form. The mineral waste form that is produced by co-processing waste with kaolin clay in an FBSR process has been shown to be comparable to LAW glass, i.e. leaches Tc-99, Re and Na at 6 (the Hanford IDF criteria for Na) in the first few hours. The granular and monolithic waste forms also pass the EPA Toxicity Characteristic Leaching Procedure (TCLP) for all Resource Conservation and Recovery Act (RCRA) components at the Universal Treatment Standards (UTS). Two identical Benchscale Steam Reformers (BSR) were designed and constructed at SRNL, one to treat non-radioactive simulants and the other to treat actual radioactive wastes. The results from the non-radioactive BSR were used to determine the parameters needed to operate the radioactive BSR in order to confirm the findings of non-radioactive FBSR pilot scale and engineering scale tests and to qualify an FBSR LAW waste form for applications at Hanford. Radioactive testing commenced using SRS LAW from Tank 50 chemically trimmed to look like Hanford’s blended LAW known as the Rassat simulant as this simulant composition had been tested in the non-radioactive BSR, the non-radioactive pilot scale FBSR at the Science Applications International Corporation-Science and Technology Applications Research (SAIC-STAR) facility in Idaho Falls, ID and in the TTT Engineering Scale Technology Demonstration (ESTD) at Hazen Research Inc. (HRI) in Denver, CO. This provided a “tie back” between radioactive BSR testing and non-radioactive BSR, pilot scale, and engineering scale testing. Approximately six hundred grams of non-radioactive and radioactive BSR product were made for extensive testing and comparison to the non-radioactive pilot scale tests performed in 2004 at SAIC-STAR and the engineering scale test performed in 2008 at HRI with the Rassat simulant. The same mineral phases and off-gas species were found in the radioactive and non-radioactive testing. The granular ESTD and BSR products (radioactive and non-radioactive) were analyzed for to

Jantzen, C. M.; Crawford, C. L.; Bannochie, C. J.; Burket, P. R.; Cozzi, A. D.; Daniel, W. E.; Hall, H. K.; Miller, D. H.; Missimer, D. M.; Nash, C. A.; Williams, M. F.

2013-08-21T23:59:59.000Z

48

Nuclear Waste Fund Activities Management Team | Department of Energy  

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

Waste Fund Activities Management Team Waste Fund Activities Management Team Nuclear Waste Fund Activities Management Team The Nuclear Waste Fund Activities Management Team has responsibility to: Manage the investments and expenditures of the Nuclear Waste Fund; Support correspondence regarding Nuclear Waste Policy Act issues raised by congressional, Inspector General, Government Accounting Office and Freedom of Information Act inquiries; and, Manage the annual fee adequacy assessment process. Applicable Documents Nuclear Waste Policy Act of 1982 Standard Contract for Disposal of Spent Nuclear Fuel and/or High-Level Radioactive Waste Standard Contract Amendment for New Reactors FY 2007 Total System Life Cycle Cost, Pub 2008 FY 2007 Fee Adequacy, Pub 2008 2009 Letter to Congress OCRWM Financial Statements for Annual Report for Years Ended

49

X-RAY FLUORESCENCE ANALYSIS OF HANFORD LOW ACTIVITY WASTE SIMULANTS  

Science Conference Proceedings (OSTI)

Savannah River National Laboratory (SRNL) was requested to develop an x-ray fluorescence (XRF) spectrometry method for elemental characterization of the Hanford Tank Waste Treatment and Immobilization Plant (WTP) pretreated low activity waste (LAW) stream to the LAW Vitrification Plant. The WTP is evaluating the potential for using XRF as a rapid turnaround technique to support LAW product compliance and glass former batching. The overall objective of this task was to develop XRF analytical methods that provide the rapid turnaround time (with the objective of optimizing the XRF methodology. Three XRF sample methods used for preparing the LAW sub-sample for XRF analysis were studied: direct liquid analysis, dried spot, and fused glass. The direct liquid method was selected because its major advantage is that the LAW can be analyzed directly without any sample alteration that could bias the method accuracy. It also is the fastest preparation technique--a typical XRF measurement could be completed in with percent relative standard deviations (%RSDs) % for most elements in filtered solution. There were some issues with a few elements precipitating out of solution over time affecting the long term precision of the method. Additional research will need to be performed to resolve this sample stability problem. Activities related to methodology optimization in the Phase 1b portion of the study were eliminated as a result of WTP request to discontinue remaining activities due to funding reduction. These preliminary studies demonstrate that developing an XRF method to support the LAW vitrification plant is feasible. When funding is restored for the WTP, it is recommended that optimization of this technology should be pursued.

Jurgensen, A; David Missimer, D; Ronny Rutherford, R

2006-05-08T23:59:59.000Z

50

Hazard Evaluation for Waste Feed Delivery Operations and Activities  

Science Conference Proceedings (OSTI)

This document contains the results of the hazard analysis that has been performed to address Waste Feed Delivery operations and activities.

RYAN, G.W.

2000-03-10T23:59:59.000Z

51

Waste management activities and carbon emissions in Africa  

Science Conference Proceedings (OSTI)

This paper summarizes research into waste management activities and carbon emissions from territories in sub-Saharan Africa with the main objective of quantifying emission reductions (ERs) that can be gained through viable improvements to waste management in Africa. It demonstrates that data on waste and carbon emissions is poor and generally inadequate for prediction models. The paper shows that the amount of waste produced and its composition are linked to national Gross Domestic Product (GDP). Waste production per person is around half that in developed countries with a mean around 230 kg/hd/yr. Sub-Saharan territories produce waste with a biogenic carbon content of around 56% (+/-25%), which is approximately 40% greater than developed countries. This waste is disposed in uncontrolled dumps that produce large amounts of methane gas. Greenhouse gas (GHG) emissions from waste will rise with increasing urbanization and can only be controlled through funding mechanisms from developed countries.

Couth, R. [University of KwaZulu-Natal, CRECHE, School of Civil Engineering, Survey and Construction, Durban 4041 (South Africa); Trois, C., E-mail: troisc@ukzn.ac.za [University of KwaZulu-Natal, CRECHE, School of Civil Engineering, Survey and Construction, Durban 4041 (South Africa)

2011-01-15T23:59:59.000Z

52

INITIAL SELECTION OF SUPPLEMENTAL TREATMENT TECHNOLOGIES FOR HANFORDS LOW ACTIVITY TANK WASTE  

SciTech Connect

In 2002, the U.S. Department of Energy (DOE) documented a plan for accelerating cleanup of the Hanford Site, located in southeastern Washington State, by at least 35 years. A key element of the plan was acceleration of the tank waste program and completion of ''tank waste treatment by 2028 by increasing the capacity of the planned Waste Treatment Plant (WTP) and using supplemental technologies for waste treatment and immobilization.'' The plan identified specific technologies to be evaluated for supplemental treatment of as much as 70% of the low-activity waste (LAW). In concert with this acceleration plan, DOE, the U.S. Environmental Protection Agency, and the Washington State Department of Ecology proposed to accelerate--from 2014 to 2006--the Hanford Federal Facility Agreement and Consent Order milestone (M-62-11) associated with a final decision on the balance of tank waste that is beyond the capacity of the WTP. The DOE Office of River Protection tank farm contractor, CH2M HILL Hanford Group, Inc. (CH2M HILL), was tasked with testing and evaluating selected supplemental technologies to support final decisions on tank waste treatment. Three technologies and corresponding vendors were selected to support an initial technology selection in 2003. The three technologies were containerized grout called cast stone (Fluor Federal Services); bulk vitrification (AMEC Earth and Environmental, Inc.); and steam reforming (THOR Treatment Technologies, LLC.). The cast stone process applies an effective grout waste formulation to the LAW and places the cement-based product in a large container for solidification and disposal. Unlike the WTP LAW treatment, which applies vitrification within continuous-fed joule-heated ceramic melters, bulk vitrification produces a glass waste form using batch melting within the disposal container. Steam reforming produces a granular denitrified mineral waste form using a high-temperature fluidized bed process. An initial supplemental technology selection was completed in December 2003, enabling DOE and CH2M HILL to focus investments in 2004 on the testing and production-scale demonstrations needed to support the 2006 milestone.

RAYMOND, R.E.

2004-02-20T23:59:59.000Z

53

Chapter 19 - Nuclear Waste Fund  

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

Nuclear Waste Fund 19-1 Nuclear Waste Fund 19-1 CHAPTER 19 NUCLEAR WASTE FUND 1. INTRODUCTION. a. Purpose. This chapter establishes the financial, accounting, and budget policies and procedures for civilian and defense nuclear waste activities, as authorized in Public Law 97-425, the Nuclear Waste Policy Act, as amended, referred to hereafter as the Act. b. Applicability. This chapter applies to all Departmental elements, including the National Nuclear Security Administration, and activities that are funded by the Nuclear Waste Fund (NWF) or the Defense Nuclear Waste Disposal appropriation. c. Background. The Act established the Office of Civilian Radioactive Waste Management (OCRWM) and assigned it responsibility for the management

54

Independent Oversight Activity Report, Hanford Waste Treatment...  

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

(VSL). Bechtel National, Inc. (BNI) is the contractor responsible for the design and construction of the Hanford Site Waste Treatment and Immobilization Plant (WTP) for the...

55

Integrated electronic waste management in Mexico : law, technology and public policy  

E-Print Network (OSTI)

What is electronic waste? Why is it considered a problem? What are the public health implications of its mishandling? The electronic industry, a sector that has experienced one of the highest growth rates of the last decade, ...

Gonzalez Llera, Ricardo, 1971-

2004-01-01T23:59:59.000Z

56

Independent Activity Report, Waste Isolation Pilot Plant - September 2011 |  

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

Waste Isolation Pilot Plant - Waste Isolation Pilot Plant - September 2011 Independent Activity Report, Waste Isolation Pilot Plant - September 2011 September 2011 Orientation Visit to the Waste Isolation Pilot Plant [HIAR-WIPP-2011-09-07] The U.S. Department of Energy (DOE) Office of Enforcement and Oversight, within the Office of Health, Safety and Security (HSS), conducted an orientation visit to the DOE Carlsbad Field Office (CBFO) and the nuclear facility at the Waste Isolation Pilot Plant (WIPP) at Carlsbad, NM, on September 7, 2011. The purpose of the visit was to discuss the nuclear safety oversight strategy, describe the site lead program, increase HSS personnel's operational awareness of the site's activities, and identify specific activities that HSS can perform to carry out its

57

Activity Report for Hanford WTP LAW Melter HA Development, July...  

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

(LMP) system. The primary purpose of this HSS field activity, conducted from July 31 to August 5, 2013, was to observe and understand the evolving approach used by Bechtel...

58

Independent Activity Report, Office of River Protection Waste Treatment  

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

Office of River Protection Waste Office of River Protection Waste Treatment Plant and Tank Farms - February 2013 Independent Activity Report, Office of River Protection Waste Treatment Plant and Tank Farms - February 2013 February 2013 Site Familiarization and Introduction of New Office of Safety and Emergency Management Evaluations Site Lead for the Office of River Protection Waste Treatment Plant and Tank Farms [HIAR-HANFORD-2013-02-25] The Office of Health, Safety and Security's (HSS) Office of Safety and Emergency Management Evaluations (HS-45) assigned a new Site Lead to provide continuous oversight of activities at the Office of River Protection (ORP) Waste Treatment Plant (WTP) and tank farms. To gain familiarity with the site programs and personnel, the new Site Lead made two trips to the site, which included tours of the WTP construction site

59

Independent Oversight Activity Report, Savannah River Site Waste  

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

Independent Oversight Activity Report, Savannah River Site Waste Independent Oversight Activity Report, Savannah River Site Waste Solidification Building Independent Oversight Activity Report, Savannah River Site Waste Solidification Building May 2013 Savannah River Site Waste Solidification Building Corrective Actions from the January 2013 Report on Construction Quality of Mechanical Systems Installation and Fire Protection Design [HIAR SRS-2013-5-07] Activity Description/Purpose: Review the corrective actions being implemented by the construction contractor to address Findings 1-4, 6, and 9 from a construction quality review performed by the Office of Health, Safety and Security (HSS) (Reference 1). Meet with the SRS WSB project staff and Savannah River Nuclear Solutions (SRNS) engineers to discuss the proposed corrective actions

60

R D activities at DOE applicable to mixed waste  

SciTech Connect

The Department of Energy (DOE) has established the Office of Environmental Restoration and Waste Management. Within the new organization, the Office of Technology Development (OTD) is responsible for research, development, demonstration, testing and evaluation (RDDT E) activities aimed at meeting DOE cleanup goals, while minimizing cost and risk. Because of US governmental activities dating back to the Manhattan project, mixed radioactive and hazardous waste is an area of particular concern to DOE. The OTD is responsible for a number of R D activities aimed at improving capabilities to characterize, control, and properly dispose of mixed waste. These activities and their progress to date will be reviewed. In addition, needs for additional R D on managing mixed waste will be presented. 5 refs., 2 tabs.

Erickson, M.D.; Devgun, J.S.; Brown, J.J.; Beskid, N.J.

1991-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "activity waste law" 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

Summary - System Planning for Low-Activity Waste Treatment at...  

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

(DOE-EM) External Technical Review of System Planning for Low-Activity Waste Treatment at Hanford Why DOE-EM Did This Review Construction of the facilities of the Hanford site's...

62

Reportable Nuclide Criteria for ORNL Waste Management Activities - 13005  

SciTech Connect

The U.S. Department of Energy's Oak Ridge National Laboratory (ORNL) in Oak Ridge, Tennessee generates numerous radioactive waste streams. Many of those streams contain a large number of radionuclides with an extremely broad range of concentrations. To feasibly manage the radionuclide information, ORNL developed a reportable nuclide criteria to distinguish between those nuclides in a waste stream that require waste tracking versus those nuclides of such minimal activity that do not require tracking. The criteria include tracking thresholds drawn from ORNL onsite management requirements, transportation requirements, and relevant treatment and disposal facility acceptance criteria. As a management practice, ORNL maintains waste tracking on a nuclide in a specific waste stream if it exceeds any of the reportable nuclide criteria. Nuclides in a specific waste stream that screen out as non-reportable under all these criteria may be dropped from ORNL waste tracking. The benefit of this criteria is to ensure that nuclides in a waste stream with activities which meaningfully affect safety and compliance are tracked, while documenting the basis for removing certain isotopes from further consideration.

McDowell, Kip [ORNL; Forrester, Tim [ORNL; Saunders, Mark Edward [ORNL

2013-01-01T23:59:59.000Z

63

Secondary Waste Cast Stone Waste Form Qualification Testing Plan  

SciTech Connect

The Hanford Tank Waste Treatment and Immobilization Plant (WTP) is being constructed to treat the 56 million gallons of radioactive waste stored in 177 underground tanks at the Hanford Site. The WTP includes a pretreatment facility to separate the wastes into high-level waste (HLW) and low-activity waste (LAW) fractions for vitrification and disposal. The LAW will be converted to glass for final disposal at the Integrated Disposal Facility (IDF). Cast Stone – a cementitious waste form, has been selected for solidification of this secondary waste stream after treatment in the ETF. The secondary-waste Cast Stone waste form must be acceptable for disposal in the IDF. This secondary waste Cast Stone waste form qualification testing plan outlines the testing of the waste form and immobilization process to demonstrate that the Cast Stone waste form can comply with the disposal requirements. Specifications for the secondary-waste Cast Stone waste form have not been established. For this testing plan, Cast Stone specifications are derived from specifications for the immobilized LAW glass in the WTP contract, the waste acceptance criteria for the IDF, and the waste acceptance criteria in the IDF Permit issued by the State of Washington. This testing plan outlines the testing needed to demonstrate that the waste form can comply with these waste form specifications and acceptance criteria. The testing program must also demonstrate that the immobilization process can be controlled to consistently provide an acceptable waste form product. This testing plan also outlines the testing needed to provide the technical basis for understanding the long-term performance of the waste form in the disposal environment. These waste form performance data are needed to support performance assessment analyses of the long-term environmental impact of the secondary-waste Cast Stone waste form in the IDF

Westsik, Joseph H.; Serne, R. Jeffrey

2012-09-26T23:59:59.000Z

64

On the Group-Velocity Property for Wave-Activity Conservation Laws  

Science Conference Proceedings (OSTI)

The density and the flux of wave-activity conservation laws are generally required to satisfy the group-velocity property: under the WKB approximation (i.e., for nearly monochromatic small-amplitude waves in a slowly varying medium), the flux ...

J. Vanneste; T. G. Shepherd

1998-03-01T23:59:59.000Z

65

Independent Oversight Activity Report, Savannah River Site Waste  

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

Savannah River Site Waste Savannah River Site Waste Solidification Building Independent Oversight Activity Report, Savannah River Site Waste Solidification Building May 2013 Savannah River Site Waste Solidification Building Corrective Actions from the January 2013 Report on Construction Quality of Mechanical Systems Installation and Fire Protection Design [HIAR SRS-2013-5-07] Activity Description/Purpose: Review the corrective actions being implemented by the construction contractor to address Findings 1-4, 6, and 9 from a construction quality review performed by the Office of Health, Safety and Security (HSS) (Reference 1). Meet with the SRS WSB project staff and Savannah River Nuclear Solutions (SRNS) engineers to discuss the proposed corrective actions discussed in Reference 2, and clarify additional reviews to be performed by

66

Phase 1 immobilized low-activity waste operational source term  

SciTech Connect

This report presents an engineering analysis of the Phase 1 privatization feeds to establish an operational source term for storage and disposal of immobilized low-activity waste packages at the Hanford Site. The source term information is needed to establish a preliminary estimate of the numbers of remote-handled and contact-handled waste packages. A discussion of the uncertainties and their impact on the source term and waste package distribution is also presented. It should be noted that this study is concerned with operational impacts only. Source terms used for accident scenarios would differ due to alpha and beta radiation which were not significant in this study.

Burbank, D.A.

1998-03-06T23:59:59.000Z

67

RADIOACTIVE DEMONSTRATION OF MINERALIZED WASTE FORMS MADE FROM HANFORD LOW ACTIVITY WASTE (TANK FARM BLEND) BY FLUIDIZED BED STEAM REFORMATION (FBSR)  

SciTech Connect

The U.S. Department of Energy’s Office of River Protection (ORP) is responsible for the retrieval, treatment, immobilization, and disposal of Hanford’s tank waste. A key aspect of the River Protection Project (RPP) cleanup mission is to construct and operate the Hanford Tank Waste Treatment and Immobilization Plant (WTP). The WTP will separate the tank waste into high-level and low-activity waste (LAW) fractions, both of which will subsequently be vitrified. The projected throughput capacity of the WTP LAW Vitrification Facility is insufficient to complete the RPP mission in the time frame required by the Hanford Federal Facility Agreement and Consent Order, also known as the Tri-Party Agreement (TPA), i.e. December 31, 2047. Supplemental Treatment is likely to be required both to meet the TPA treatment requirements as well as to more cost effectively complete the tank waste treatment mission. The Supplemental Treatment chosen will immobilize that portion of the retrieved LAW that is not sent to the WTP’s LAW Vitrification facility into a solidified waste form. The solidified waste will then be disposed on the Hanford site in the Integrated Disposal Facility (IDF). Fluidized Bed Steam Reforming (FBSR) offers a moderate temperature (700-750°C) continuous method by which LAW can be processed irrespective of whether the waste contain organics, nitrates, sulfates/sulfides, chlorides, fluorides, volatile radionuclides or other aqueous components. The FBSR technology can process these wastes into a crystalline ceramic (mineral) waste form. The mineral waste form that is produced by co-processing waste with kaolin clay in an FBSR process has been shown to be comparable to LAW glass, i.e. leaches Tc-99, Re and Na at <2g/m2 during ASTM C1285 (Product Consistency) durability testing. Monolithing of the granular FBSR product was investigated to prevent dispersion during transport or burial/storage. Monolithing in an inorganic geopolymer binder, which is amorphous, macro-encapsulates the granules, and the monoliths pass ANSI/ANS 16.1 and ASTM C1308 durability testing with Re achieving a Leach Index (LI) of 9 (the Hanford Integrated Disposal Facility, IDF, criteria for Tc-99) after a few days and Na achieving an LI of >6 (the Hanford IDF criteria for Na) in the first few hours. The granular and monolithic waste forms also pass the EPA Toxicity Characteristic Leaching Procedure (TCLP) for all Resource Conservation and Recovery Act (RCRA) components at the Universal Treatment Standards (UTS). Two identical Benchscale Steam Reformers (BSR) were designed and constructed at SRNL, one to treat non-radioactive simulants and the other to treat actual radioactive wastes. The results from the non-radioactive BSR were used to determine the parameters needed to operate the radioactive BSR in order to confirm the findings of non-radioactive FBSR pilot scale and engineering scale tests and to qualify an FBSR LAW waste form for applications at Hanford. Radioactive testing commenced using SRS LAW from Tank 50 chemically trimmed to look like Hanford’s blended LAW known as the Rassat simulant as this simulant composition had been tested in the non-radioactive BSR, the non-radioactive pilot scale FBSR at the Science Applications International Corporation-Science and Technology Applications Research (SAIC-STAR) facility in Idaho Falls, ID and in the TTT Engineering Scale Technology Demonstration (ESTD) at Hazen Research Inc. (HRI) in Denver, CO. This provided a “tie back” between radioactive BSR testing and non-radioactive BSR, pilot scale, and engineering scale testing. Approximately six hundred grams of non-radioactive and radioactive BSR product were made for extensive testing and comparison to the non-radioactive pilot scale tests performed in 2004 at SAIC-STAR and the engineering scale test performed in 2008 at HRI with the Rassat simulant. The same mineral phases and off-gas species were found in the radioactive and non-radioactive testing. The granular ESTD and BSR products (radioactive and non-radioactive) were analyzed for to

Jantzen, C. M.; Crawford, C. L.; Bannochie, C. J.; Burket, P. R.; Cozzi, A. D.; Daniel, W. E.; Hall, H. K.; Miller, D. H.; Missimer, D. M.; Nash, C. A.; Williams, M. F.

2013-08-21T23:59:59.000Z

68

Hanford immobilized low-activity tank waste performance assessment  

Science Conference Proceedings (OSTI)

The Hanford Immobilized Low-Activity Tank Waste Performance Assessment examines the long-term environmental and human health effects associated with the planned disposal of the vitrified low-level fraction of waste presently contained in Hanford Site tanks. The tank waste is the by-product of separating special nuclear materials from irradiated nuclear fuels over the past 50 years. This waste has been stored in underground single and double-shell tanks. The tank waste is to be retrieved, separated into low and high-activity fractions, and then immobilized by private vendors. The US Department of Energy (DOE) will receive the vitrified waste from private vendors and plans to dispose of the low-activity fraction in the Hanford Site 200 East Area. The high-level fraction will be stored at Hanford until a national repository is approved. This report provides the site-specific long-term environmental information needed by the DOE to issue a Disposal Authorization Statement that would allow the modification of the four existing concrete disposal vaults to provide better access for emplacement of the immobilized low-activity waste (ILAW) containers; filling of the modified vaults with the approximately 5,000 ILAW containers and filler material with the intent to dispose of the containers; construction of the first set of next-generation disposal facilities. The performance assessment activity will continue beyond this assessment. The activity will collect additional data on the geotechnical features of the disposal sites, the disposal facility design and construction, and the long-term performance of the waste. Better estimates of long-term performance will be produced and reviewed on a regular basis. Performance assessments supporting closure of filled facilities will be issued seeking approval of those actions necessary to conclude active disposal facility operations. This report also analyzes the long-term performance of the currently planned disposal system as a basis to set requirements on the waste form and the facility design that will protect the long-term public health and safety and protect the environment.

Mann, F.M.

1998-03-26T23:59:59.000Z

69

Independent Oversight Activity Report, Hanford Waste Treatment and  

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

November 2013 November 2013 Independent Oversight Activity Report, Hanford Waste Treatment and Immobilization Plant - November 2013 December 2013 Catholic University of America Vitreous State Laboratory Tour and Discussion of Experiments Conducted in Support of Hanford Site Waste Treatment and Immobilization Plant Select Systems Design [HIAR-VSL-2013-11-18] This Independent Activity Report documents an oversight activity conducted by the Office of Health, Safety and Security's (HSS) Office of Safety and Emergency Management Evaluations on November 18, 2013, at the Catholic University of America Vitreous State Laboratory (VSL). Bechtel National, Inc. (BNI) is the contractor responsible for the design and construction of the Hanford Site Waste Treatment and Immobilization Plant (WTP) for the

70

Waste management plan for Hanford spent nuclear fuel characterization activities  

SciTech Connect

A joint project was initiated between Westinghouse Hanford Company (WHC) and Pacific Northwest Laboratory (PNL) to address critical issues associated with the Spent Nuclear Fuel (SNF) stored at the Hanford Site. Recently, particular attention has been given to remediation of the SNF stored in the K Basins. A waste management plan (WMP) acceptable to both parties is required prior to the movement of selected material to the PNL facilities for examination. N Reactor and Single Pass Reactor (SPR) fuel has been stored for an extended period of time in the N Reactor, PUREX, K-East, and K-West Basins. Characterization plans call for transport of fuel material form the K Basins to the 327 Building Postirradiation Testing Laboratory (PTL) in the 300 Area for examination. However, PNL received a directive stating that no examination work will be started in PNL hot cell laboratories without an approved disposal route for all waste generated related to the activity. Thus, as part of the Characterization Program Management Plan for Hanford Spent Nuclear Fuel, a waste management plan which will ensure that wastes generated as a result of characterization activities conducted at PNL will be accepted by WHC for disposition is required. This document contains the details of the waste handling plan that utilizes, to the greatest extent possible, established waste handling and disposal practices at Hanford between PNL and WHC. Standard practices are sufficient to provides for disposal of most of the waste materials, however, special consideration must be given to the remnants of spent nuclear fuel elements following examination. Fuel element remnants will be repackaged in an acceptable container such as the single element canister and returned to the K Basins for storage.

Chastain, S.A. [Westinghouse Hanford Co., Richland, WA (United States); Spinks, R.L. [Pacific Northwest Lab., Richland, WA (United States)

1994-10-17T23:59:59.000Z

71

Disposal Activities and the Unique Waste Streams at the Nevada National Security Site (NNSS)  

SciTech Connect

This slide show documents waste disposal at the Nevada National Security Site. Topics covered include: radionuclide requirements for waste disposal; approved performance assessment (PA) for depleted uranium disposal; requirements; program approval; the Waste Acceptance Review Panel (WARP); description of the Radioactive Waste Acceptance Program (RWAP); facility evaluation; recent program accomplishments, nuclear facility safety changes; higher-activity waste stream disposal; large volume bulk waste streams.

Arnold, P.

2012-10-31T23:59:59.000Z

72

Biomass Support for the China Renewable Energy Law: Feasibility Report -- Agricultural and Forestry Solid Wastes Power Generation Demonstration, December 2005  

DOE Green Energy (OSTI)

Subcontractor report on feasibility of using agricultural and forestry wastes for power generation in China

Not Available

2006-10-01T23:59:59.000Z

73

How Does Law Matter to Social Movements? A Case Study of Gay Activism in Singapore  

E-Print Network (OSTI)

David M. 1998. “How Does Law Matter in the Constitution ofG. , and Austin Sarat. 1998. How Does Law Matter? Evanston:Chicago Press. ------ 1998. “How Does Law Matter for Social

Chua, Lynette Janice

2011-01-01T23:59:59.000Z

74

TWRS Retrieval and Storage Mission and Immobilized Low Activity Waste (ILAW) Disposal Plan  

Science Conference Proceedings (OSTI)

This project plan has a twofold purpose. First, it provides a waste stream project plan specific to the River Protection Project (RPP) (formerly the Tank Waste Remediation System [TWRS] Project) Immobilized Low-Activity Waste (LAW) Disposal Subproject for the Washington State Department of Ecology (Ecology) that meets the requirements of Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Milestone M-90-01 (Ecology et al. 1994) and is consistent with the project plan content guidelines found in Section 11.5 of the Tri-Party Agreement action plan (Ecology et al. 1998). Second, it provides an upper tier document that can be used as the basis for future subproject line-item construction management plans. The planning elements for the construction management plans are derived from applicable U.S. Department of Energy (DOE) planning guidance documents (DOE Orders 4700.1 [DOE 1992] and 430.1 [DOE 1995a]). The format and content of this project plan are designed to accommodate the requirements mentioned by the Tri-Party Agreement and the DOE orders. A cross-check matrix is provided in Appendix A to explain where in the plan project planning elements required by Section 11.5 of the Tri-Party Agreement are addressed.

BURBANK, D.A.

1999-09-01T23:59:59.000Z

75

Effects of Globally Waste Disturbing Activities on Gas Generation, Retention, and Release in Hanford Waste Tanks  

SciTech Connect

Various operations are authorized in Hanford single- and double-shell tanks that disturb all or a large fraction of the waste. These globally waste-disturbing activities have the potential to release a large fraction of the retained flammable gas and to affect future gas generation, retention, and release behavior. This report presents analyses of the expected flammable gas release mechanisms and the potential release rates and volumes resulting from these activities. The background of the flammable gas safety issue at Hanford is summarized, as is the current understanding of gas generation, retention, and release phenomena. Considerations for gas monitoring and assessment of the potential for changes in tank classification and steady-state flammability are given.

Stewart, Charles W.; Fountain, Matthew S.; Huckaby, James L.; Mahoney, Lenna A.; Meyer, Perry A.; Wells, Beric E.

2005-08-02T23:59:59.000Z

76

Briefing book on environmental and waste management activities  

Science Conference Proceedings (OSTI)

The purpose of the Briefing Book is to provide current information on Environmental Restoration and Waste Management Activities at the Hanford Site. Each edition updates the information in the previous edition by deleting those sections determined not to be of current interest and adding new topics to keep up to date with the changing requirements and issues. This edition covers the period from October 15, 1992 through April 15, 1993.

Quayle, T.A.

1993-04-01T23:59:59.000Z

77

Baseline LAW Glass Formulation Testing  

Science Conference Proceedings (OSTI)

The major objective of the baseline glass formulation work was to develop and select glass formulations that are compliant with contractual and processing requirements for each of the LAW waste streams. Other objectives of the work included preparation and characterization of glasses with respect to the properties of interest, optimization of sulfate loading in the glasses, evaluation of ability to achieve waste loading limits, testing to demonstrate compatibility of glass melts with melter materials of construction, development of glass formulations to support ILAW qualification activities, and identification of glass formulation issues with respect to contract specifications and processing requirements.

Kruger, Albert A. [USDOE Office of River Protection, Richland, WA (United States); Mooers, Cavin [The Catholic University of America, Washington, DC (United States). Vitreous State Lab.; Bazemore, Gina [The Catholic University of America, Washington, DC (United States). Vitreous State Lab; Pegg, Ian L. [The Catholic University of America, Washington, DC (United States). Vitreous State Lab; Hight, Kenneth [The Catholic University of America, Washington, DC (United States). Vitreous State Lab; Lai, Shan Tao [The Catholic University of America, Washington, DC (United States). Vitreous State Lab; Buechele, Andrew [The Catholic University of America, Washington, DC (United States). Vitreous State Lab; Rielley, Elizabeth [The Catholic University of America, Washington, DC (United States). Vitreous State Lab; Gan, Hao [The Catholic University of America, Washington, DC (United States). Vitreous State Lab; Muller, Isabelle S. [The Catholic University of America, Washington, DC (United States). Vitreous State Lab; Cecil, Richard [The Catholic University of America, Washington, DC (United States). Vitreous State Lab

2013-06-13T23:59:59.000Z

78

DOE site performance assessment activities. Radioactive Waste Technical Support Program  

Science Conference Proceedings (OSTI)

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

Not Available

1990-07-01T23:59:59.000Z

79

Design requirements document for project W-465, immobilized low activity waste interim storage  

SciTech Connect

The scope of this design requirements document is to identify the functions and associated requirements that must be performed to accept, transport, handle, and store immobilized low-activity waste produced by the privatized Tank Waste Remediation System treatment contractors. The functional and performance requirements in this document provide the basis for the conceptual design of the Tank Waste Remediation System Immobilized low-activity waste interim storage facility project and provides traceability from the program level requirements to the project design activity.

Burbank, D.A.

1997-01-27T23:59:59.000Z

80

A Generic Technical Basis for Implementing a Very Low Level Waste Category for Disposal of Low Activity Radioactive Wastes  

Science Conference Proceedings (OSTI)

The International Atomic Energy Agency (IAEA) has recognized Very Low Level Waste (VLLW) as a category that provides both practical and economic benefits. Implementation of VLLW in the international community has been successfully demonstrated in France and Spain, as described in EPRI report 1024844, Basis for National and International Low Activity and Very Low Level Waste (VLLW) Disposal Classifications. This report presents the technical basis for a waste category of Very Low Level ...

2013-12-23T23:59:59.000Z

Note: This page contains sample records for the topic "activity waste law" 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

1991 annual report on low-level radioactive waste management progress. Report to Congress in response to Public Law 99-240  

Science Conference Proceedings (OSTI)

This report summarizes the progress during 1991 of States and compact regions in establishing new low-level radioactive waste disposal capacity. It has been prepared in response to requirements in Section 7 (b) of Title I of Public Law 99-240, the Low-Level Radioactive Waste Policy Amendments Act of 1985 (the Act). By the end of 1991, 9 compact regions (totaling 42 States) were functioning with plans to establish low-level radioactive waste disposal facilities: Appalachian, Central, Central Midwest, Midwest, Northeast, Northwest, Rocky Mountain, Southeast, and Southwestern. Also planning to construct disposal facilities, but unaffiliated with a compact region, are Maine, Massachusetts, New York, Texas, and Vermont. The District of Columbia, New Hampshire, Puerto Rico, Rhode Island and Michigan are unaffiliated with a compact region and do not plan to construct a disposal facility. Michigan was the host State for the Midwest compact region until July 1991 when the Midwest Interstate Compact Commission revoked Michigan`s membership. Only the Central, Central Midwest, and Southwestern compact regions met the January 1, 1992, milestone in the Act to submit a complete disposal license application. None of the States or compact regions project meeting the January 1, 1993, milestone to have an operational low-level radioactive waste disposal facility. Also summarized are significant events that occurred in low-level radioactive waste management in 1991 and early 1992, including the 1992 United States Supreme Court decision in New York v. United States in which New York challenged the constitutionality of the Act, particularly the ``take-title`` provision. Summary information is also provided on the volume of low-level radioactive waste received for disposal in 1991 by commercially operated low-level radioactive waste disposal facilities.

Not Available

1992-11-01T23:59:59.000Z

82

Impacts of Feed Composition and Recycle on Hanford Low-Activity Waste Glass Mass  

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

Feed Composition Feed Composition and Recycle on Hanford Low- Activity Waste Glass Mass J.D. Vienna & D.S. Kim - Pacific Northwest National Laboratory I.L. Pegg - Catholic University of America 1 LAW Glass Loading Limits WTP baseline (LAW Glass Formulation Algorithm) low uncertainty  thoroughly tested accounts for Na, S, Cl, F, Cr, K, and P impacts conservative loading Advanced silicate formulation higher uncertainty than baseline currently accounts for Na and S impacts impacts of other components not specifically tested, but, one can evaluate maxima from testing as a lower bound 2 0 5 10 15 20 25 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 SO 3 (target) wt% in Glass Na 2 O (target) wt% in Glass SO 3 ≤ 0.77 wt% Na 2 O ≤ 35.875 - 42.5*SO 3 (in wt%) Na 2 O ≤ 21 wt% Na 2 O + 0.66*K

83

Technetium Retention During LAW Vitrification  

• Technetium in Hanford tank waste is a significant risk contributor in performance assessments for low activity waste disposal

84

Conceptual design statement of work for the immobilized low-activity waste interim storage facility project  

SciTech Connect

The Immobilized Low-Activity Waste Interim Storage subproject will provide storage capacity for immobilized low-activity waste product sold to the U.S. Department of Energy by the privatization contractor. This statement of work describes the work scope (encompassing definition of new installations and retrofit modifications to four existing grout vaults), to be performed by the Architect-Engineer, in preparation of a conceptual design for the Immobilized Low-Activity Waste Interim Storage Facility.

Carlson, T.A., Fluor Daniel Hanford

1997-02-06T23:59:59.000Z

85

Tank Waste Corporate Board Meeting 11/18/10 | Department of Energy  

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

Tank Waste Corporate Board Meeting 11/18/10 Tank Waste Corporate Board Meeting 11/18/10 Tank Waste Corporate Board Meeting 11/18/10 The following documents are associated with the Tank Waste Corporate Board Meeting held on November 18th, 2010. High-Level Waste Corporate Board Meeting Agenda Journey to Excellence Goal 2 and Enhanced Tank Waste Strategy Introduction to Tc/I in Hanford Flowsheet Fate of Tc99 at WTP and Current Work on Capture Technetium Retention During LAW Vitrification Impacts of Feed Composition and Recycle on Hanford Low-Activity Waste Glass Mass Secondary Waste Forms and Technetium Management Hanford Low Activity Waste (LAW) Fluidized Bed Steam Reformer (FBSR) Na-Al-Si (NAS) Waste Form Qualification Salt Waste Processing Initiatives Recap and Conclusions to Tc/I in Hanford Flowsheet Presentations

86

MINERALIZING, STEAM REFORMING TREATMENT OF HANFORD LOW-ACTIVITY WASTE (a.k.a. INEEL/EXT-05-02526)  

SciTech Connect

The U.S. Department of Energy (DOE) documented, in 2002, a plan for accelerating cleanup of the Hanford Site, located in southeastern Washington State, by at least 35 years. A key element of the plan was acceleration of the tank waste program and completion of ''tank waste treatment by 2028 by increasing the capacity of the planned Waste Treatment Plant (WTP) and using supplemental technologies for waste treatment and immobilization.'' The plan identified steam reforming technology as a candidate for supplemental treatment of as much as 70% of the low-activity waste (LAW). Mineralizing steam reforming technology, offered by THOR Treatment Technologies, LLC would produce a denitrated, granular mineral waste form using a high-temperature fluidized bed process. A pilot scale demonstration of the technology was completed in a 15-cm-diameter reactor vessel. The pilot scale facility was equipped with a cyclone separator and heated sintered metal filters for particulate removal, a thermal oxidizer for reduced gas species and NOx destruction, and a packed activated carbon bed for residual volatile species capture. The pilot scale equipment is owned by the DOE, but located at the Science and Technology Applications Research (STAR) Center in Idaho Falls, ID. Pilot scale testing was performed August 2–5, 2004. Flowsheet chemistry and operational parameters were defined through a collaborative effort involving Idaho National Engineering and Environmental Laboratory (INEEL), Savannah River National Laboratory (SRNL), and THOR Treatment Technologies personnel. Science Application International Corporation, owners of the STAR Center, personnel performed actual pilot scale operation. The pilot scale test achieved a total of 68.4 hours of cumulative/continuous processing operation before termination in response to a bed de-fluidization condition. 178 kg of LAW surrogate were processed that resulted in 148 kg of solid product, a mass reduction of about 17%. The process achieved essentially complete bed turnover within approximately 40 hours. Samples of mineralized solid product materials were analyzed for chemical/physical properties. SRNL will report separately the results of product performance testing that were accomplished.

A. L. Olson; N. R. Soelberg; D. W. Marshall; G. L. Anderson

2005-02-01T23:59:59.000Z

87

Evidence for departure from a power-law flare size distribution for a small solar active region  

E-Print Network (OSTI)

Active region 11029 was a small, highly flare-productive solar active region observed at a time of extremely low solar activity. The region produced only small flares: the largest of the $>70$ Geostationary Observational Environmental Satellite (GOES) events for the region has a peak 1--$8{\\AA}$ flux of $2.2\\times 10^{-6} {\\rm W} {\\rm m}^{-2}$ (GOES C2.2). The background-subtracted GOES peak-flux distribution suggests departure from power-law behavior above $10^{-6} {\\rm W} {\\rm m}^{-2}$, and a Bayesian model comparison strongly favors a power-law plus rollover model for the distribution over a simple power-law model. The departure from the power law is attributed to this small active region having a finite amount of energy. The rate of flaring in the region varies with time, becoming very high for two days coinciding with the onset of an increase in complexity of the photospheric magnetic field. The observed waiting-time distribution for events is consistent with a piecewise-constant Poisson model. These res...

Wheatland, M S

2010-01-01T23:59:59.000Z

88

Review of the Hanford Site Waste Treatment and Immobilization...  

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

U.S. Department of Energy DOE-WTP ORP WTP Project Office HLW High-Level Waste Facility HVAC Heating, Ventilation, and Air Conditioning LAB Analytical Laboratory LAW Low-Activity...

89

System Planning for Low-Activity Waste at Hanford  

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

Technical Review of System Planning Technical Review of System Planning for Low-Activity Waste Treatment at Hanford November 2008 Dr. David S. Kosson, Vanderbilt University Dr. David R. Gallay, Logistics Management Institute Dr. Ian L. Pegg, The Catholic University of America Dr. Ray G. Wymer, Oak Ridge National Laboratory (ret.) Dr. Steven Krahn, U. S. Department of Energy ii ACKNOWLEDGEMENT The Review Team thanks Mr. Ben Harp, Office of River Protection (ORP), and Mr. James Honeyman, CH2M HILL, for their exceptional support during this review. Mr. Harp was the lead Department of Energy (DOE) representative responsible for organizing reviews held on-site by the Review Team. Mr. Honeyman, and his staff, provided responsive support through technical presentations, telephone conferences, and numerous reference documents.

90

Design requirements document for project W-520, immobilized low-activity waste disposal  

SciTech Connect

This design requirements document (DRD) identifies the functions that must be performed to accept, handle, and dispose of the immobilized low-activity waste (ILAW) produced by the Tank Waste Remediation System (TWRS) private treatment contractors and close the facility. It identifies the requirements that are associated with those functions and that must be met. The functional and performance requirements in this document provide the basis for the conceptual design of the Tank Waste Remediation System Immobilized Low-Activity Waste disposal facility project (W-520) and provides traceability from the program-level requirements to the project design activity.

Ashworth, S.C.

1998-08-06T23:59:59.000Z

91

Review of the Hanford Site Waste Treatment and Immobilization Plant Low Activity Waste Melter Process System Hazards Analysis Activity, December 2012  

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

the Hanford Site the Hanford Site Waste Treatment and Immobilization Plant Low Activity Waste Melter Process System Hazards Analysis Activity December 2012 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Table of Contents 1.0 Purpose ................................................................................................................................................. 1 2.0 Background.......................................................................................................................................... 1 3.0 Scope and Methodology... ................................................................................................................... 1

92

Review of the Hanford Site Waste Treatment and Immobilization Plant Low Activity Waste Melter Process System Hazards Analysis Activity, December 2012  

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

the Hanford Site the Hanford Site Waste Treatment and Immobilization Plant Low Activity Waste Melter Process System Hazards Analysis Activity December 2012 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Table of Contents 1.0 Purpose ................................................................................................................................................. 1 2.0 Background.......................................................................................................................................... 1 3.0 Scope and Methodology... ................................................................................................................... 1

93

Technical basis for classification of low-activity waste fraction from Hanford site tanks  

SciTech Connect

The overall objective of this report is to provide a technical basis to support a U.S. Nuclear Regulatory Commission determination to classify the low-activity waste from the Hanford Site single-shell and double-shell tanks as `incidental` wastes after removal of additional radionuclides and immobilization.The proposed processing method, in addition to the previous radionuclide removal efforts, will remove the largest practical amount of total site radioactivity, attributable to high-level waste, for disposal is a deep geologic repository. The remainder of the waste would be considered `incidental` waste and could be disposed onsite.

Petersen, C.A.

1996-09-20T23:59:59.000Z

94

Nonhazardous Solid Waste Management Regulations & Criteria (Mississippi)  

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

The purpose of the Nonhazardous Solid Waste Management Regulations & Criteria is to establish a minimum State Criteria under the Mississippi Solid Waste Law for all solid waste management...

95

FLUIDIZED BED STEAM REFORMING FOR TREATMENT AND IMMOBILIZATION OF LOW-ACTIVITY WASTE  

SciTech Connect

This report is one of four reports written to provide background information regarding immobilization technologies remaining under consideration for supplemental immobilization of Hanford's low-activity waste. This paper provides the reader a general understanding of fluidized bed steam reforming and its possible application to treat and immobilize Hanford low-activity waste.

HEWITT WM

2011-04-08T23:59:59.000Z

96

BULK VITRIFICATION TECHNOLOGY FOR THE TREATMENT AND IMMOBILIZATION OF LOW-ACTIVITY WASTE  

SciTech Connect

This report is one of four reports written to provide background information regarding immobilization technologies under consideration for supplemental immobilization of Hanford's low-activity waste. This paper is intended to provide the reader with general understanding of Bulk Vitrification and how it might be applied to immobilization of Hanford's low-activity waste.

ARD KE

2011-04-11T23:59:59.000Z

97

A JOULE-HEATED MELTER TECHNOLOGY FOR THE TREATMENT AND IMMOBILIZATION OF LOW-ACTIVITY WASTE  

SciTech Connect

This report is one of four reports written to provide background information regarding immobilization technologies remaining under consideration for supplemental immobilization of Hanford's low-activity waste. This paper provides the reader a general understanding of joule-heated ceramic lined melters and their application to Hanford's low-activity waste.

KELLY SE

2011-04-07T23:59:59.000Z

98

Immobilized low-activity waste interim storage facility, Project W-465 conceptual design report  

SciTech Connect

This report outlines the design and Total Estimated Cost to modify the four unused grout vaults for the remote handling and interim storage of immobilized low-activity waste (ILAW). The grout vault facilities in the 200 East Area of the Hanford Site were constructed in the 1980s to support Tank Waste disposal activities. The facilities were to serve project B-714 which was intended to store grouted low-activity waste. The existing 4 unused grout vaults, with modifications for remote handling capability, will provide sufficient capacity for approximately three years of immobilized low activity waste (ILAW) production from the Tank Waste Remediation System-Privatization Vendors (TWRS-PV). These retrofit modifications to the grout vaults will result in an ILAW interim storage facility (Project W465) that will comply with applicable DOE directives, and state and federal regulations.

Pickett, W.W.

1997-12-30T23:59:59.000Z

99

DESIGN OF THE DEMOSNTRATION BULK VITRIFICATION SYSTEM FOR THE SUPPLEMENTAL TREATMENT OF LOW ACTIVITY TANK WASTE AT HANFORD  

SciTech Connect

In June 2004, the Demonstration Bulk Vitrification System (DBVS) was initiated with the intent to design, construct, and operate a full-scale bulk vitrification pilot-plant to treat low-activity tank waste from Hanford Tank 241-S-109. The DBVS facility uses In-Container Vitrification{trademark} (ICV{trademark}) at the core of the treatment process. The basic process steps combine liquid low-activity waste (LAW) and glassformers; dry the mixture; and then vitrify the mixture in a batch feed-while-melt process in a refractory lined steel container. Off-gases are processed through a state-of-the-art air pollution control system including sintered-metal filtration, thermal oxidation, acid gas scrubbing, and high-efficiency particulate air (HEPA) and high-efficiency gas adsorber (HEGA) filtration. Testing has focused on development and validation of the waste dryer, ICV, and sintered-metal filters (SMFs) equipment, operations enhancements, and glass formulation. With a parallel testing and design process, testing has allowed improvements to the DBVS equipment configuration and operating methodology, since its original inception. Design improvements include optimization of refractory panels in the ICV, simplifying glassformer addition equipment, increasing the number of waste feed chutes to the ICV, and adding capability for remote clean-out of piping, In addition, the U.S. Department of Energy (DOE) has provided an independent review of the entire DBVS process. While the review did not find any fatal flaws, some technical issues were identified that required a re-evaluation of the DBVS design and subsequent changes to the design. A 100 percent design package for the pilot plant will be completed and submitted to DOE for review in early 2008 that incorporates process improvements substantiated through testing and reviews. This paper provides a description of the bulk vitrification process and a discussion of major equipment design changes that have occurred based on full-scale testing over the past two years and DOE reviews.

VAN BEEK JE

2008-02-14T23:59:59.000Z

100

Preliminary Investigation of Sulfur Loading in Hanford LAW Glass  

SciTech Connect

A preliminary estimate was developed for loading limits for high-sulfur low-activity waste (LAW) feeds that will be vitrified into borosilicate glass at the Hanford Site in the waste-cleanup effort. Previous studies reported in the literature were consulted to provide a basis for the estimate. The examination of previous studies led to questions about sulfur loading in Hanford LAW glass, and scoping tests were performed to help answer these questions. These results of these tests indicated that a formulation approach developed by Vienna and colleagues shows promise for maximizing LAW loading in glass. However, there is a clear need for follow-on work. The potential for significantly lowering the amount of LAW glass produced at Hanford (after the initial phase of processing) because of higher sulfur tolerances may outweigh the cost and effort required to perform the necessary testing.

Vienna, John D.; Hrma, Pavel R.; Buchmiller, William C.; Ricklefs, Joel S.

2004-04-01T23:59:59.000Z

Note: This page contains sample records for the topic "activity waste law" 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

Idaho Nuclear Technology and Engineering Center Low-Activity Waste Process Technology Program FY-2000 Status Report  

SciTech Connect

The Low-Activity Waste Process Technology Program anticipated that grouting will be used for disposal of low-level and transuranic wastes generated at the Idaho Nuclear Technology Engineering Center (INTEC). During fiscal year 2000, grout formulations were studied for transuranic waste derived from INTEC liquid sodium-bearing waste and for projected newly generated low-level liquid waste. Additional studies were completed using silica gel and other absorbents to solidify sodium-bearing wastes. A feasibility study and conceptual design were completed for the construction of a grout pilot plant for simulated wastes and demonstration facility for actual wastes.

Herbst, A.K.; McCray, J.A.; Kirkham, R.J.; Pao, J.; Argyle, M.D.; Lauerhass, L.; Bendixsen, C.L.; Hinckley, S.H.

2000-10-31T23:59:59.000Z

102

Idaho Nuclear Technology and Engineering Center Low-Activity Waste Process Technology Program FY-2000 Status Report  

SciTech Connect

The Low-Activity Waste Process Technology Program anticipated that grouting will be used for disposal of low-level and transuranic wastes generated at the Idaho Nuclear Technology Engineering Center (INTEC). During fiscal year 2000, grout formulations were studied for transuranic waste derived from INTEC liquid sodium-bearing waste and for projected newly generated low-level liquid waste. Additional studies were completed using silica gel and other absorbents to solidify sodium-bearing wastes. A feasibility study and conceptual design were completed for the construction of a grout pilot plant for simulated wastes and demonstration facility for actual wastes.

Herbst, Alan Keith; Mc Cray, John Alan; Kirkham, Robert John; Pao, Jenn Hai; Argyle, Mark Don; Lauerhass, Lance; Bendixsen, Carl Lee; Hinckley, Steve Harold

2000-11-01T23:59:59.000Z

103

WASTE SOLIDIFICATION BUILDING BENCH SCALE HIGH ACTIVITY WASTE SIMULANT VARIABILITY STUDY FY2008  

SciTech Connect

The primary objective of this task was to perform a variability study of the high activity waste (HAW) acidic feed to determine the impact of feed variability on the quality of the final grout and on the mixability of the salt solution into the dry powders. The HAW acidic feeds were processed through the neutralization/pH process, targeting a final pH of 12. These fluids were then blended with the dry materials to make the final waste forms. A secondary objective was to determine if elemental substitution for cost prohibitive or toxic elements in the simulant affects the mixing response, thus providing a more economical simulant for use in full scale tests. Though not an objective, the HAW simulant used in the full scale tests was also tested and compared to the results from this task. A statistically designed test matrix was developed based on the maximum molarity inputs used to make the acidic solutions. The maximum molarity inputs were: 7.39 HNO{sub 3}, 0.11618 gallium, 0.5423 silver, and 1.1032 'other' metals based on their NO{sub 3}{sup -} contribution. Substitution of the elements aluminum for gallium and copper for silver was also considered in this test matrix, resulting in a total of 40 tests. During the NaOH addition, the neutralization/pH adjustment process was controlled to a maximum temperature of 60 C. The neutralized/pH adjusted simulants were blended with Portland cement and zircon flour at a water to cement mass ratio of 0.30. The mass ratio of zircon flour to Portland cement was 1/12. The grout was made using a Hobart N-50 mixer running at low speed for two minutes to incorporate and properly wet the dry solids with liquid and at medium speed for five minutes for mixing. The resulting fresh grout was measured for three consecutive yield stress measurements. The cured grout was measured for set, bleed, and density. Given the conditions of preparing the grout in this task, all of the grouts were visually well mixed prior to preparing the grouts for measurements. All of the cured grouts were measured for bleed and set. All of the cured grouts satisfied the bleed and set requirements, where no bleed water was observed on any of the grout samples after one day and all had set within 3 days of curing. This data indicates, for a well mixed product, bleed and set requirement are satisfied for the range of acidic feeds tested in this task. The yield stress measurements provide both an indication on the mixability of the salt solution with dry materials and an indication of how quickly the grout is starting to form structure. The inability to properly mix these two streams into a well mixed grout product will lead to a non-homogeneous mixture that will impact product quality. Product quality issues could be unmixed regions of dry material and hot spots having high concentrations of americium 241. Mixes that were more difficult to incorporate typically resulted in grouts with higher yield stresses. The mixability from these tests will provide Waste Solidification Building (WSB) an indication of which grouts will be more challenging to mix. The first yield stress measurements were statistically compared to a list of variables, specifically the batched chemicals used to make the acidic solutions. The first yield stress was also compared to the physical properties of the acidic solutions, physical and pH properties of the neutralized/pH adjusted solutions, and chemical and physical properties of the grout.

Hansen, E; Timothy Jones, T; Tommy Edwards, T; Alex Cozzi, A

2009-03-20T23:59:59.000Z

104

Final Environmental Impact Statement Waste Management Activities for Groundwater Protection Savannah River Plant Aiken, South Carolina  

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

PURPOSE PURPOSE The U.S. Department of Energv SUMRY (DOE) has Dreuared this environmental impact -. . . statement (EIS) to assess the environmental consequences of the implementation of modified waste management activities for hazardous, low-level radioactive, and mixed wastes for the protection of groundwater, human health, and the environment at its Savannah River Plant (SRP) in Aiken, South Carolina. This EIS, which is both programmatic and project-specific, has been prepared in accordance with Section 102(2)(C) of the National Environmental Policy Act (NEPA) of 1969, as amended. It is intended to support broad decisions on future actions on SRP waste management activities and to provide project- related environmental input and support for project-specific decisions on pro- ceeding with cleanup activities at existing waste sites in the R- and F-Areas, establishing new waste

105

Lessons learned from reactive transport modeling of a low-activity waste glass disposal system  

Science Conference Proceedings (OSTI)

A set of reactive chemical transport calculations were conducted with the Subsurface Transport Over Reactive Multiphases (STORM) code to evaluate the long-term performance of a representative low-activity waste glass in a shallow subsurface disposal ... Keywords: chemical transport, low-level waste, numerical model, unsaturated flow, vadose zone

Diana H. Bacon; B. Peter McGrail

2003-04-01T23:59:59.000Z

106

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

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

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

107

DuraLith Geopolymer Low Temperature Waste Forms  

Hanford Low-Activity Waste (LAW), mol/L Minor constituents: 129I, 99Tc (HSW), 99Tc, 137Cs (LAW) heavy and other metals Na OH NO 3 Al TOC Si K CO 3 Cl NO 2 PO 4 SO 4

108

Independent Activity Report, Waste Isolation Pilot Plant - September...  

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

2011 September 2011 Orientation Visit to the Waste Isolation Pilot Plant HIAR-WIPP-2011-09-07 The U.S. Department of Energy (DOE) Office of Enforcement and Oversight,...

109

Tank Waste Corporate Board Meeting 11/18/10 | Department of Energy  

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

18/10 18/10 Tank Waste Corporate Board Meeting 11/18/10 The following documents are associated with the Tank Waste Corporate Board Meeting held on November 18th, 2010. High-Level Waste Corporate Board Meeting Agenda Journey to Excellence Goal 2 and Enhanced Tank Waste Strategy Introduction to Tc/I in Hanford Flowsheet Fate of Tc99 at WTP and Current Work on Capture Technetium Retention During LAW Vitrification Impacts of Feed Composition and Recycle on Hanford Low-Activity Waste Glass Mass Secondary Waste Forms and Technetium Management Hanford Low Activity Waste (LAW) Fluidized Bed Steam Reformer (FBSR) Na-Al-Si (NAS) Waste Form Qualification Salt Waste Processing Initiatives Recap and Conclusions to Tc/I in Hanford Flowsheet Presentations Tank Closure More Documents & Publications

110

Secondary Waste Form Down-Selection Data Package—Fluidized Bed Steam Reforming Waste Form  

SciTech Connect

The Hanford Site in southeast Washington State has 56 million gallons of radioactive and chemically hazardous wastes stored in 177 underground tanks (ORP 2010). The U.S. Department of Energy (DOE), Office of River Protection (ORP), through its contractors, is constructing the Hanford Tank Waste Treatment and Immobilization Plant (WTP) to convert the radioactive and hazardous wastes into stable glass waste forms for disposal. Within the WTP, the pretreatment facility will receive the retrieved waste from the tank farms and separate it into two treated process streams. These waste streams will be vitrified, and the resulting waste canisters will be sent to offsite (high-level waste [HLW]) and onsite (immobilized low-activity waste [ILAW]) repositories. As part of the pretreatment and ILAW processing, liquid secondary wastes will be generated that will be transferred to the Effluent Treatment Facility (ETF) on the Hanford Site for further treatment. These liquid secondary wastes will be converted to stable solid waste forms that will be disposed of in the Integrated Disposal Facility (IDF). To support the selection of a waste form for the liquid secondary wastes from WTP, Washington River Protection Solutions (WRPS) has initiated secondary waste form testing work at Pacific Northwest National Laboratory (PNNL). In anticipation of a down-selection process for a waste form for the Solidification Treatment Unit to be added to the ETF, PNNL is developing data packages to support that down-selection. The objective of the data packages is to identify, evaluate, and summarize the existing information on the four waste forms being considered for stabilizing and solidifying the liquid secondary wastes. At the Hanford Site, the FBSR process is being evaluated as a supplemental technology for treating and immobilizing Hanford LAW radioactive tank waste and for treating secondary wastes from the WTP pretreatment and LAW vitrification processes.

Qafoku, Nikolla; Westsik, Joseph H.; Strachan, Denis M.; Valenta, Michelle M.; Pires, Richard P.

2011-09-12T23:59:59.000Z

111

Immobilized low-activity waste interim storage facility, Project W-465 conceptual design report  

Science Conference Proceedings (OSTI)

This report outlines the design and total estimated cost to modify the four unused grout vaults for the remote handling and interim storage of immobilized low-activity waste (ILAW).

Pickett, W.W.

1998-03-02T23:59:59.000Z

112

DURABILITY TESTING OF FLUIDIZED BED STEAM REFORMER (FBSR) WASTE FORMS  

SciTech Connect

Fluidized Bed Steam Reforming (FBSR) is being considered as a potential technology for the immobilization of a wide variety of high sodium aqueous radioactive wastes. The addition of clay and a catalyst as co-reactants converts high sodium aqueous low activity wastes (LAW) such as those existing at the Hanford and Idaho DOE sites to a granular ''mineralized'' waste form that may be made into a monolith form if necessary. Simulant Hanford and Idaho high sodium wastes were processed in a pilot scale FBSR at Science Applications International Corporation (SAIC) Science and Technology Applications Research (STAR) facility in Idaho Falls, ID. Granular mineral waste forms were made from (1) a basic Hanford Envelope A low-activity waste (LAW) simulant and (2) an acidic INL simulant commonly referred to as sodium-bearing waste (SBW). The FBSR waste forms were characterized and the durability tested via ASTM C1285 (Product Consistency Test), the Environmental Protection Agency (EPA) Toxic Characteristic Leaching Procedure (TCLP), and the Single Pass Flow Through (SPFT) test. The durability of the FBSR waste form products was tested in order to compare the measured durability to previous FBSR waste form testing on Hanford Envelope C waste forms that were made by THOR Treatment Technologies (TTT) and to compare the FBSR durability to vitreous LAW waste forms, specifically the Hanford low activity waste (LAW) glass known as the Low-activity Reference Material (LRM). The durability of the FBSR waste form is comparable to that of the LRM glass for the test responses studied.

Jantzen, C

2006-01-06T23:59:59.000Z

113

Data Packages for the Hanford Immobilized Low Activity Tank Waste Performance Assessment 2001 Version [SEC 1 THRU 5  

SciTech Connect

Data package supporting the 2001 Immobilized Low-Activity Waste Performance Analysis. Geology, hydrology, geochemistry, facility, waste form, and dosimetry data based on recent investigation are provided. Verification and benchmarking packages for selected software codes are provided.

MANN, F.M.

2000-03-02T23:59:59.000Z

114

Idaho Nuclear Technology and Engineering Center Low-Activity Waste Process Technology Program FY-99 Status Report  

SciTech Connect

The Low-Activity Waste Process Technology Program at the Idaho Nuclear Technology and Engineering Center (INTEC) anticipates that large volumes of low-level/low-activity wastes will need to be grouted prior to near-surface disposal. During fiscal year 1999, grout formulations were studied for transuranic waste derived from INTEC liquid sodium-bearing waste and for projected newly generated low-level liquid waste. Additional studies were completed on radionuclide leaching, microbial degradation, waste neutralization, and a small mockup for grouting the INTEC underground storage tank residual heels.

Herbst, Alan Keith; Mc Cray, John Alan; Kirkham, Robert John; Pao, Jenn Hai; Hinckley, Steve Harold

1999-10-01T23:59:59.000Z

115

Idaho Nuclear Technology and Engineering Center Low-Activity Waste Process Technology Program FY-99 Status Report  

SciTech Connect

The Low-Activity Waste Process Technology Program at the Idaho Nuclear Technology and Engineering Center (INTEC) anticipates that large volumes of low-level/low-activity wastes will need to be grouted prior to near-surface disposal. During fiscal year 1999, grout formulations were studied for transuranic waste derived from INTEC liquid sodium-bearing waste and for projected newly generated low-level liquid waste. Additional studies were completed on radionuclide leaching, microbial degradation, waste neutralization, and a small mockup for grouting the INTEC underground storage tank residual heels.

A. K. Herbst; J. A. McCray; R. J. Kirkham; J. Pao; S. H. Hinckley

1999-09-30T23:59:59.000Z

116

WATER ACTIVITY DATA ASSESSMENT TO BE USED IN HANFORD WASTE SOLUBILITY CALCULATIONS  

SciTech Connect

The purpose of this report is to present and assess water activity versus ionic strength for six solutes:sodium nitrate, sodium nitrite, sodium chloride, sodium carbonate, sodium sulfate, and potassium nitrate. Water activity is given versus molality (e.g., ionic strength) and temperature. Water activity is used to estimate Hanford crystal hydrate solubility present in the waste.

DISSELKAMP RS

2011-01-06T23:59:59.000Z

117

Collecting mixed waste information for Department of Energy Environmental Restoration activities  

SciTech Connect

The US Department of Energy (DOE) Office of Environmental Restoration is currently developing an integrated data structure to link information on wastes and contaminated media from environmental restoration activities with other program information, including waste management plans. Mixed wastes are a key element of this data system because of the reporting requirements of the recent Federal Facility Compliance Act. The first step taken to satisfy various environmental restoration program needs was to develop a data call that would capture information on contamination and cleanup projections for all environmental restoration sites.

Tolbert-Smith, M. [Dept. of Energy, Germantown, MD (United States); MacDonell, M.; Peterson, J. [Argonne National Lab., IL (United States)

1994-03-01T23:59:59.000Z

118

Aerobic composting of waste activated sludge: Kinetic analysis for microbiological reaction and oxygen consumption  

SciTech Connect

In order to examine the optimal design and operating parameters, kinetics for microbiological reaction and oxygen consumption in composting of waste activated sludge were quantitatively examined. A series of experiments was conducted to discuss the optimal operating parameters for aerobic composting of waste activated sludge obtained from Kawagoe City Wastewater Treatment Plant (Saitama, Japan) using 4 and 20 L laboratory scale bioreactors. Aeration rate, compositions of compost mixture and height of compost pile were investigated as main design and operating parameters. The optimal aerobic composting of waste activated sludge was found at the aeration rate of 2.0 L/min/kg (initial composting mixture dry weight). A compost pile up to 0.5 m could be operated effectively. A simple model for composting of waste activated sludge in a composting reactor was developed by assuming that a solid phase of compost mixture is well mixed and the kinetics for microbiological reaction is represented by a Monod-type equation. The model predictions could fit the experimental data for decomposition of waste activated sludge with an average deviation of 2.14%. Oxygen consumption during composting was also examined using a simplified model in which the oxygen consumption was represented by a Monod-type equation and the axial distribution of oxygen concentration in the composting pile was described by a plug-flow model. The predictions could satisfactorily simulate the experiment results for the average maximum oxygen consumption rate during aerobic composting with an average deviation of 7.4%.

Yamada, Y. [Research Center for Biochemical and Environmental Engineering, Department of Applied Chemistry, Toyo University, Kawagoe, Saitama, 350-8585 (Japan); Kawase, Y. [Research Center for Biochemical and Environmental Engineering, Department of Applied Chemistry, Toyo University, Kawagoe, Saitama, 350-8585 (Japan)]. E-mail: bckawase@mail.eng.toyo.ac.jp

2006-07-01T23:59:59.000Z

119

Impact of EPS on Digestion of Waste Activate Sludge Thomas Gostanian  

E-Print Network (OSTI)

is by either aerobic or anaerobic self-digestion, in which the bacteria consume their own mass. Currently are particular in their assistance of either aerobic or anaerobic digestion. Direct samples of activated sludgeImpact of EPS on Digestion of Waste Activate Sludge Thomas Gostanian Faculty Mentor: Professor Chul

Mountziaris, T. J.

120

Lessons Learned from V-Tank Waste Remediation Activities at the Idaho National Laboratory  

SciTech Connect

The purpose of this paper is to discuss major activities and lessons learned from remediation of the V-tank waste at Idaho National Laboratory's (INL's) Test Area North (TAN) complex. Remediation activities involved the on-site treatment, solidification and disposal of over 61,000 L (16,000 gal) of radioactively hazardous V-tank waste. In July, 2006, over 98% of the V-tank waste was disposed of at the Idaho CERCLA Disposal Facility (ICDF). Disposal was accomplished using the three 38,000-L (10,000-gal) V-tanks that had stored most of the V-tank waste for over 30 years. Included in V-Tank remediation was the removal of approximately 7,650 m{sup 3} (10,000 yd{sup 3}) of contaminated soil. Plans are to treat the remaining V-tank waste off-site in early 2007, with the treated residual also disposed of at the ICDF. Disposal of the treated V-tank waste at ICDF marked a major step in completing remediation of the TAN V-tanks, a task begun in 1999 when the original Record of Decision (ROD) was published. Over this time, there have been a number of stops and starts associated with remediating this waste. Although many of these stops and starts were unavoidable, there are a number of lessons learned for the V-tank remediation that could help prevent unnecessary expenses and schedule delays in future remediation activities within the Department of Energy (DOE) complex. This paper identifies major and minor lessons learned from V-tank waste remediation efforts - those that resulted in unnecessary delays/expenses, as well as those areas that accelerated V-tank remediation efforts. (authors)

Farnsworth, R.K.; Jessmore, J.J.; Eaton, D.L.; McDannel, G.E.; Sloan, P.A.; Jantz, A.E.; Tyson, D.R. [CH2M-Washington Group Idaho -Idaho Cleanup Project-a, Idaho Falls, ID (United States); Burt, B.T. [E2 Consulting Engineers, Idaho Falls ID (United States)

2007-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "activity waste law" 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

Water, law, science  

SciTech Connect

In a world with water resources severely impacted bytechnology, science must actively contribute to water law. To this end,this paper is an earth scientist s attempt to comprehend essentialelements of water law, and to examine their connections to science.Science and law share a common logical framework of starting with apriori prescribed tenets, and drawing consistent inferences. In science,observationally established physical laws constitute the tenets, while inlaw, they stem from social values. The foundations of modern water law inEurope and the New World were formulated nearly two thousand years ago byRoman jurists who were inspired by Greek philosophy of reason.Recognizing that vital natural elements such as water, air, and the seawere governed by immutable natural laws, they reasoned that theseelements belonged to all humans, and therefore cannot be owned as privateproperty. Legally, such public property was to be governed by jusgentium, the law of all people or the law of all nations. In contrast,jus civile or civil law governed private property. Remarkably, jusgentium continues to be relevant in our contemporary society in whichscience plays a pivotal role in exploiting vital resources common to all.This paper examines the historical roots of modern water law, followstheir evolution through the centuries, and examines how the spirit ofscience inherent in jus gentium is profoundly influencing evolving waterand environmental laws in Europe, the United States and elsewhere. In atechnological world, scientific knowledge has to lie at the core of waterlaw. Yet, science cannot formulate law. It is hoped that a philosophicalunderstanding of the relationships between science and law willcontribute to their constructively coming together in the service ofsociety.

Narasimhan, T.N.

2007-10-17T23:59:59.000Z

122

1992 annual report on low-level radioactive waste management progress; Report to Congress in response to Public Law 99-240  

Science Conference Proceedings (OSTI)

This report summarizes the progress States and compact regions made during 1992 in establishing new low-level radioactive waste disposal facilities. It also provides summary information on the volume of low-level radioactive waste received for disposal in 1992 by commercially operated low-level radioactive waste disposal facilities. This report is in response to section 7 (b) of the Low-Level Radioactive Waste Policy Act.

NONE

1993-11-01T23:59:59.000Z

123

List of Municipal Solid Waste Incentives | Open Energy Information  

Open Energy Info (EERE)

Waste Incentives Waste Incentives Jump to: navigation, search The following contains the list of 172 Municipal Solid Waste Incentives. CSV (rows 1 - 172) Incentive Incentive Type Place Applicable Sector Eligible Technologies Active Advanced Clean Energy Project Grants (Texas) State Grant Program Texas Commercial Industrial Utility Biomass Municipal Solid Waste No Advanced Energy Fund (Ohio) Public Benefits Fund Ohio Commercial Industrial Institutional Residential Utility Biomass CHP/Cogeneration Fuel Cells Fuel Cells using Renewable Fuels Geothermal Electric Hydroelectric energy Landfill Gas Microturbines Municipal Solid Waste Photovoltaics Solar Space Heat Solar Thermal Electric Solar Water Heat Wind energy Yes Alternative Energy Law (AEL) (Iowa) Renewables Portfolio Standard Iowa Investor-Owned Utility Anaerobic Digestion

124

PROMETHEE: An Alpha Low Level Waste Assay System Using Passive and Active Neutron Measurement Methods  

Science Conference Proceedings (OSTI)

The development of a passive-active neutron assay system for alpha low level waste characterization at the French Atomic Energy Commission is discussed. Less than 50 Bq[{alpha}] (about 50 {mu}g Pu) per gram of crude waste must be measured in 118-l 'European' drums in order to reach the requirements for incinerating wastes. Detection limits of about 0.12 mg of effective {sup 239}Pu in total active neutron counting, and 0.08 mg of effective {sup 239}Pu coincident active neutron counting, may currently be detected (empty cavity, measurement time of 15 min, neutron generator emission of 1.6 x 10{sup 8} s{sup -1} [4{pi}]). The most limiting parameters in terms of performances are the matrix of the drum - its composition (H, Cl...), its density, and its heterogeneity degree - and the localization and self-shielding properties of the contaminant.

Passard, Christian [French Atomic Energy Commission, C.E.A. Cadarache (France); Mariani, Alain [French Atomic Energy Commission, C.E.A. Cadarache (France); Jallu, Fanny [French Atomic Energy Commission, C.E.A. Cadarache (France); Romeyer-Dherbey, Jacques [French Atomic Energy Commission, C.E.A. Cadarache (France); Recroix, Herve [French Atomic Energy Commission, C.E.A. Cadarache (France); Rodriguez, Michel [French Atomic Energy Commission, C.E.A. Cadarache (France); Loridon, Joel [French Atomic Energy Commission, C.E.A. Cadarache (France); Denis, Caroline [French Atomic Energy Commission, C.E.A. Cadarache (France); Toubon, Herve [COGEMA (France)

2002-12-15T23:59:59.000Z

125

Melting Hanford LAW into Iron-Phosphate Glass in a CCIM  

SciTech Connect

A vitrification test has been conducted using the cold crucible induction melter (CCIM) test system at the Idaho National Laboratory. The test was conducted to demonstrate the vitrification of a Hanford low activity waste (LAW) that contains relatively large amounts of sulfate and sodium, compared to other radioactive Hanford waste streams. The high sulfate content limits the potential loading of this waste stream in conventional borosilicate glass, so this test demonstrated how this waste stream could be vitrified in an iron-phosphate glass that can tolerate higher levels of sulfate.

Nick Soelberg; Sharna Rossberg

2011-09-01T23:59:59.000Z

126

conservation laws  

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

Conservation Laws Conservation Laws Conservation Laws - Data Analysis Using Graphs - Histograms - Units or Vectors in Particle Physics In all of physics there are only six conservation laws. Each describes a quantity that is conserved, that is, the total amount is the same before and after something occurs. These laws have the restriction that the system is closed, that is, the system is not affected by anything outside it. Conservation of charge Conservation of momentum Conservation of mass/energy Conservation of angular momentum Conservation of baryons Conservation of leptons Let's review the conservation laws that you know from classical physics. Then, we will describe two particle physics conservation laws. Conservation of Charge This is used all the time in chemistry. The total charge in the system is

127

Advanced Electrochemical Waste Forms  

Science Conference Proceedings (OSTI)

... of Fluidized Bed Steam Reforming (FBSR) with Hanford Low Activity Wastes ... Level Waste at the Defense Waste Processing Facility through Sludge Batch 7b.

128

Idaho Nuclear Technology and Engineering Center Low-Activity Waste Process Technology Program FY-98 Status Report  

SciTech Connect

The Low-Activity Waste Process Technology Program at the Idaho Nuclear Technology and Engineering Center (INTEC) anticipates that large volumes of low-level/low-activity wastes will need to be grouted prior to near-surface disposal. During fiscal year 1998, three grout formulations were studied for low-activity wastes derived from INTEC liquid sodium-bearing waste. Compressive strength and leach results are presented for phosphate bonding cement, acidic grout, and alkaline grout formulations. In an additional study, grout formulations are recommended for stabilization of the INTEC underground storage tank residual heels.

Herbst, Alan Keith; Mc Cray, John Alan; Rogers, Adam Zachary; Simmons, R. F.; Palethorpe, S. J.

1999-03-01T23:59:59.000Z

129

Idaho Nuclear Technology and Engineering Center Low-Activity Waste Process Technology Program, FY-98 Status Report  

SciTech Connect

The Low-Activity Waste Process Technology Program at the Idaho Nuclear Technology and Engineering Center (INTEC) anticipates that large volumes of low-level/low-activity wastes will need to be grouted prior to near-surface disposal. During fiscal year 1998, three grout formulations were studied for low-activity wastes derived from INTEC liquid sodium-bearing waste. Compressive strength and leach results are presented for phosphate bonding cement, acidic grout, and alkaline grout formulations. In an additional study, grout formulations are recommended for stabilization of the INTEC underground storage tank residual heels.

Herbst, A.K.; Rogers, A.Z.; McCray, J.A.; Simmons, R.F.; Palethorpe, S.J.

1999-03-01T23:59:59.000Z

130

A systematic approach for future solid waste cleanup activities at the Hanford Site  

SciTech Connect

This paper describes the systematic approach to the treatment, storage, and disposal system (TSD) planning and management that has been developed and implemented by Hanford`s Solid Waste Program. The systematic approach includes: collecting the forecast and waste inventory data; defining Hanford`s TSD system; studying and refining the TSD system by using analysis tools; and documenting analysis results. The customers responsible for planning, funding, and managing future solid waste activities have driven the evolution of the solid waste system. Currently, all treatment facilities are several years from operating. As these facilities become closer to reality, more detailed systems analysis and modeling will be necessary to successfully remediate solid waste at the Site. The tools will continue to be developed in detail to address the complexities of the system as they become better defined. The tools will help determine which facility lay-outs are most optimal, will help determine what types of equipment should be used to optimize the transport of materials to and from each TSD facility, and will be used for performing life-cycle analysis. It is envisioned that in addition to developing the tools to be adapted to the more specific facility design issues, this approach will also be used as an example for other waste installations across the DOE complex.

Dirks, L.L.; Konynenbelt, H.S. [Pacific Northwest Lab., Richland, WA (United States); Hladek, K.L. [Westinghouse Hanford Co., Richland, WA (United States)

1995-02-01T23:59:59.000Z

131

Management Activities for Retrieved and Newly Generated Transuranic Wastes Savannah River Plant  

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

8 WL 253648 (F.R.) 8 WL 253648 (F.R.) NOTICES DEPARTMENT OF ENERGY Finding of No Significant Impact; Transuranic Waste Management Activities at the Savannah River Plant, Aiken, SC Tuesday, August 30, 1988 *33172 AGENCY: Department of Energy. ACTION: Finding of No Significant Impact. SUMMARY: The Department of Energy (DOE) has prepared an environmental assessment (EA), DOE/EA -0315, for transuranic (TRU) waste management activities at DOE's Savannah River Plant (SRP), including the construction and operation of a new TRU Waste Processing Facility. Based on analyses in the EA, DOE has determined that the proposed action is not a major Federal action significantly affecting the quality of the human environment, within the meaning of the National Environmental Policy Act (NEPA) of 1969. Therefore, the preparation of an environmental impact

132

Design requirements document for Project W-465, immobilized low-activity waste interim storage  

SciTech Connect

The scope of this Design Requirements Document (DRD) is to identify the functions and associated requirements that must be performed to accept, transport, handle, and store immobilized low-activity waste (ILAW) produced by the privatized Tank Waste Remediation System (TWRS) treatment contractors. The functional and performance requirements in this document provide the basis for the conceptual design of the TWRS ILAW Interim Storage facility project and provides traceability from the program level requirements to the project design activity. Technical and programmatic risk associated with the TWRS planning basis are discussed in the Tank Waste Remediation System Decisions and Risk Assessment (Johnson 1994). The design requirements provided in this document will be augmented by additional detailed design data documented by the project.

Burbank, D.A.

1998-05-19T23:59:59.000Z

133

Active Zinc Oxide Production From Waste Zinc Powder  

Science Conference Proceedings (OSTI)

In this study, various quality of active zinc oxides containing up to 98 wt. ... Comparison of Microstructural Evolution of Nickel During Conventional and Spark ...

134

Activated carbon: Utilization excluding industrial waste treatment. (Latest citations from the Compendex database). Published Search  

SciTech Connect

The bibliography contains citations concerning the commercial use and theoretical studies of activated carbon. Topics include performance evaluations in water treatment processes, preparation and regeneration techniques, materials recovery, and pore structure studies. Adsorption characteristics for specific materials are discussed. Studies pertaining specifically to industrial waste treatment are excluded. (Contains 250 citations and includes a subject term index and title list.)

Not Available

1993-06-01T23:59:59.000Z

135

CAST STONE TECHNOLOGY FOR THE TREATMENT AND IMMOBILIZATION OF LOW-ACTIVITY WASTE  

SciTech Connect

Cast stone technology is being evaluated for potential application in the treatment and immobilization of Hanford low-activity waste. The purpose of this document is to provide background information on cast stone technology. The information provided in the report is mainly based on a pre-conceptual design completed in 2003.

MINWALL HJ

2011-04-08T23:59:59.000Z

136

Sorption of metal ions from multicomponent aqueous solutions by activated carbons produced from waste  

SciTech Connect

Activated carbons produced by thermal treatment of a mixture of sunflower husks, low-grade coal, and refinery waste were studied as adsorbents of transition ion metals from aqueous solutions of various compositions. The optimal conditions and the mechanism of sorption, as well as the structure of the sorbents, were studied.

Tikhonova, L.P.; Goba, V.E.; Kovtun, M.F.; Tarasenko, Y.A.; Khavryuchenko, V.D.; Lyubchik, S.B.; Boiko, A.N. [National Academy of Science Ukraine, Kiev (Ukraine). Institute of Coal Chemistry

2008-08-15T23:59:59.000Z

137

Preliminary Closure Plan for the Immobilized Low Activity Waste (ILAW) Disposal Facility  

Science Conference Proceedings (OSTI)

This document describes the preliminary plans for closure of the Immobilized Low-Activity Waste (ILAW) disposal facility to be built by the Office of River Protection at the Hanford site in southeastern Washington. The facility will provide near-surface disposal of up to 204,000 cubic meters of ILAW in engineered trenches with modified RCRA Subtitle C closure barriers.

BURBANK, D.A.

2000-08-31T23:59:59.000Z

138

Followup of Waste Treatment and Immobilization Plant Low Activity...  

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

HSS Independent Activity Report - Rev. 0 Report Number: HIAR-WTP-2013-03-18 Site: Hanford Site Subject: Office of Enforcement and Oversight's Office of Safety and Emergency...

139

Effects of resource activities upon repository siting and waste containment with reference to bedded salt  

SciTech Connect

The primary consideration for the suitability of a nuclear waste repository site is the overall ability of the repository to safely contain radioactive waste. This report is a discussion of the past, present, and future effects of resource activities on waste containment. Past and present resource activities which provide release pathways (i.e., leaky boreholes, adjacent mines) will receive initial evaluation during the early stages of any repository site study. However, other resource activities which may have subtle effects on containment (e.g., long-term pumping causing increased groundwater gradients, invasion of saline water causing lower retardation) and all potential future resource activities must also be considered during the site evaluation process. Resource activities will affect both the siting and the designing of repositories. Ideally, sites should be located in areas of low resource activity and low potential for future activity, and repository design should seek to eliminate or minimize the adverse effects of any resource activity. Buffer zones should be created to provide areas in which resource activities that might adversely affect containment can be restricted or curtailed. This could mean removing large areas of land from resource development. The impact of these frozen assets should be assessed in terms of their economic value and of their effect upon resource reserves. This step could require a major effort in data acquisition and analysis followed by extensive numerical modeling of regional fluid flow and mass transport. Numerical models should be used to assess the effects of resource activity upon containment and should include the cumulative effects of different resource activities. Analysis by other methods is probably not possible except for relatively simple cases.

Ashby, J.; Rowe, J.

1980-02-01T23:59:59.000Z

140

Final Environmental Impact Statement Waste Management Activities for Groundwater Protection Savannah River Plant Aiken, South Carolina  

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

Els-o120 Els-o120 Final Environmental Impact Statement I Waste Management Activities for Groundwater Protection Savannah River Plant Aiken, South Carolina of Energy 1 COVER SHEET RESPONSIBLE AGENCY: U.S. Department of Energy ACTIVITY: Final Environmental Impact Statement, Waste Management I TC Activities for Groundwater Protection at the Savannah River Plant, Aiken, South Carolina. CONTACT: ABSTRACT: Additional information concerning this Statement can be obtained from: Mr. S. R. Wright Director, Environmental Division U.S. Department of Energy Savannah River Operations Office Post Office Box A Aiken, South Carolina 29802 (803) 725-3957 I TC For general information on the Department of Energy qs EIS process contact: Office of the Assistant Secretary for Environment, Safety, and Health U.S. Department of Energy Attn: Ms. Carol Bergstrom (EH-25) Acting Director, Office of

Note: This page contains sample records for the topic "activity waste law" 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

Report for Treating Hanford LAW and WTP SW Simulants: Pilot Plant Mineralizing Flowsheet  

SciTech Connect

The US Department of Energy is responsible for managing the disposal of radioactive liquid waste in underground storage tanks at the Hanford site in Washington State. The Hanford waste treatment and immobilization plant (WPT) will separate the waste into a small volume of high level waste (HLW), containing most of the radioactive constituents, and a larger volume of low activity waste (LAW), containing most of the non-radioactive chemical and hazardous constituents. The HLW and LAW will be converted into immobilized waste forms for disposal. Currently there is inadequate LAW vitrification capacity planned at the WTP to complete the mission within the required timeframe. Therefore additional LAW capacity is required. One candidate supplemental treatment technology is the fluidized bed steam reformer process (FBSR). This report describes the demonstration testing of the FBSR process using a mineralizing flowsheet for treating simulated Hanford LAW and secondary waste from the WTP (WTP SW). The FBSR testing project produced leach-resistant solid products and environmentally compliant gaseous effluents. The solid products incorporated normally soluble ions into an alkali alumino-silicate (NaS) mineral matrix. Gaseous emissions were found to be within regulatory limits. Cesium and rhenium were captured in the mineralized products with system removal efficiencies of 99.999% and 99.998 respectively. The durability and leach performance of the FBSR granular solid were superior to the low activity reference material (LMR) glass standards. Normalized product consistency test (PCT) release rates for constituents of concern were approximately 2 orders of magnitude less than that of sodium in the Hanford glass [standard].

Arlin Olson

2012-02-28T23:59:59.000Z

142

Immobilized low-activity waste site borehole 299-E17-21  

SciTech Connect

The Tank Waste Remediation System (TWRS) is the group at the Hanford Site responsible for the safe underground storage of liquid waste from previous Hanford Site operations, the storage and disposal of immobilized tank waste, and closure of underground tanks. The current plan is to dispose of immobilized low-activity tank waste (ILAW) in new facilities in the southcentral part of 200-East Area and in four existing vaults along the east side of 200-East Area. Boreholes 299-E17-21, B8501, and B8502 were drilled at the southwest corner of the ILAW site in support of the Performance Assessment activities for the disposal options. This report summarizes the initial geologic findings, field tests conducted on those boreholes, and ongoing studies. One deep (480 feet) borehole and two shallow (50 feet) boreholes were drilled at the southwest corner of the ILAW site. The primary factor dictating the location of the boreholes was their characterization function with respect to developing the geohydrologic model for the site and satisfying associated Data Quality Objectives. The deep borehole was drilled to characterize subsurface conditions beneath the ILAW site, and two shallow boreholes were drilled to support an ongoing environmental tracer study. The tracer study will supply information to the Performance Assessment. All the boreholes provide data on the vadose zone and saturated zone in a previously uncharacterized area.

Reidel, S.P.; Reynolds, K.D.; Horton, D.G.

1998-08-01T23:59:59.000Z

143

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

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

144

Thermal Diffusivity and Thermal Conductivity of HLW and LAW ...  

Science Conference Proceedings (OSTI)

In the present work, such data were collected for four waste glasses representative of those currently projected for treatment of Hanford HLW and LAW streams.

145

Assessment of national systems for obtaining local acceptance of waste management siting and routing activities  

SciTech Connect

There is a rich mixture of formal and informal approaches being used in our sister nuclear democracies in their attempts to deal with the difficulties of obtaining local acceptance for siting of waste management facilities and activities. Some of these are meeting with a degree of success not yet achieved in the US. Although this survey documents and assesses many of these approaches, time did not permit addressing in any detail their relevance to common problems in the US. It would appear the US could benefit from a periodic review of the successes and failures of these efforts, including analysis of their applicability to the US system. Of those countries (Germany, Sweden, Switzerland, Japan, Belgium, and the US) who are working to a time table for the preparation of a high-level waste (HLW) repository, Germany is the only country to have gained local siting acceptance for theirs. With this (the most difficult of siting problems) behind them they appear to be in the best overall condition relative to waste management progress and plans. This has been achieved without a particularly favorable political structure, made up for by determination on the part of the political leadership. Of the remaining three countries studied (France, UK and Canada) France, with its AVM production facility, is clearly the world leader in the HLW immobilization aspect of waste management. France, Belgium and the UK appear to have the least favorable political structures and environments for arriving at waste management decisions. US, Switzerland and Canada appear to have the least favorable political structures and environments for arriving at waste management decisions.

Paige, H.W.; Lipman, D.S.; Owens, J.E.

1980-07-01T23:59:59.000Z

146

Preliminary ILAW Formulation Algorithm Description, 24590 LAW RPT-RT-04-0003, Rev. 1  

SciTech Connect

The U.S. Department of Energy (DOE), Office of River Protection (ORP), has contracted with Bechtel National, Inc. (BNI) to design, construct, and commission the Hanford Tank Waste Treatment and Immobilization Plant (WTP) at the Hanford Site (DOE 2000). This plant is designed to operate for 40 years and treat roughly 50 million gallons of mixed hazardous high-level waste (HLW) stored in 177 underground tanks at the Hanford Site. The process involves separating the hight-level and low-activity waste (LAW) fractions through filtration, leaching, Cs ion exchange, and precipitation. Each fraction will be separately vitrified into borosilicate waste glass. This report documents the initial algorithm for use by Hanford WTP in batching LAW and glass-forming chemicals (GFCs) in the LAW melter feed preparation vessel (MFPV). Algorithm inputs include the chemical analyses of the pretreated LAW in the concentrate receipt vessel (CRV), the volume of the MFPV heel, and the compositions of individual GFCs. In addition to these inputs, uncertainties in the LAW composition and processing parameters are included in the algorithm.

Kruger, Albert A.; Kim, Dong-Sang; Vienna, John D.

2013-12-03T23:59:59.000Z

147

FINAL REPORT TESTING OF IRON PHOSPHATE LAW GLASS (VSL-11R2340-1) 04/25/2011 REV 0 06/10/2011  

Science Conference Proceedings (OSTI)

About 50 million gallons of high-level mixed waste is currently stored in underground tanks at The United States Department of Energy's (DOE's) Hanford site in the State of Washington. The Hanford Tank Waste Treatment and Immobilization Plant (WTP) will provide DOE's Office of River Protection (ORP) with a means of treating this waste by vitrification for subsequent disposal. The tank waste will be separated into low- and high-activity waste fractions, which will then be vitrified respectively into Immobilized Low Activity Waste (ILAW) and Immobilized High Level Waste (IHLW) products. The ILAW product will be disposed in an engineered facility on the Hanford site while the IHLW product will likely be directed to a national deep geological disposal facility for high-level nuclear waste. The ILA W and IHLW products must meet a variety of requirements with respect to protection of the environment before they can be accepted for disposal. The objectives of the work reported herein were to assess the corrosion of Inconel 690 and 693 in the FeP glass developed by MS&T and to measure key high temperature properties of the LAW iron phosphate glass. Specific objectives of these tests were the following: (1) Determination of the extent of corrosion of Inconel 690 and 693 in LAW FeP glass at 1050, 1l00, and 1150 C; (2) Determination of the extent of corrosion of Inconel 690 and 693 in LAW FeP glass in the presence of an electric field; (3) Measurement of the high temperature specific heat of the LAW FeP glass; (4) Measurement of the high temperature density of the LAW FeP glass; (5) Measurement of the high temperature thermal diffusivity of the LAW FeP glass; and (6) Calculation of the high temperature thermal conductivity of the LAW FeP glass from the above three measured properties.

KRUGER AA; GAN H ET AL; JOSEPH I; BEUCHELE AC; FENG Z; WANG C; VIRAGHC; PEGG IL

2011-08-31T23:59:59.000Z

148

Preliminary siting activities for new waste handling facilities at the Idaho National Engineering Laboratory  

SciTech Connect

The Idaho Waste Processing Facility, the Mixed and Low-Level Waste Treatment Facility, and the Mixed and Low-Level Waste Disposal Facility are new waste treatment, storage, and disposal facilities that have been proposed at the Idaho National Engineering Laboratory (INEL). A prime consideration in planning for such facilities is the selection of a site. Since spring of 1992, waste management personnel at the INEL have been involved in activities directed to this end. These activities have resulted in the (a) identification of generic siting criteria, considered applicable to either treatment or disposal facilities for the purpose of preliminary site evaluations and comparisons, (b) selection of six candidate locations for siting,and (c) site-specific characterization of candidate sites relative to selected siting criteria. This report describes the information gathered in the above three categories for the six candidate sites. However, a single, preferred site has not yet been identified. Such a determination requires an overall, composite ranking of the candidate sites, which accounts for the fact that the sites under consideration have different advantages and disadvantages, that no single site is superior to all the others in all the siting criteria, and that the criteria should be assigned different weighing factors depending on whether a site is to host a treatment or a disposal facility. Stakeholder input should now be solicited to help guide the final selection. This input will include (a) siting issues not already identified in the siting, work to date, and (b) relative importances of the individual siting criteria. Final site selection will not be completed until stakeholder input (from the State of Idaho, regulatory agencies, the public, etc.) in the above areas has been obtained and a strategy has been developed to make a composite ranking of all candidate sites that accounts for all the siting criteria.

Taylor, D.D.; Hoskinson, R.L.; Kingsford, C.O.; Ball, L.W.

1994-09-01T23:59:59.000Z

149

Review of the Waste Isolation Pilot Plant Work Planning and Control Activities, April 2013  

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

Independent Oversight Review of the Independent Oversight Review of the Waste Isolation Pilot Plant Work Planning and Control Activities April 2013 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Table of Contents 1.0 Purpose ................................................................................................................................................. 1 2.0 Scope.................................................................................................................................................... 1 3.0 Background........................................................................................................................................... 1 4.0 Methodology......................................................................................................................................... 2

150

Demonstration of the TRUEX process for the treatment of actual high activity tank waste at the INEEL using centrifugal contactors  

SciTech Connect

The Idaho Chemical Processing Plant (ICPP), located at the Idaho National Engineering and Environmental Laboratory (INEEL), formerly reprocessed spent nuclear fuel to recover fissionable uranium. The radioactive raffinates from the solvent extraction uranium recovery processes were converted to granular solids (calcine) in a high temperature fluidized bed. A secondary liquid waste stream was generated during the course of reprocessing, primarily from equipment decontamination between campaigns and solvent wash activities. This acidic tank waste cannot be directly calcined due to the high sodium content and has historically been blended with reprocessing raffinates or non-radioactive aluminum nitrate prior to calcination. Fuel reprocessing activities are no longer being performed at the ICPP, thereby eliminating the option of waste blending to deplete the waste inventory. Currently, approximately 5.7 million liters of high-activity waste are temporarily stored at the ICPP in large underground stainless-steel tanks. The United States Environmental Protection Agency and the Idaho Department of Health and Welfare filed a Notice of Noncompliance in 1992 contending some of the underground waste storage tanks do not meet secondary containment. As part of a 1995 agreement between the State of Idaho, the Department of Energy, and the Department of Navy, the waste must be removed from the tanks by 2012. Treatment of the tank waste inventories by partitioning the radionuclides and immobilizing the resulting high-activity and low-activity waste streams is currently under evaluation. A recent peer review identified the most promising radionuclide separation technologies for evaluation. The Transuranic Extraction-(TRUEX) process was identified as a primary candidate for separation of the actinides from ICPP tank waste.

Law, J.D.; Brewer, K.N.; Todd, T.A.; Olson, L.G.

1997-10-01T23:59:59.000Z

151

Near-Field Hydrology Data Package for the Immobilized Low-Activity Waste 2001 Performance Assessment  

SciTech Connect

Lockheed Martin Hanford Company (LMHC) is designing and assessing the performance of disposal facilities to receive radioactive wastes that are currently stored in single- and double-shell tanks at the Hanford Site. The preferred method for disposing of the portion that is classified as immobilized low-activity waste (ILAW) is to vitrify the waste and place the product in new-surface, shallow land burial facilities. The LMHC project to assess the performance of these disposal facilities is the Hanford ILAW Performance Assessment (PA) Activity. The goal of this project is to provide a reasonable expectation that the disposal of the waste is protective of the general public, groundwater resources, air resources, surface water resources, and inadvertent intruders. Achieving this goal will require prediction of contaminant migration from the facilities. This migration is expected to occur primarily via the movement of water through the facilities and the consequent transport of dissolved contaminants in the pore water of the vadose zone. Pacific Northwest National Laboratory (PNNL) assists LMHC in its performance assessment activities. One of PNNL's tasks is to provide estimates of the physical, hydraulic, and transport properties of the materials comprising the disposal facilities and the disturbed region around them. These materials are referred to as the near-field materials. Their properties are expressed as parameters of constitutive models used in simulations of subsurface flow and transport. In addition to the best-estimate parameter values, information on uncertainty in the parameter values and estimates of the changes in parameter values over time are required to complete the PA. These parameter estimates and information are contained in this report, the Near-Field Hydrology Data Package.

PD Meyer; RJ Serne

1999-12-21T23:59:59.000Z

152

Research and development activities waste fixation program. Quarterly progress report, July--September 1975  

SciTech Connect

Engineering-scale in-canister melting tests were made to evaluate the use of silicon to prevent formation of water-soluble molybdate phases in melts. The tests demonstrated that silicon metal powder added to the feed stock effectively prevents formation of such phases. A test also showed that coatings of ZrO$sub 2$ or chromium carbide on stainless steel canisters prevent oxidation during the in-can melting process. Thermal analysis of canister design concepts examined effects of type of storage, use of fins, emissivity, canister size and cracks in glass. Pressurization tests show that all types of calcine can produce very high pressures within the canister unless the calcine is post-treated at temperatures greater than 850$sup 0$C. Initial studies on the effects of alpha and recoil bombardment (from $sup 244$Cm doping) on devitrification of waste- containing glass were completed. The devitrification behavior of a waste-bearing zinc orthosilicate glass is being studied using optical microscopy, electron microprobe, and x-ray diffraction examination. Fine calcine particles were agglomerated into larger particles suitable for coating via chemical vapor deposition. Thermal stability tests of nickel and Cr$sub 7$C$sub 3$ coatings on waste calcine have been conducted, and deterioration has occurred at temperatures as low as 500$sup 0$C. Waste-containing pellets were successfully coated by plasma spraying Al$sub 2$O$sub 3$ powder. Calculations indicate that plasma spraying of large pellets is feasible on a production scale. Seven scoping runs made with a disc pelletizer indicate that it can provide a simple, inexpensive process for making high-quality pellets from calcine-frit powders. Risk assessment was used to systematically identify dominant sequences for the accidental release of radionuclides during the solidification, basin storage, and rail transport activities of high-level waste management. (JGB)

McElroy, J L

1976-01-01T23:59:59.000Z

153

Final Report - Crystal Settling, Redox, and High Temperature Properties of ORP HLW and LAW Glasses, VSL-09R1510-1, Rev. 0, dated 6/18/09  

Science Conference Proceedings (OSTI)

The radioactive tank waste treatment programs at the U. S. Department of Energy (DOE) have featured joule heated ceramic melter technology for the vitrification of high level waste (HLW). The Hanford Tank Waste Treatment and Immobilization Plant (WTP) employs this same basic technology not only for the vitrification of HLW streams but also for the vitrification of Low Activity Waste (LAW) streams. Because of the much greater throughput rates required of the WTP as compared to the vitrification facilities at the West Valley Demonstration Project (WVDP) or the Defense Waste Processing Facility (DWPF), the WTP employs advanced joule heated melters with forced mixing of the glass pool (bubblers) to improve heat and mass transport and increase melting rates. However, for both HLW and LAW treatment, the ability to increase waste loadings offers the potential to significantly reduce the amount of glass that must be produced and disposed and, therefore, the overall project costs. This report presents the results from a study to investigate several glass property issues related to WTP HLW and LAW vitrification: crystal formation and settling in selected HLW glasses; redox behavior of vanadium and chromium in selected LAW glasses; and key high temperature thermal properties of representative HLW and LAW glasses. The work was conducted according to Test Plans that were prepared for the HLW and LAW scope, respectively. One part of this work thus addresses some of the possible detrimental effects due to considerably higher crystal content in waste glass melts and, in particular, the impact of high crystal contents on the flow property of the glass melt and the settling rate of representative crystalline phases in an environment similar to that of an idling glass melter. Characterization of vanadium redox shifts in representative WTP LAW glasses is the second focal point of this work. The third part of this work focused on key high temperature thermal properties of representative WTP HLW and LAW glasses over a wide range of temperatures, from the melter operating temperature to the glass transition.

Kruger, Albert A.; Wang, C.; Gan, H.; Pegg, I. L.; Chaudhuri, M.; Kot, W.; Feng, Z.; Viragh, C.; McKeown, D. A.; Joseph, I.; Muller, I. S.; Cecil, R.; Zhao, W.

2013-11-13T23:59:59.000Z

154

Summary - Flowsheet for the Hanford Waste Treatment Plant  

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

Waste Treatment Plant Waste Treatment Plant ETR Report Date: March 2006 ETR-1 United States Department of Energy Office of Environmental Management (DOE-EM) External Technical Review of the Flowsheet for the Hanford Waste Treatment Plant (WTP) Why DOE-EM Did This Review The Hanford Waste Treatment and Immobilization Plant (WTP) is being constructed to treat the 53 million gallons of radioactive waste, separate it into high- and low-activity fractions, and produce canisters of high-level (HLW) glass (left) and containers of low-activity waste (LAW) glass (right). At the time of this review, the Plant was at approximately 70% design and 30% construction completion. The external review objective was to determine how well the WTP would meet its throughput capacities based on the current design,

155

Selection of Pretreatment Processes for Removal of Radionuclides from Hanford Tank Waste  

Science Conference Proceedings (OSTI)

The U.S. Department of Energy's (DOE's), Office of River Protection (ORP) located at Hanford Washington has established a contract (1) to design, construct, and commission a new Waste Treatment and Immobilization Plant (WTP) that will treat and immobilize the Hanford tank wastes for ultimate disposal. The WTP is comprised of four major elements, pretreatment, LAW immobilization, HLW immobilization, and balance of plant facilities. This paper describes the technologies selected for pretreatment of the LAW and HLW tank wastes, how these technologies were selected, and identifies the major technology testing activities being conducted to finalize the design of the WTP.

Carreon, R.; Mauss, B. M.; Johnson, M. E.; Holton, L. K.; Wright, G. T.; Peterson, R. A.; Rueter, K. J.

2002-02-26T23:59:59.000Z

156

National Low-Level Waste Management Program final summary report of key activities and accomplishments for fiscal year 1997  

Science Conference Proceedings (OSTI)

The US Department of Energy (DOE) has responsibilities under the Low-Level Radioactive Waste Policy Amendments Act of 1985 to assist states and compacts in their siting and licensing efforts for low-level radioactive waste disposal facilities. The National Low-Level Waste Management Program (NLLWMP) is the element of the DOE that performs the key support activities under the Act. The NLLWMP`s activities are driven by the needs of the states and compacts as they prepare to manage their low-level waste under the Act. Other work is added during the fiscal year as necessary to accommodate new requests brought on by status changes in states` and compacts` siting and licensing efforts. This report summarizes the activities and accomplishments of the NLLWMP during FY 1997.

Rittenberg, R.B.

1998-03-01T23:59:59.000Z

157

Waste tire recycling by pyrolysis  

DOE Green Energy (OSTI)

This project examines the City of New Orleans' waste tire problem. Louisiana State law, as of January 1, 1991, prohibits the knowing disposal of whole waste tires in landfills. Presently, the numerous waste tire stockpiles in New Orleans range in size from tens to hundreds of tires. New Orleans' waste tire problem will continue to increase until legal disposal facilities are made accessible and a waste tire tracking and regulatory system with enforcement provisions is in place. Tires purchased outside of the city of New Orleans may be discarded within the city's limits; therefore, as a practical matter this study analyzes the impact stemming from the entire New Orleans metropolitan area. Pyrolysis mass recovery (PMR), a tire reclamation process which produces gas, oil, carbon black and steel, is the primary focus of this report. The technical, legal and environmental aspects of various alternative technologies are examined. The feasibility of locating a hypothetical PMR operation within the city of New Orleans is analyzed based on the current economic, regulatory, and environmental climate in Louisiana. A thorough analysis of active, abandoned, and proposed Pyrolysis operations (both national and international) was conducted as part of this project. Siting a PMR plant in New Orleans at the present time is technically feasible and could solve the city's waste tire problem. Pending state legislation could improve the city's ability to guarantee a long term supply of waste tires to any large scale tire reclamation or recycling operation, but the local market for PMR end products is undefined.

Not Available

1992-10-01T23:59:59.000Z

158

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

Science Conference Proceedings (OSTI)

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

NONE

1996-08-01T23:59:59.000Z

159

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

Science Conference Proceedings (OSTI)

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

NONE

1996-01-01T23:59:59.000Z

160

Summary of expenditures of rebates from the low-level radioactive waste surcharge escrow account for calendar year 1989: Report to Congress in response to Public Law 99-240  

SciTech Connect

This response is submitted in response to the Low-Level Radioactive Waste Policy Amendments Act of 1985 (the Act), Public Law 99-240. The report summarizes expenditures made during the calendar year 1989 of surcharge rebates from the July 1, 1986, milestones. Title I of the Act requires the Department of Energy (DOE) to administer a Surcharge Escrow Account. This account consists of a portion of the surcharge fees paid by generators of low-level radioactive waste in nonsited compacts (regional compacts currently without operating disposal sites) and nonmember States (States without disposal sites that are not members of compacts) to the three States with operating disposal facilities (Nevada, South Carolina, and Washington) (sited States) for using their disposal facilities. In administering the Surcharge Escrow Account, the Act requires DOE to: invest the funds in interest-bearing United States Government securities; determine eligibility of rebates of the funds by evaluating State and compact progress toward developing new disposal sites against milestones set forth in the Act; disburse the collected rebates and interest; assess compliance of rebate expenditures with the limitations prescribed in the Act; and submit a report annually to Congress summarizing rebate expenditures by States and regions. 5 tabs.

Not Available

1990-06-01T23:59:59.000Z

Note: This page contains sample records for the topic "activity waste law" 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

Round-robin testing of a reference glass for low-activity waste forms  

SciTech Connect

A round robin test program was conducted with a glass that was developed for use as a standard test material for acceptance testing of low-activity waste glasses made with Hanford tank wastes. The glass is referred to as the low-activity test reference material (LRM). The program was conducted to measure the interlaboratory reproducibility of composition analysis and durability test results. Participants were allowed to select the methods used to analyze the glass composition. The durability tests closely followed the Product Consistency Test (PCT) Method A, except that tests were conducted at both 40 and 90 C and that parallel tests with a reference glass were not required. Samples of LRM glass that had been crushed, sieved, and washed to remove fines were provided to participants for tests and analyses. The reproducibility of both the composition and PCT results compare favorably with the results of interlaboratory studies conducted with other glasses. From the perspective of reproducibility of analysis results, this glass is acceptable for use as a composition standard for nonradioactive components of low-activity waste forms present at >0.1 elemental mass % and as a test standard for PCTS at 40 and 90 C. For PCT with LRM glass, the expected test results at the 95% confidence level are as follows: (1) at 40 C: pH = 9.86 {+-} 0.96; [B] = 2.30 {+-} 1.25 mg/L; [Na] = 19.7 {+-} 7.3 mg/L; [Si] = 13.7 {+-} 4.2 mg/L; and (2) at 90 C: pH = 10.92 {+-} 0.43; [B] = 26.7 {+-} 7.2 mg/L; [Na] = 160 {+-} 13 mg/L; [Si] = 82.0 {+-} 12.7 mg/L. These ranges can be used to evaluate the accuracy of PCTS conducted at other laboratories.

Ebert, W. L.; Wolf, S. F.

1999-12-06T23:59:59.000Z

162

Swedish nuclear waste efforts  

SciTech Connect

After the introduction of a law prohibiting the start-up of any new nuclear power plant until the utility had shown that the waste produced by the plant could be taken care of in an absolutely safe way, the Swedish nuclear utilities in December 1976 embarked on the Nuclear Fuel Safety Project, which in November 1977 presented a first report, Handling of Spent Nuclear Fuel and Final Storage of Vitrified Waste (KBS-I), and in November 1978 a second report, Handling and Final Storage of Unreprocessed Spent Nuclear Fuel (KBS II). These summary reports were supported by 120 technical reports prepared by 450 experts. The project engaged 70 private and governmental institutions at a total cost of US $15 million. The KBS-I and KBS-II reports are summarized in this document, as are also continued waste research efforts carried out by KBS, SKBF, PRAV, ASEA and other Swedish organizations. The KBS reports describe all steps (except reprocessing) in handling chain from removal from a reactor of spent fuel elements until their radioactive waste products are finally disposed of, in canisters, in an underground granite depository. The KBS concept relies on engineered multibarrier systems in combination with final storage in thoroughly investigated stable geologic formations. This report also briefly describes other activities carried out by the nuclear industry, namely, the construction of a central storage facility for spent fuel elements (to be in operation by 1985), a repository for reactor waste (to be in operation by 1988), and an intermediate storage facility for vitrified high-level waste (to be in operation by 1990). The R and D activities are updated to September 1981.

Rydberg, J.

1981-09-01T23:59:59.000Z

163

Thermodynamics of electrolyte mixtures. Activity and osmotic coefficients consistent with the higher-order limiting law for symmetrical mixing  

SciTech Connect

The parameters for symmetrical mixing of ions of the same sign in the virial-coefficient (Pitzer) system are evaluated from literature data for 25/sup 0/C in a manner consistent with the higher-order limiting law of Friedman. Twenty-four systems involve cation mixing with a common anion and fourteen involve anion mixing with a common cation. Heat of mixing data were similarly treated in a recent publication; the results give the temperature coefficients of some of these same parameters. The combined results yield the mixing parameters as functions of temperature on a basis both self-consistent and in accord with the limiting law. The results also yield, for a few systems without a common ion, predicted values in good agreement with experimental data.

Yang, J.; Pitzer, K.S.

1988-10-01T23:59:59.000Z

164

Summary - Demonstration Bulk Vitrification System (DBVS) for Low-Actvity Waste at Hanford  

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

DBVS DBVS ETR Report Date: September 2006 ETR-3 United States Department of Energy Office of Environmental Management (DOE-EM) External Technical Review of the Demonstration Bulk Vitrification System (DBVS) for Low Activity Waste (LAW) at Hanford Why DOE-EM Did This Review The Department of Energy (DOE) is charged with the safe retrieval, treatment and disposal of 53 million gallons of Hanford radioactive waste. The Waste Treatment Plant (WTP) is being designed to treat and vitrify the High Level Waste (HLW) fraction in 20-25 years. The WTP is undersized for vitrifying the LAW fraction over the same time frame. The DOE is evaluating Bulk Vitrification as an alternative to increasing the size of the WTP LAW treatment process. Bulk vitrification is an in-container melting

165

Program on Technology Innovation: Volume Reduction Methods and Waste Form Changes for High-Activity Spent Resin  

Science Conference Proceedings (OSTI)

The Electric Power Research Institute (EPRI) has initiated a series of studies to mitigate the impact of limited disposal-site access on continued light water reactor operations. A previous EPRI report, Program on Technology Innovation: Volume Reduction Methods and Waste Form Changes for High-Activity Spent Resin: A Feasibility Study (1025303), established that cation and anion resin beads could be separated for the purpose of rendering the anion resin as Class A resin waste, and ...

2013-11-14T23:59:59.000Z

166

Waste Management Programmatic Environmental Impact Statement (WM PEIS)  

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

Waste Waste Management Programmatic Environmental Impact Statement (WM PEIS) Reports and Records of Decision Waste Management Programmatic Environmental Impact Statement (WM PEIS) Reports and Records of Decision The Final Waste Management Programmatic Environmental Impact Statement (WM PEIS) is a nationwide study examining the environmental impacts of managing more than 2 million cubic meters of radioactive wastes from past, present, and future DOE activities. The WM PEIS will assist the U.S. Department of Energy (DOE) in improving the efficiency and reliability of management of its current and anticipated volumes of radioactive and hazardous wastes and will help DOE continue to comply with applicable laws and regulations and protect workers, public health and safety, and the environment. The WM PEIS

167

Thirty-Year Solid Waste Generation Maximum and Minimum Forecast for SRS  

SciTech Connect

This report is the third phase (Phase III) of the Thirty-Year Solid Waste Generation Forecast for Facilities at the Savannah River Site (SRS). Phase I of the forecast, Thirty-Year Solid Waste Generation Forecast for Facilities at SRS, forecasts the yearly quantities of low-level waste (LLW), hazardous waste, mixed waste, and transuranic (TRU) wastes generated over the next 30 years by operations, decontamination and decommissioning and environmental restoration (ER) activities at the Savannah River Site. The Phase II report, Thirty-Year Solid Waste Generation Forecast by Treatability Group (U), provides a 30-year forecast by waste treatability group for operations, decontamination and decommissioning, and ER activities. In addition, a 30-year forecast by waste stream has been provided for operations in Appendix A of the Phase II report. The solid wastes stored or generated at SRS must be treated and disposed of in accordance with federal, state, and local laws and regulations. To evaluate, select, and justify the use of promising treatment technologies and to evaluate the potential impact to the environment, the generic waste categories described in the Phase I report were divided into smaller classifications with similar physical, chemical, and radiological characteristics. These smaller classifications, defined within the Phase II report as treatability groups, can then be used in the Waste Management Environmental Impact Statement process to evaluate treatment options. The waste generation forecasts in the Phase II report includes existing waste inventories. Existing waste inventories, which include waste streams from continuing operations and stored wastes from discontinued operations, were not included in the Phase I report. Maximum and minimum forecasts serve as upper and lower boundaries for waste generation. This report provides the maximum and minimum forecast by waste treatability group for operation, decontamination and decommissioning, and ER activities.

Thomas, L.C.

1994-10-01T23:59:59.000Z

168

Hanford Immobilized Low Activity Waste (ILAW) Performance Assessment 2001 Version [Formerly DOE/RL-97-69] [SEC 1 & 2  

SciTech Connect

The Hanford Immobilized Low-Activity Waste Performance Assessment examines the long-term environmental and human health effects associated with the planned disposal of the vitrified low-activity fraction of waste presently contained in Hanford Site tanks. The tank waste is the byproduct of separating special nuclear materials from irradiated nuclear fuels over the past 50 years. This waste is stored in underground single- and double-shell tanks. The tank waste is to be retrieved, separated into low-activity and high-level fractions, and then immobilized by vitrification. The US. Department of Energy (DOE) plans to dispose of the low-activity fraction in the Hanford Site 200 East Area. The high-level fraction will be stored at the Hanford Site until a national repository is approved. This report provides the site-specific long-term environmental information needed by the DOE to modify the current Disposal Authorization Statement for the Hanford Site that would allow the following: construction of disposal trenches; and filling of these trenches with ILAW containers and filler material with the intent to dispose of the containers.

MANN, F.M.

2000-08-01T23:59:59.000Z

169

Will Moore's Law Be Sufficient?  

Science Conference Proceedings (OSTI)

It seems well understood that supercomputer simulation is an enabler for scientific discoveries, weapons, and other activities of value to society. It also seems widely believed that Mooreýs Law will make progressively more powerful supercomputers ...

Erik P. DeBenedictis

2004-11-01T23:59:59.000Z

170

Final Environmental Impact Statement Waste Management Activities for Groundwater Protection Savannah River Plant Aiken, South Carolina  

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

I I I Y DoE/Els-o120 Final Environmental Impact Statement Waste Management Activities for Groundwater Protection Savannah River Plant Aiken, South Carolina Volume 2 Q ~<$c'% ~ v ~ g ;:: # +4 -~ STATES O* December 1987 United States Department of Energy -- TABLE OF CONTENTS Appendix A GEOLOGY AND SUBSURFACE HYDROLOGY . . . . . . . . . . . . . . . A.1 Geology and Seismology . . . . . . . . . . . . . . . . . A.1.l Regional Geologic Setting . . . . . . . . . . . . A.1.1.1 Tectonic Provinces . . . . . . . . . . . A.I.1.2 Stratigraphy . . . . . . . . . . . . . . A.1.1.3 Geomorphology . . . . . . . . . . . . . . A.1.2 Seismology and Geologic Hazards . . . . . . . . . A.1.2.1 Geologic Structures and Seismicity . . . A.1.2.2 Seismic Events and Liquefaction Potentill . . . . . . . . . . . . . . . . A.2 Groundwater Resources . . . . . . . . . . . . . . . . . . A.2.1 Hydrostratigraphy . . . . . . . . . . . . . . . . A.2.2 Groundwater Hydrology . . . . . . . . . . . . . . A.2.2.1 Hydrologic Properties

171

Final Environmental Impact Statement Waste Management Activities for Groundwater Protection Savannah River Plant Aiken, South Carolina  

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

Impact Impact \ DoE/Els-o120 Statement Waste Management Activities for Groundwater Protection Savannah River Plant Aiken, South Carolina Volume 3 Q ~+ ~ FNT O&@+@ &v a w ~ k ~ ;%." $ +6 & ~+e $TiTES Of December 1987 United States Department of Energy TABLE OF CONTENTS ~pendix G ASSESSMENT OF ALTERNATIVE STRATEGIES FOR STORAGE FACILITIES . . . . . . . . . . . G.1 No-Action Strategy . . . . . . . . G.1.l Sununarv and Objectives . . NEW DISPOSAL/ . . . . . . . . . . . . . . . G.1.2 Groundwater and Surface Water Effects G.1.3 Nonradioactive Atmospheric Releases . G.1.4 Ecological Effects . . . . . . . . . G.1.5 Radiological Releases . . . . . . . . G.1.6 Archaeological and Historic Resources G.1.7 SOciOecOnOmics . . . . . . . . . . . G.1.8 Dedication of Site . . . . . . . . . G.1.9 Institutional Impacts . . . . . . . . G.l.10 Noise . . . . . . . . . . . . . . . . G.2 Dedication Strategy . . . . . . . . . . . . . G.2.1 G.2.2 G.2.3 G.2.4 G.2.5 G.2.6

172

Geochemical data package for the Hanford immobilized low-activity tank waste performance assessment (ILAW PA)  

Science Conference Proceedings (OSTI)

Lockheed Martin Hanford Company (LMHC) is designing and assessing the performance of disposal facilities to receive radioactive wastes that are stored in single- and double-shell tanks at the Hanford Site. The preferred method of disposing of the portion that is classified as low-activity waste is to vitrify the liquid/slurry and place the solid product in near-surface, shallow-land burial facilities. The LMHC project to assess the performance of these disposal facilities is the Hanford Immobilized Low-Activity Tank Waste (ILAW) Performance Assessment (PA) activity. The goal of this project is to provide a reasonable expectation that the disposal of the waste is protective of the general public, groundwater resources, air resources, surface-water resources, and inadvertent intruders. Achieving this goal will require prediction of contaminant migration from the facilities. This migration is expected to occur primarily via the movement of water through the facilities, and the consequent transport of dissolved contaminants in the porewater of the vadose zone. Pacific Northwest National Laboratory assists LMHC in their performance assessment activities. One of the PNNL tasks is to provide estimates of the geochemical properties of the materials comprising the disposal facility, the disturbed region around the facility, and the physically undisturbed sediments below the facility (including the vadose zone sediments and the aquifer sediments in the upper unconfined aquifer). The geochemical properties are expressed as parameters that quantify the adsorption of contaminants and the solubility constraints that might apply for those contaminants that may exceed solubility constraints. The common parameters used to quantify adsorption and solubility are the distribution coefficient (K{sub d}) and the thermodynamic solubility product (K{sub sp}), respectively. In this data package, the authors approximate the solubility of contaminants using a more simplified construct, called the solution concentration limit, a constant value. In future geochemical data packages, they will determine whether a more rigorous measure of solubility is necessary or warranted based on the dose predictions emanating from the ILAW 2001 PA and reviewers' comments. The K{sub d}s and solution concentration limits for each contaminant are direct inputs to subsurface flow and transport codes used to predict the performance of the ILAW system. In addition to the best-estimate K{sub d}s, a reasonable conservative value and a range are provided. They assume that K{sub d} values are log normally distributed over the cited ranges. Currently, they do not give estimates for the range in solubility limits or their uncertainty. However, they supply different values for both the K{sub d}s and solution concentration limits for different spatial zones in the ILAW system and supply time-varying K{sub d}s for the concrete zone, should the final repository design include concrete vaults or cement amendments to buffer the system pH.

DI Kaplan; RJ Serne

2000-02-24T23:59:59.000Z

173

Characterizing and improving passive-active shufflers for assays of 208-Liter waste drums  

DOE Green Energy (OSTI)

A passive and active neutron shuffler for 208-L waste drums has been used to perform over 1500 active and 500 passive measurements on uranium and plutonium samples in 28 different matrices. The shuffler is now better characterized and improvements have been implemented or suggested. An improved correction for the effects of the matrix material was devised from flux-monitor responses. The most important cause of inaccuracies in assays is a localized instead of a uniform distribution of fissile material in a drum; a technique for deducing the distribution from the assay data and then applying a correction is suggested and will be developed further. A technique is given to detect excessive amounts of moderator that could make hundreds of grams of {sup 235}U assay as zero grams. Sensitivities (minimum detectable masses) for {sup 235}U with active assays and for {sup 240}Pu{sub eff} with passive assays are presented and the effects of moderators and absorbers on sensitivities noted.

Rinard, P.M.; Adams, E.L.; Menlove, H.O.; Sprinkle, J.K. Jr.

1992-06-01T23:59:59.000Z

174

Characterizing and improving passive-active shufflers for assays of 208-Liter waste drums  

DOE Green Energy (OSTI)

A passive and active neutron shuffler for 208-L waste drums has been used to perform over 1500 active and 500 passive measurements on uranium and plutonium samples in 28 different matrices. The shuffler is now better characterized and improvements have been implemented or suggested. An improved correction for the effects of the matrix material was devised from flux-monitor responses. The most important cause of inaccuracies in assays is a localized instead of a uniform distribution of fissile material in a drum; a technique for deducing the distribution from the assay data and then applying a correction is suggested and will be developed further. A technique is given to detect excessive amounts of moderator that could make hundreds of grams of {sup 235}U assay as zero grams. Sensitivities (minimum detectable masses) for {sup 235}U with active assays and for {sup 240}Pu{sub eff} with passive assays are presented and the effects of moderators and absorbers on sensitivities noted.

Rinard, P.M.; Adams, E.L.; Menlove, H.O.; Sprinkle, J.K. Jr.

1992-01-01T23:59:59.000Z

175

Toxicity mitigation and solidification of municipal solid waste incinerator fly ash using alkaline activated coal ash  

Science Conference Proceedings (OSTI)

Highlights: Black-Right-Pointing-Pointer Incinerator fly ash (IFA) is added to an alkali activated coal fly ash (CFA) matrix. Black-Right-Pointing-Pointer Means of stabilizing the incinerator ash for use in construction applications. Black-Right-Pointing-Pointer Concrete made from IFA, CFA and IFA-CFA mixes was chemically characterized. Black-Right-Pointing-Pointer Environmentally friendly solution to IFA disposal by reducing its toxicity levels. - Abstract: Municipal solid waste (MSW) incineration is a common and effective practice to reduce the volume of solid waste in urban areas. However, the byproduct of this process is a fly ash (IFA), which contains large quantities of toxic contaminants. The purpose of this research study was to analyze the chemical, physical and mechanical behaviors resulting from the gradual introduction of IFA to an alkaline activated coal fly ash (CFA) matrix, as a mean of stabilizing the incinerator ash for use in industrial construction applications, where human exposure potential is limited. IFA and CFA were analyzed via X-ray fluorescence (XRF), X-ray diffraction (XRD) and Inductive coupled plasma (ICP) to obtain a full chemical analysis of the samples, its crystallographic characteristics and a detailed count of the eight heavy metals contemplated in US Title 40 of the Code of Federal Regulations (40 CFR). The particle size distribution of IFA and CFA was also recorded. EPA's Toxicity Characteristic Leaching Procedure (TCLP) was followed to monitor the leachability of the contaminants before and after the activation. Also images obtained via Scanning Electron Microscopy (SEM), before and after the activation, are presented. Concrete made from IFA, CFA and IFA-CFA mixes was subjected to a full mechanical characterization; tests include compressive strength, flexural strength, elastic modulus, Poisson's ratio and setting time. The leachable heavy metal contents (except for Se) were below the maximum allowable limits and in many cases even below the reporting limit. The leachable Chromium was reduced from 0.153 down to 0.0045 mg/L, Arsenic from 0.256 down to 0.132 mg/L, Selenium from 1.05 down to 0.29 mg/L, Silver from 0.011 down to .001 mg/L, Barium from 2.06 down to 0.314 mg/L and Mercury from 0.007 down to 0.001 mg/L. Although the leachable Cd exhibited an increase from 0.49 up to 0.805 mg/L and Pd from 0.002 up to 0.029 mg/L, these were well below the maximum limits of 1.00 and 5.00 mg/L, respectively.

Ivan Diaz-Loya, E. [Alternative Cementitious Binders Laboratory (ACBL), Department of Civil Engineering, Louisiana Tech University, Ruston, LA 71272 (United States); Allouche, Erez N., E-mail: allouche@latech.edu [Alternative Cementitious Binders Laboratory (ACBL), Department of Civil Engineering, Louisiana Tech University, Ruston, LA 71272 (United States); Eklund, Sven; Joshi, Anupam R. [Department of Chemistry, Louisiana Tech University, Ruston, LA 71272 (United States); Kupwade-Patil, Kunal [Alternative Cementitious Binders Laboratory (ACBL), Department of Civil Engineering, Louisiana Tech University, Ruston, LA 71272 (United States)

2012-08-15T23:59:59.000Z

176

Activated carbon: Utilization excluding industrial waste treatment. (Latest citations from the EI Compendex*plus database). Published Search  

SciTech Connect

The bibliography contains citations concerning the commercial use and theoretical studies of activated carbon. Topics include performance evaluations in water treatment processes, preparation and regeneration techniques, materials recovery, and pore structure studies. Adsorption characteristics for specific materials are discussed. Studies pertaining specifically to industrial waste treatment are excluded. (Contains 250 citations and includes a subject term index and title list.)

Not Available

1993-11-01T23:59:59.000Z

177

Load requirements for maintaining structural integrity of Hanford single-shell tanks during waste feed delivery and retrieval activities  

Science Conference Proceedings (OSTI)

This document provides structural load requirements and their basis for maintaining the structural integrity of the Hanford Single-Shell Tanks during waste feed delivery and retrieval activities. The requirements are based on a review of previous requirements and their basis documents as well as load histories with particular emphasis on the proposed lead transfer feed tanks for the privatized vitrification plant.

JULYK, L.J.

1999-09-22T23:59:59.000Z

178

Testing of Large-Scale ICV Glasses with Hanford LAW Simulant  

SciTech Connect

Preliminary glass compositions for immobilizing Hanford low-activity waste (LAW) by the in-container vitrification (ICV) process were initially fabricated at crucible- and engineering-scale, including simulants and actual (radioactive) LAW. Glasses were characterized for vapor hydration test (VHT) and product consistency test (PCT) responses and crystallinity (both quenched and slow-cooled samples). Selected glasses were tested for toxicity characteristic leach procedure (TCLP) responses, viscosity, and electrical conductivity. This testing showed that glasses with LAW loading of 20 mass% can be made readily and meet all product constraints by a far margin. Glasses with over 22 mass% Na2O can be made to meet all other product quality and process constraints. Large-scale testing was performed at the AMEC, Geomelt Division facility in Richland. Three tests were conducted using simulated LAW with increasing loadings of 12, 17, and 20 mass% Na2O. Glass samples were taken from the test products in a manner to represent the full expected range of product performance. These samples were characterized for composition, density, crystalline and non-crystalline phase assemblage, and durability using the VHT, PCT, and TCLP tests. The results, presented in this report, show that the AMEC ICV product with meets all waste form requirements with a large margin. These results provide strong evidence that the Hanford LAW can be successfully vitrified by the ICV technology and can meet all the constraints related to product quality. The economic feasibility of the ICV technology can be further enhanced by subsequent optimization.

Hrma, Pavel R.; Kim, Dong-Sang; Vienna, John D.; Matyas, Josef; Smith, Donald E.; Schweiger, Michael J.; Yeager, John D.

2005-03-01T23:59:59.000Z

179

Hanford Low-Level Waste Form Performance for Meeting Land Disposal Requirements  

Science Conference Proceedings (OSTI)

Immobilized Low-activity waste (ILAW) from the Hanford site will be disposed of in near-surface burial grounds and must be processed into a chemically durable waste form to prevent release of hazardous constituents to the environment. To meet his goal, the LAW will be immobilized in borosilicate glass. the DOE office of River Protection and the Rive Protection Project-Waste Treatment Plant (RPP-WTP) project have agreed on testing requirements that the immobilized LAW glass must meet to demonstrate chemically durability. Two of the tests are the Product Consistency Test (PCT) and Environmental Protection Agency's (EPA) Toxicity Characteristic Leaching Procedure (TCLP). This paper provides results of RPP-WTP PCT and TCLP testing on both actual radioactive and non-radioactive simulant LAW glasses to show they meet the associated land disposal requirements.

Crawford, C.L.

2003-01-07T23:59:59.000Z

180

FY-97 operations of the pilot-scale glass melter to vitrify simulated ICPP high activity sodium-bearing waste  

SciTech Connect

A 3.5 liter refractory-lined joule-heated glass melter was built to test the applicability of electric melting to vitrify simulated high activity waste (HAW). The HAW streams result from dissolution and separation of Idaho Chemical Processing Plant (ICPP) calcines and/or radioactive liquid waste. Pilot scale melter operations will establish selection criteria needed to evaluate the application of joule heating to immobilize ICPP high activity waste streams. The melter was fabricated with K-3 refractory walls and Inconel 690 electrodes. It is designed to be continuously operated at 1,150 C with a maximum glass output rate of 10 lbs/hr. The first set of tests were completed using surrogate HAW-sodium bearing waste (SBW). The melter operated for 57 hours and was shut down due to excessive melt temperatures resulting in low glass viscosity (< 30 Poise). Due to the high melt temperature and low viscosity the molten glass breached the melt chamber. The melter has been dismantled and examined to identify required process improvement areas and successes of the first melter run. The melter has been redesigned and is currently being fabricated for the second run, which is scheduled to begin in December 1997.

Musick, C.A.

1997-11-01T23:59:59.000Z

Note: This page contains sample records for the topic "activity waste law" 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

Pilot-scale anaerobic co-digestion of municipal biomass waste and waste activated sludge in China: Effect of organic loading rate  

Science Conference Proceedings (OSTI)

Highlights: Black-Right-Pointing-Pointer Co-digestion of municipal biomass waste (MBW) and waste activated sludge (WAS) was examined on a pilot-scale reactor. Black-Right-Pointing-Pointer System performance and stability under OLR of 1.2, 2.4, 3.6, 4.8, 6.0 and 8.0 kg VS (m{sup 3} d){sup -1} were analyzed. Black-Right-Pointing-Pointer A maximum methane production rate of 2.94 m{sup 3} (m{sup 3} d){sup -1} was achieved at OLR of 8.0 kg VS (m{sup 3} d){sup -1} and HRT of 15d. Black-Right-Pointing-Pointer With the increasing OLRs, pH values, VS removal rate and methane concentration decreased and VFA increased. Black-Right-Pointing-Pointer The changing of biogas production rate can be a practical approach to monitor and control anaerobic digestion system. - Abstract: The effects of organic loading rate on the performance and stability of anaerobic co-digestion of municipal biomass waste (MBW) and waste activated sludge (WAS) were investigated on a pilot-scale reactor. The results showed that stable operation was achieved with organic loading rates (OLR) of 1.2-8.0 kg volatile solid (VS) (m{sup 3} d){sup -1}, with VS reduction rates of 61.7-69.9%, and volumetric biogas production of 0.89-5.28 m{sup 3} (m{sup 3} d){sup -1}. A maximum methane production rate of 2.94 m{sup 3} (m{sup 3} d){sup -1} was achieved at OLR of 8.0 kg VS (m{sup 3} d){sup -1} and hydraulic retention time of 15 days. With increasing OLRs, the anaerobic reactor showed a decrease in VS removal rate, average pH value and methane concentration, and a increase of volatile fatty acid concentration. By monitoring the biogas production rate (BPR), the anaerobic digestion system has a higher acidification risk under an OLR of 8.0 kg VS (m{sup 3} d){sup -1}. This result remarks the possibility of relating bioreactor performance with BPR in order to better understand and monitor anaerobic digestion process.

Liu Xiao, E-mail: liuxiao07@mails.tsinghua.edu.cn [School of Environment, Tsinghua University, Beijing 100084 (China); Wang Wei; Shi Yunchun; Zheng Lei [School of Environment, Tsinghua University, Beijing 100084 (China); Gao Xingbao [Chinese Research Academy of Environmental Sciences, Beijing 100012 (China); Qiao Wei [State Key Laboratory of Heavy Oil Processing, China University of Petroleum, Beijing 102249 (China); Zhou Yingjun [Department of Urban and Environmental Engineering, Graduate School of Engineering, Kyoto University, Katsura, Nisikyo-ku, Kyoto 615-8540 (Japan)

2012-11-15T23:59:59.000Z

182

Waste tire recycling by pyrolysis  

DOE Green Energy (OSTI)

This project examines the City of New Orleans` waste tire problem. Louisiana State law, as of January 1, 1991, prohibits the knowing disposal of whole waste tires in landfills. Presently, the numerous waste tire stockpiles in New Orleans range in size from tens to hundreds of tires. New Orleans` waste tire problem will continue to increase until legal disposal facilities are made accessible and a waste tire tracking and regulatory system with enforcement provisions is in place. Tires purchased outside of the city of New Orleans may be discarded within the city`s limits; therefore, as a practical matter this study analyzes the impact stemming from the entire New Orleans metropolitan area. Pyrolysis mass recovery (PMR), a tire reclamation process which produces gas, oil, carbon black and steel, is the primary focus of this report. The technical, legal and environmental aspects of various alternative technologies are examined. The feasibility of locating a hypothetical PMR operation within the city of New Orleans is analyzed based on the current economic, regulatory, and environmental climate in Louisiana. A thorough analysis of active, abandoned, and proposed Pyrolysis operations (both national and international) was conducted as part of this project. Siting a PMR plant in New Orleans at the present time is technically feasible and could solve the city`s waste tire problem. Pending state legislation could improve the city`s ability to guarantee a long term supply of waste tires to any large scale tire reclamation or recycling operation, but the local market for PMR end products is undefined.

Not Available

1992-10-01T23:59:59.000Z

183

Solid Waste and Infectious Waste Regulations (Ohio) | Department of Energy  

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

and Infectious Waste Regulations (Ohio) and Infectious Waste Regulations (Ohio) Solid Waste and Infectious Waste Regulations (Ohio) < Back Eligibility Utility Agricultural Investor-Owned Utility Industrial Municipal/Public Utility Local Government Rural Electric Cooperative Program Info State Ohio Program Type Environmental Regulations Provider Ohio Environmental Protection Agency This chapter of the law that establishes the Ohio Environmental Protection Agency establishes the rules and regulations regarding solid waste. The chapter establishes specific regulations for biomass facilities, which includes permitting, siting, operation, safety guidelines, and closing requirements. Siting regulations include setbacks from waste handling areas for state facilities (1000 feet from jails, schools), requirements for not siting

184

Microbiological characterization and specific methanogenic activity of anaerobe sludges used in urban solid waste treatment  

SciTech Connect

This study presents the microbiological characterization of the anaerobic sludge used in a two-stage anaerobic reactor for the treatment of organic fraction of urban solid waste (OFUSW). This treatment is one alternative for reducing solid waste in landfills at the same time producing a biogas (CH{sub 4} and CO{sub 2}) and an effluent that can be used as biofertilizer. The system was inoculated with sludge from a wastewater treatment plant (WWTP) (Rio Frio Plant in Bucaramanga-Colombia) and a methanogenic anaerobic digester for the treatment of pig manure (Mesa de los Santos in Santander). Bacterial populations were evaluated by counting groups related to oxygen sensitivity, while metabolic groups were determined by most probable number (MPN) technique. Specific methanogenic activity (SMA) for acetate, formate, methanol and ethanol substrates was also determined. In the acidogenic reactor (R1), volatile fatty acids (VFA) reached values of 25,000 mg L{sup -1} and a concentration of CO{sub 2} of 90%. In this reactor, the fermentative population was predominant (10{sup 5}-10{sup 6} MPN mL{sup -1}). The acetogenic population was (10{sup 5} MPN mL{sup -1}) and the sulphate-reducing population was (10{sup 4}-10{sup 5} MPN mL{sup -1}). In the methanogenic reactor (R2), levels of CH{sub 4} (70%) were higher than CO{sub 2} (25%), whereas the VFA values were lower than 4000 mg L{sup -1}. Substrate competition between sulphate-reducing (10{sup 4}-10{sup 5} MPN mL{sup -1}) and methanogenic bacteria (10{sup 5} MPN mL{sup -1}) was not detected. From the SMA results obtained, acetoclastic (2.39 g COD-CH{sub 4} g{sup -1} VSS{sup -1} day{sup -1}) and hydrogenophilic (0.94 g COD-CH{sub 4} g{sup -1} VSS{sup -1} day{sup -1}) transformations as possible metabolic pathways used by methanogenic bacteria is suggested from the SMA results obtained. Methanotrix sp., Methanosarcina sp., Methanoccocus sp. and Methanobacterium sp. were identified.

Sandoval Lozano, Claudia Johanna [Centro de Estudios e Investigaciones Ambientales, Universidad Industrial de Santander, Calle 9A Carrera 27, Aptdo Aereo 678, Bucaramanga (Colombia)], E-mail: ceiam@uis.edu.co; Vergara Mendoza, Marisol; Carreno de Arango, Mariela; Castillo Monroy, Edgar Fernando [Centro de Estudios e Investigaciones Ambientales, Universidad Industrial de Santander, Calle 9A Carrera 27, Aptdo Aereo 678, Bucaramanga (Colombia)

2009-02-15T23:59:59.000Z

185

MEASUREMENT AND CALCULATION OF RADIONUCLIDE ACTIVITIES IN SAVANNAH RIVER SITE HIGH LEVEL WASTE SLUDGE FOR ACCEPTANCE OF DEFENSE WASTE PROCESSING FACILITY GLASS IN A FEDERAL REPOSITORY  

SciTech Connect

This paper describes the results of the analyses of High Level Waste (HLW) sludge slurry samples and of the calculations necessary to decay the radionuclides to meet the reporting requirement in the Waste Acceptance Product Specifications (WAPS) [1]. The concentrations of 45 radionuclides were measured. The results of these analyses provide input for radioactive decay calculations used to project the radionuclide inventory at the specified index years, 2015 and 3115. This information is necessary to complete the Production Records at Savannah River Site's Defense Waste Processing Facility (DWPF) so that the final glass product resulting from Macrobatch 5 (MB5) can eventually be submitted to a Federal Repository. Five of the necessary input radionuclides for the decay calculations could not be measured directly due to their low concentrations and/or analytical interferences. These isotopes are Nb-93m, Pd-107, Cd-113m, Cs-135, and Cm-248. Methods for calculating these species from concentrations of appropriate other radionuclides will be discussed. Also the average age of the MB5 HLW had to be calculated from decay of Sr-90 in order to predict the initial concentration of Nb-93m. As a result of the measurements and calculations, thirty-one WAPS reportable radioactive isotopes were identified for MB5. The total activity of MB5 sludge solids will decrease from 1.6E+04 {micro}Ci (1 {micro}Ci = 3.7E+04 Bq) per gram of total solids in 2008 to 2.3E+01 {micro}Ci per gram of total solids in 3115, a decrease of approximately 700 fold. Finally, evidence will be given for the low observed concentrations of the radionuclides Tc-99, I-129, and Sm-151 in the HLW sludges. These radionuclides were reduced in the MB5 sludge slurry to a fraction of their expected production levels due to SRS processing conditions.

Bannochie, C; David Diprete, D; Ned Bibler, N

2008-12-31T23:59:59.000Z

186

WIPP WASTE MINIMIZATION PROGRAM DESCRIPTION  

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

is required by and has bee n prepared in accordance with the WIPP Hazardous Waste Facility Perm it Part 2, Permit Condition 2.4. We certify under penalty of law that this...

187

Sources, classification, and disposal of radioactive wastes: History and legal and regulatory requirements  

Science Conference Proceedings (OSTI)

This report discusses the following topics: (1) early definitions of different types (classes) of radioactive waste developed prior to definitions in laws and regulations; (2) sources of different classes of radioactive waste; (3) current laws and regulations addressing classification of radioactive wastes; and requirements for disposal of different waste classes. Relationship between waste classification and requirements for permanent disposal is emphasized; (4) federal and state responsibilities for radioactive wastes; and (5) distinctions between radioactive wastes produced in civilian and defense sectors.

Kocher, D.C.

1991-01-01T23:59:59.000Z

188

Independent Oversight Review, Waste Treatment and Immobilization Plant- December 2012  

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

Review of the Hanford Site Waste Treatment and Immobilization Plant Low Activity Waste Melter Process System Hazards Analysis Activity

189

Independent Activity Report, Office of River Protection Waste Treatment Plant and Tank Farms- February 2013  

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

Site Familiarization and Introduction of New Office of Safety and Emergency Management Evaluations Site Lead for the Office of River Protection Waste Treatment Plant and Tank Farms [HIAR-HANFORD-2013-02-25

190

Basis for National and International Low Activity and Very Low Level Waste Disposal Classifications  

Science Conference Proceedings (OSTI)

In order to determine whether the Very Low Level Waste (VLLW) category would be a viable option in the United States, European and U.S. experiences were reviewed in detail.

2012-03-30T23:59:59.000Z

191

RADIOACTIVE DEMONSTRATION OF FINAL MINERALIZED WASTE FORMS FOR HANFORD WASTE TREATMENT PLANT SECONDARY WASTE BY FLUIDIZED BED STEAM REFORMING USING THE BENCH SCALE REFORMER PLATFORM  

Science Conference Proceedings (OSTI)

The U.S. Department of Energy's Office of River Protection (ORP) is responsible for the retrieval, treatment, immobilization, and disposal of Hanford's tank waste. Currently there are approximately 56 million gallons of highly radioactive mixed wastes awaiting treatment. A key aspect of the River Protection Project (RPP) cleanup mission is to construct and operate the Waste Treatment and Immobilization Plant (WTP). The WTP will separate the tank waste into high-level and low-activity waste (LAW) fractions, both of which will subsequently be vitrified. The projected throughput capacity of the WTP LAW Vitrification Facility is insufficient to complete the RPP mission in the time frame required by the Hanford Federal Facility Agreement and Consent Order, also known as the Tri-Party Agreement (TPA), i.e. December 31, 2047. Therefore, Supplemental Treatment is required both to meet the TPA treatment requirements as well as to more cost effectively complete the tank waste treatment mission. In addition, the WTP LAW vitrification facility off-gas condensate known as WTP Secondary Waste (WTP-SW) will be generated and enriched in volatile components such as {sup 137}Cs, {sup 129}I, {sup 99}Tc, Cl, F, and SO{sub 4} that volatilize at the vitrification temperature of 1150 C in the absence of a continuous cold cap (that could minimize volatilization). The current waste disposal path for the WTP-SW is to process it through the Effluent Treatment Facility (ETF). Fluidized Bed Steam Reforming (FBSR) is being considered for immobilization of the ETF concentrate that would be generated by processing the WTP-SW. The focus of this current report is the WTP-SW. FBSR offers a moderate temperature (700-750 C) continuous method by which WTP-SW wastes can be processed irrespective of whether they contain organics, nitrates, sulfates/sulfides, chlorides, fluorides, volatile radionuclides or other aqueous components. The FBSR technology can process these wastes into a crystalline ceramic (mineral) waste form. The mineral waste form that is produced by co-processing waste with kaolin clay in an FBSR process has been shown to be as durable as LAW glass. Monolithing of the granular FBSR product is being investigated to prevent dispersion during transport or burial/storage, but is not necessary for performance. A Benchscale Steam Reformer (BSR) was designed and constructed at the SRNL to treat actual radioactive wastes to confirm the findings of the non-radioactive FBSR pilot scale tests and to qualify the waste form for applications at Hanford. BSR testing with WTP SW waste surrogates and associated analytical analyses and tests of granular products (GP) and monoliths began in the Fall of 2009, and then was continued from the Fall of 2010 through the Spring of 2011. Radioactive testing commenced in 2010 with a demonstration of Hanford's WTP-SW where Savannah River Site (SRS) High Level Waste (HLW) secondary waste from the Defense Waste Processing Facility (DWPF) was shimmed with a mixture of {sup 125/129}I and {sup 99}Tc to chemically resemble WTP-SW. Prior to these radioactive feed tests, non-radioactive simulants were also processed. Ninety six grams of radioactive granular product were made for testing and comparison to the non-radioactive pilot scale tests. The same mineral phases were found in the radioactive and non-radioactive testing.

Crawford, C.; Burket, P.; Cozzi, A.; Daniel, W.; Jantzen, C.; Missimer, D.

2012-02-02T23:59:59.000Z

192

US - Former Soviet Union environmental restoration and waste management activities, March 1994  

Science Conference Proceedings (OSTI)

The Peaceful Uses of Atomic Energy Agreement was signed between DOE and the Ministry of Atomic Energy for the Russian Federation and provides a mechanism for cooperation in research, development, and safe utilization of nuclear energy. Under the umbrella of this agreement, DOE and the former Ministry of Atomic Power and Industry signed a Memorandum of Cooperation in the areas of environmental restoration and waste management in September 1990. This document discusses the environmental situation, science and technology process, technical projects (separations, contaminant transport, waste treatment, environmental restoration), scientist exchanges, enhanced data transfer, the US-Russia industry partnership (conference, centers), and future actions.

Not Available

1994-03-01T23:59:59.000Z

193

Some activities in the United States concerning the physics aspects of actinide waste recycling  

SciTech Connect

Reactor types being considered in the United States for the purpose of actinide waste recycling are discussed briefly. The reactor types include thermal reactors operating on the 3.3 percent $sup 235$U--$sup 238$U and the $sup 233$U--$sup 232$Th fuel cycles, liquid metal fast breeder reactors, reactors fueled entirely by actinide wastes, gaseous fuel reactors, and fusion reactors. Cross section measurements in progress or planned toward providing basic data for testing the recycle concept are also discussed. (auth)

Raman, S.

1975-01-01T23:59:59.000Z

194

WASTE TREATMENT AND IMMOBILIZATION PLANT U. S. DEPARTMENT OF ENERGY OFFICE OF RIVER PROTECTION SUBMERGED BED SCRUBBER CONDENSATE DISPOSITION PROJECT - ABSTRACT # 13460  

SciTech Connect

The Hanford Waste Treatment and Immobilization Plant (WTP) will generate an off-gas treatment system secondary liquid waste stream [submerged bed scrubber (SBS) condensate], which is currently planned for recycle back to the WTP Low Activity Waste (LAW) melter. This SBS condensate waste stream is high in Tc-99, which is not efficiently captured in the vitrified glass matrix. A pre-conceptual engineering study was prepared in fiscal year 2012 to evaluate alternate flow paths for melter off-gas secondary liquid waste generated by the WTP LAW facility. This study evaluated alternatives for direct off-site disposal of this SBS without pre-treatment, which mitigates potential issues associated with recycling.

YANOCHO RM; CORCORAN C

2012-11-15T23:59:59.000Z

195

SRNL PHASE 1 ASSESSMENT OF THE WTP WASTE QUALIFICATION PROGRAM  

SciTech Connect

The Hanford Tank Waste Treatment and Immobilization Plant (WTP) Project is currently transitioning its emphasis from an engineering design and construction phase toward facility completion, start-up and commissioning. With this transition, the WTP Project has initiated more detailed assessments of the requirements that must be met during the actual processing of the Hanford Site tank waste. One particular area of interest is the waste qualification program. In general, the waste qualification program involves testing and analysis to demonstrate compliance with waste acceptance criteria, determine waste processability, and demonstrate laboratory-scale unit operations to support WTP operations. The testing and analysis are driven by data quality objectives (DQO) requirements necessary for meeting waste acceptance criteria for transfer of high-level wastes from the tank farms to the WTP, and for ensuring waste processability including proper glass formulations during processing within the WTP complex. Given the successful implementation of similar waste qualification efforts at the Savannah River Site (SRS) which were based on critical technical support and guidance from the Savannah River National Laboratory (SRNL), WTP requested subject matter experts (SMEs) from SRNL to support a technology exchange with respect to waste qualification programs in which a critical review of the WTP program could be initiated and lessons learned could be shared. The technology exchange was held on July 18-20, 2011 in Richland, Washington, and was the initial step in a multi-phased approach to support development and implementation of a successful waste qualification program at the WTP. The 3-day workshop was hosted by WTP with representatives from the Tank Operations Contractor (TOC) and SRNL in attendance as well as representatives from the US DOE Office of River Protection (ORP) and the Defense Nuclear Facility Safety Board (DNFSB) Site Representative office. The purpose of the workshop was to share lessons learned and provide a technology exchange to support development of a technically defensible waste qualification program. The objective of this report is to provide a review, from SRNL's perspective, of the WTP waste qualification program as presented during the workshop. In addition to SRNL's perspective on the general approach to the waste qualification program, more detailed insight into the specific unit operations presented by WTP during the workshop is provided. This report also provides a general overview of the SRS qualification program which serves as a basis for a comparison between the two programs. Recommendations regarding specific steps are made based on the review and SRNL's lessons learned from qualification of SRS low-activity waste (LAW) and high-level waste (HLW) to support maturation of the waste qualification program leading to WTP implementation.

Peeler, D.; Hansen, E.; Herman, C.; Marra, S.; Wilmarth, B.

2012-03-06T23:59:59.000Z

196

EVALUATION OF THE INTEGRATED SOLUBILITY MODEL, A GRADED APPROACH FOR PREDICTING PHASE DISTRIBUTION IN HANFORD TANK WASTE  

SciTech Connect

The mission of the DOE River Protection Project (RPP) is to store, retrieve, treat and dispose of Hanford's tank waste. Waste is retrieved from the underground tanks and delivered to the Waste Treatment and Immobilization Plant (WTP). Waste is processed through a pretreatment facility where it is separated into low activity waste (LAW), which is primarily liquid, and high level waste (HLW), which is primarily solid. The LAW and HLW are sent to two different vitrification facilities and glass canisters are then disposed of onsite (for LAW) or shipped off-site (for HLW). The RPP mission is modeled by the Hanford Tank Waste Operations Simulator (HTWOS), a dynamic flowsheet simulator and mass balance model that is used for mission analysis and strategic planning. The integrated solubility model (ISM) was developed to improve the chemistry basis in HTWOS and better predict the outcome of the RPP mission. The ISM uses a graded approach to focus on the components that have the greatest impact to the mission while building the infrastructure for continued future improvement and expansion. Components in the ISM are grouped depending upon their relative solubility and impact to the RPP mission. The solubility of each group of components is characterized by sub-models of varying levels of complexity, ranging from simplified correlations to a set of Pitzer equations used for the minimization of Gibbs Energy.

PIERSON KL; BELSHER JD; SENIOW KR

2012-10-19T23:59:59.000Z

197

RADIOACTIVE DEMONSTRATION OF MINERALIZED WASTE FORMS MADE FROM HANFORD LOW ACTIVITY WASTE (TANK SX-105, TANK AN-103, AND AZ-101/102) BY FLUIDIZED BED STEAM REFORMATION (FBSR)  

Science Conference Proceedings (OSTI)

Fluidized Bed Steam Reforming (FBSR) is a robust technology for the immobilization of a wide variety of radioactive wastes. Applications have been tested at the pilot scale for the high sodium, sulfate, halide, organic and nitrate wastes at the Hanford site, the Idaho National Laboratory (INL), and the Savannah River Site (SRS). Due to the moderate processing temperatures, halides, sulfates, and technetium are retained in mineral phases of the feldspathoid family (nepheline, sodalite, nosean, carnegieite, etc). The feldspathoid minerals bind the contaminants such as Tc-99 in cage (sodalite, nosean) or ring (nepheline) structures to surrounding aluminosilicate tetrahedra in the feldspathoid structures. The granular FBSR mineral waste form that is produced has a comparable durability to LAW glass based on the short term PCT testing in this study, the INL studies, SPFT and PUF testing from previous studies as given in the columns in Table 1-3 that represent the various durability tests. Monolithing of the granular product was shown to be feasible in a separate study. Macro-encapsulating the granular product provides a decrease in leaching compared to the FBSR granular product when the geopolymer is correctly formulated.

Jantzen, C.; Crawford, C.; Bannochie, C.; Burket, P.; Cozzi, A.; Daniel, G.; Hall, H.; Miller, D.; Missimer, D.; Nash, C.; Williams, F.

2013-09-18T23:59:59.000Z

198

State of Nevada, Agency for Nuclear Projects/Nuclear Waste Project Office narrative report, July 1--September 30, 1991  

Science Conference Proceedings (OSTI)

The Agency for Nuclear Projects/Nuclear Waste Project Office (NWPO) is the State of Nevada agency designated by State law to monitor and oversee US Department of Energy (DOE) activities relative to the possible siting, construction, operation and closure of a high-level nuclear waste repository at Yucca Mountain and to carry out the State of Nevada`s responsibilities under the Nuclear Waste Policy Act of 1982. During the reporting period the NWPO continued to work toward the five objectives designed to implement the Agency`s oversight responsibilities. (1) Assure that the health and safety of Nevada`s citizens are adequately protected with regard to any federal high-level radioactive waste program within the State. (2) Take the responsibilities and perform the duties of the State of Nevada as described in the Nuclear Waste Policy Act of 1982 (Public Law 97-425) and the Nuclear Waste Policy Amendments Act of 1987. (3) Advise the Governor, the State Commission on Nuclear Projects and the Nevada State Legislature on matters concerning the potential disposal of high-level radioactive waste in the State. (4) Work closely and consult with affected local governments and State agencies. (5) Monitor and evaluate federal planning and activities regarding high-level radioactive waste disposal. Plan and conduct independent State studies regarding the proposed repository.

NONE

1991-12-31T23:59:59.000Z

199

Waste Isolation Pilot Plant Activites  

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

DENVER, CO DENVER, CO WASTE ISOLATION PILOT PLANT ACTIVITIES ACTIVITIES O.W. EATON MANAGER, EXTERNAL EMERGENCY MANAGEMENT OPENING OF NEW ROUTES COMPLIANCE WITH PUBLIC LAW 102 579 WIPP LANDWITHDRAWL 102-579 WIPP LANDWITHDRAWL ACT OF 1992 1082 EMERGENCY PERSONNEL TRAINED IN 2010 *MERRTT 1082 EMERGENCY PERSONNEL TRAINED IN 2010 MERRTT *INCIDENT COMMAND SYSTEM *HOSPITAL PREPAREDNESS *HOSPITAL PREPAREDNESS *MEDICAL EXAMINER DISPATCHER (BETA) *DISPATCHER (BETA) RADIOLOGICAL TRAINING RADIOLOGICAL TRAINING FOR FOR FOR FOR HOSPITAL PERSONNEL HOSPITAL PERSONNEL Based on FEMA Course G-346 iNTRODUCTION 4 Hazardous Materials Accidents Part 1 WIPP EXTERNAL EMERGENCY MANAGEMENT EXERCISES CONDUCTED E ercise Location Date Exercise Location Date TRANSAX 90 Colorado Springs, Colorado November 8, 1990 1

200

River Protection Project (RPP) Immobilized Low Activity Waste (ILAW) Disposal Plan  

Science Conference Proceedings (OSTI)

This document replaces HNF-1517, Rev 2 which is deleted. It incorporates updates to reflect changes in programmatic direction associated with the vitrification plant contract change and associated DOE/ORP guidance. In addition it incorporates the cancellation of Project W-465, Grout Facility, and the associated modifications to Project W-520, Immobilized High-Level Waste Disposal Facility. It also includes document format changes and section number modifications consistent with CH2M HILL Hanford Group, Inc. procedures.

BRIGGS, M.G.

2000-09-22T23:59:59.000Z

Note: This page contains sample records for the topic "activity waste law" 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

NATURE OF RADIOACTIVE WASTES  

SciTech Connect

The integrated processes of nuclear industry are considered to define the nature of wastes. Processes for recovery and preparation of U and Th fuels produce wastes containing concentrated radioactive materials which present problems of confinement and dispersal. Fundamentals of waste treatment are considered from the standpoint of processes in which radioactive materials become a factor such as naturally occurring feed materials, fission products, and elements produced by parasitic neutron capture. In addition, the origin of concentrated fission product wastes is examined, as well as characteristics of present wastes and the level of fission products in wastes. Also, comments are included on high-level wastes from processes other than solvent extraction, active gaseous wastes, and low- to intermediate-level liquid wastes. (J.R.D.)

Culler, F.L. Jr.

1959-01-26T23:59:59.000Z

202

Semi-continuous anaerobic co-digestion of thickened waste activated sludge and fat, oil and grease  

SciTech Connect

Highlights: > Co-digestion of thickened waste activated sludge (TWAS) with fat, oil and grease (FOG). > Co-digestion of TWAS and FOG at 64% VS increased biogas production by 137%. > FOG addition ratio at 74% of total VS caused inhibition of the anaerobic digestion process. > Micronutrients addition did not significantly improve the biogas production and digestion stabilization. - Abstract: Co-digestion of thickened waste activated sludge (TWAS) and fat, oil and grease (FOG) was conducted semi-continuously under mesophilic conditions. The results showed that daily methane yield at the steady state was 598 L/kg VS{sub added} when TWAS and FOG (64% of total VS) were co-digested, which was 137% higher than that obtained from digestion of TWAS alone. The biogas composition was stabilized at a CH{sub 4} and CO{sub 2} content of 66.8% and 29.5%, respectively. Micronutrients added to co-digestion did not improve the biogas production and digestion stabilization. With a higher addition of FOG (74% of total VS), the digester initially failed but was slowly self-recovered; however, the methane yield was only about 50% of a healthy reactor with the same organic loading rate.

Wan Caixia; Zhou Quancheng; Fu Guiming [Department of Food, Agricultural, and Biological Engineering, Ohio State University/Ohio Agricultural Research and Development Center, 1680 Madison Ave., Wooster, OH 44691-4096 (United States); Li Yebo, E-mail: li.851@osu.edu [Department of Food, Agricultural, and Biological Engineering, Ohio State University/Ohio Agricultural Research and Development Center, 1680 Madison Ave., Wooster, OH 44691-4096 (United States)

2011-08-15T23:59:59.000Z

203

Liquidus Temperature Studies for High Level Nuclear Waste Glasses  

Science Conference Proceedings (OSTI)

... of Fluidized Bed Steam Reforming (FBSR) with Hanford Low Activity Wastes ... Level Waste at the Defense Waste Processing Facility through Sludge Batch 7b.

204

Sodalite-Based Forms for Wastes Containing Actinides and Halides  

Science Conference Proceedings (OSTI)

... of Fluidized Bed Steam Reforming (FBSR) with Hanford Low Activity Wastes ... Level Waste at the Defense Waste Processing Facility through Sludge Batch 7b.

205

Advanced Ceramic Waste Forms for the Immobilisation of ...  

Science Conference Proceedings (OSTI)

... of Fluidized Bed Steam Reforming (FBSR) with Hanford Low Activity Wastes ... Level Waste at the Defense Waste Processing Facility through Sludge Batch 7b.

206

NEXT GENERATION MELTER(S) FOR VITRIFICATION OF HANFORD WASTE STATUS AND DIRECTION  

SciTech Connect

Vitrification technology has been selected to treat high-level waste (HLW) at the Hanford Site, the West Valley Demonstration Project and the Savannah River Site (SRS), and low activity waste (LAW) at Hanford. In addition, it may potentially be applied to other defense waste streams such as sodium bearing tank waste or calcine. Joule-heated melters (already in service at SRS) will initially be used at the Hanford Site's Waste Treatment and Immobilization Plant (WTP) to vitrify tank waste fractions. The glass waste content and melt/production rates at WTP are limited by the current melter technology. Significant reductions in glass volumes and mission life are only possible with advancements in melter technology coupled with new glass formulations. The Next Generation Melter (NGM) program has been established by the U.S. Department of Energy's (DOE's), Environmental Management Office of Waste Processing (EM-31) to develop melters with greater production capacity (absolute glass throughput rate) and the ability to process melts with higher waste fractions. Advanced systems based on Joule-Heated Ceramic Melter (JHCM) and Cold Crucible Induction Melter (CCIM) technologies will be evaluated for HLW and LAW processing. Washington River Protection Solutions (WRPS), DOE's tank waste contractor, is developing and evaluating these systems in cooperation with EM-31, national and university laboratories, and corporate partners. A primary NGM program goal is to develop the systems (and associated flowsheets) to Technology Readiness Level 6 by 2016. Design and testing are being performed to optimize waste glass process envelopes with melter and balance of plant requirements. A structured decision analysis program will be utilized to assess the performance of the competing melter technologies. Criteria selected for the decision analysis program will include physical process operations, melter performance, system compatibility and other parameters.

RAMSEY WG; GRAY MF; CALMUS RB; EDGE JA; GARRETT BG

2011-01-13T23:59:59.000Z

207

Implementing waste minimization at an active plutonium processing facility: Successes and progress at technical area (TA) -55 of the Los Alamos National Laboratory  

SciTech Connect

The Los Alamos National Laboratory has ongoing national security missions that necessitate increased plutonium processing. The bulk of this activity occurs at Technical Area -55 (TA-55), the nations only operable plutonium facility. TA-55 has developed and demonstrated a number of technologies that significantly minimize waste generation in plutonium processing (supercritical CO{sub 2}, Mg(OH){sub 2} precipitation, supercritical H{sub 2}O oxidation, WAND), disposition of excess fissile materials (hydride-dehydride, electrolytic decontamination), disposition of historical waste inventories (salt distillation), and Decontamination & Decommissioning (D&D) of closed nuclear facilities (electrolytic decontamination). Furthermore, TA-55 is in the process of developing additional waste minimization technologies (molten salt oxidation, nitric acid recycle, americium extraction) that will significantly reduce ongoing waste generation rates and allow volume reduction of existing waste streams. Cost savings from reduction in waste volumes to be managed and disposed far exceed development and deployment costs in every case. Waste minimization is also important because it reduces occupational exposure to ionizing radiation, risks of transportation accidents, and transfer of burdens from current nuclear operations to future generations.

Balkey, J.J.; Robinson, M.A.; Boak, J.

1997-12-01T23:59:59.000Z

208

Uniform Laws and Regulations  

Science Conference Proceedings (OSTI)

Page 1. Page 2. Uniform Laws and Regulations in the areas of legal metrology and engine fuel quality as adopted by the ...

2011-09-13T23:59:59.000Z

209

Uniform Laws and Regulations  

Science Conference Proceedings (OSTI)

Page 1. Uniform Laws and Regulations in the areas of legal metrology and engine fuel quality as adopted by the 96th National Conference on ...

2012-07-12T23:59:59.000Z

210

Systems engineering management and implementation plan for Project W-465, immobilized low-activity waste plan  

SciTech Connect

The Systems Engineering Management and Implementation Plan (SEMIP) for TWRS Project W-465 describes the project implementation of the Tank Waste Remediation System Systems Engineering Management Plan (TWRS SEMP), Rev. 1. The SEMIP outlines systems engineering (SE) products and processes to be used by the project for technical baseline development. A formal graded approach is used to determine the products necessary for requirements, design, and operational baseline completion. SE management processes are defined, and roles and responsibilities for management processes and major technical baseline elements are documented.

Latray, D.A.

1998-05-15T23:59:59.000Z

211

FLUIDIZED BED STEAM REFORMED MINERAL WASTE FORMS: CHARACTERIZATION AND DURABILITY TESTING  

SciTech Connect

Fluidized Bed Steam Reforming (FBSR) is being considered as a potential technology for the immobilization of a wide variety of high sodium low activity wastes (LAW) such as those existing at the Hanford site, at the Idaho National Laboratory (INL), and the Savannah River Site (SRS). The addition of clay, charcoal, and a catalyst as co-reactants with the waste denitrates the aqueous wastes and forms a granular mineral waste form that can subsequently be made into a monolith for disposal if necessary. The waste form produced is a multiphase mineral assemblage of Na-Al-Si (NAS) feldspathoid minerals with cage and ring structures and iron bearing spinel minerals. The mineralization occurs at moderate temperatures between 650-750 C in the presence of superheated steam. The cage and ring structured feldspathoid minerals atomically bond radionuclides like Tc-99 and Cs-137 and anions such as SO{sub 4}, I, F, and Cl. The spinel minerals stabilize Resource Conservation and Recovery Act (RCRA) hazardous species such as Cr and Ni. Granular mineral waste forms were made from (1) a basic Hanford Envelope A low activity waste (LAW) simulant and (2) an acidic INL simulant commonly referred to as sodium bearing waste (SBW) in pilot scale facilities at the Science Applications International Corporation (SAIC) Science and Technology Applications Research (STAR) facility in Idaho Falls, ID. The FBSR waste forms were characterized and the durability tested via ASTM C1285 (Product Consistency Test), the Environmental Protection Agency (EPA) Toxic Characteristic Leaching Procedure (TCLP), and the Single Pass Flow Through (SPFT) test. The results of the SPFT testing and the activation energies for dissolution are discussed in this study.

Jantzen, C; Troy Lorier, T; John Pareizs, J; James Marra, J

2006-12-06T23:59:59.000Z

212

FLUIDIZED BED STEAM REFORMED MINERAL WASTE FORMS: CHARACTERIZATION AND DURABILITY TESTING  

SciTech Connect

Fluidized Bed Steam Reforming (FBSR) is being considered as a potential technology for the immobilization of a wide variety of high sodium low activity wastes (LAW) such as those existing at the Hanford site, at the Idaho National Laboratory (INL), and the Savannah River Site (SRS). The addition of clay, charcoal, and a catalyst as co-reactants with the waste denitrates the aqueous wastes and forms a granular mineral waste form that can subsequently be made into a monolith for disposal if necessary. The waste form produced is a multiphase mineral assemblage of Na-Al-Si (NAS) feldspathoid minerals with cage and ring structures and iron bearing spinel minerals. The mineralization occurs at moderate temperatures between 650-750 C in the presence of superheated steam. The cage and ring structured feldspathoid minerals atomically bond radionuclides like Tc-99 and Cs-137 and anions such as SO4, I, F, and Cl. The spinel minerals stabilize Resource Conservation and Recovery Act (RCRA) hazardous species such as Cr and Ni. Granular mineral waste forms were made from (1) a basic Hanford Envelope A low-activity waste (LAW) simulant and (2) an acidic INL simulant commonly referred to as sodium bearing waste (SBW) in pilot scale facilities at the Science Applications International Corporation (SAIC) Science and Technology Applications Research (STAR) facility in Idaho Falls, ID. The FBSR waste forms were characterized and the durability tested via ASTM C1285 (Product Consistency Test), the Environmental Protection Agency (EPA) Toxic Characteristic Leaching Procedure (TCLP), and the Single Pass Flow Through (SPFT) test. The results of the SPFT testing and the activation energies for dissolution are discussed in this study.

Jantzen, C; Troy Lorier, T; John Pareizs, J; James Marra, J

2007-03-31T23:59:59.000Z

213

Waste Clean Up 5  

Science Conference Proceedings (OSTI)

... deployment and clean-up activities of robot arms into a nuclear contaminated pit at the opening of waste storage tank C-106 at Hanford, Washington ...

2011-08-30T23:59:59.000Z

214

Laws DOE Administers | Department of Energy  

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

Laws DOE Administers Laws DOE Administers Laws DOE Administers The Department of Energy's (DOE) overarching mission is to advance the national, economic, and energy security of the United States; to promote scientific and technological innovation in support of that mission; and to ensure the environmental cleanup of the national nuclear weapons complex. Laws passed by Congress and signed by the President both define DOE's authorities and set forth DOE's responsibilities. Additionally, a number of Executive Orders issued by the President play a central role in guiding DOE's activities. In the space below, we have provided links to key statutes and executive orders which affect the Department of Energy. For every law, we provide a link to the United States Code (U.S.C.) , which is the codification by

215

International fuel cycle and waste management technology exchange activities sponsored by the United States Department of Energy: FY 1982 evaluation report  

SciTech Connect

In FY 1982, DOE and DOE contractor personnel attended 40 international symposia and conferences on fuel reprocessing and waste management subjects. The treatment of high-level waste was the topic most often covered in the visits, with geologic disposal and general waste management also being covered in numerous visits. Topics discussed less frequently inlcude TRU/LLW treatment, airborne waste treatment, D and D, spent fuel handling, and transportation. The benefits accuring to the US from technology exchange activities with other countries are both tangible, e.g., design of equipment, and intangible, e.g., improved foreign relations. New concepts initiated in other countries, particularly those with sizable nuclear programs, are beginning to appear in US efforts in growing numbers. The spent fuel dry storage concept originating in the FRG is being considered at numerous sites. Similarly, the German handling and draining concepts for the joule-heated ceramic melter used to vitrify wastes are being incorporated in US designs. Other foreigh technologies applicable in the US include the slagging incinerator (Belgium), the SYNROC waste form (Australia), the decontamination experience gained in decommissioning the Eurochemic reprocessing plant (Belgium), the engineered surface storage of low- and intermediate-level waste (Belgium, FRG, France), the air-cooled storage of vitrified high-level waste (France, UK), waste packaging (Canada, FRG, Sweden), disposal in salt (FRG), disposal in granite (Canada, Sweden), and sea dumping (UK, Belgium, The Netherlands, Switzerland). These technologies did not necessarily originated or have been tried in the US but for various reasons are now being applied and extended in other countries. This growing nuclear technological base in other countires reduces the number of technology avenues the US need follow to develop a solid nuclear power program.

Lakey, L.T.; Harmon, K.M.

1983-02-01T23:59:59.000Z

216

Idaho Waste Vitrification Facilities Project Vitrified Waste Interim Storage Facility  

SciTech Connect

This feasibility study report presents a draft design of the Vitrified Waste Interim Storage Facility (VWISF), which is one of three subprojects of the Idaho Waste Vitrification Facilities (IWVF) project. The primary goal of the IWVF project is to design and construct a treatment process system that will vitrify the sodium-bearing waste (SBW) to a final waste form. The project will consist of three subprojects that include the Waste Collection Tanks Facility, the Waste Vitrification Facility (WVF), and the VWISF. The Waste Collection Tanks Facility will provide for waste collection, feed mixing, and surge storage for SBW and newly generated liquid waste from ongoing operations at the Idaho Nuclear Technology and Engineering Center. The WVF will contain the vitrification process that will mix the waste with glass-forming chemicals or frit and turn the waste into glass. The VWISF will provide a shielded storage facility for the glass until the waste can be disposed at either the Waste Isolation Pilot Plant as mixed transuranic waste or at the future national geological repository as high-level waste glass, pending the outcome of a Waste Incidental to Reprocessing determination, which is currently in progress. A secondary goal is to provide a facility that can be easily modified later to accommodate storage of the vitrified high-level waste calcine. The objective of this study was to determine the feasibility of the VWISF, which would be constructed in compliance with applicable federal, state, and local laws. This project supports the Department of Energy’s Environmental Management missions of safely storing and treating radioactive wastes as well as meeting Federal Facility Compliance commitments made to the State of Idaho.

Bonnema, Bruce Edward

2001-09-01T23:59:59.000Z

217

Solid and hazardous energy wastes: synfuels. I. Review of research activities. [US DOE- and US EPA-sponsored research  

DOE Green Energy (OSTI)

Current chemical and biological research sponsored by the Department of Energy (DOE) and the Environmental Protection Agency (EPA) on solid, liquid, and gaseous waste streams from coal-conversion and oil-shale technologies is summarized. Brief descriptions, including the objectives, current activities, and future plans (if any), of ongoing projects were obtained from the principal investigators, where possible, or from current publications, progress reports, or scope-of-work sheets from DOE and EPA laboratories. References to publications that have resulted from the various research projects are included where applicable. Additional references to work on hazardous and solid synfuel waste are included in the appendixes, drawn from computerized bibliographic searches of Chemical Abstracts and the National Technical Information Service (NTIS). Appendix I contains information found in the NTIS search from 1974 to 1980, which includes the title, author(s), place of investigation, NTIS ordering number, date of publication, and the actual abstracts. Appendix II contains information found in the Chemical Abstracts search from 1973 to 1980, which includes the title; author(s); journal title, volume, and number; chemical abstracts numbers; descriptors and identifiers based on the given title and/or abstract; and date of publication.

Fradkin, L.; Surles, T.; DeCarlo, V.

1981-05-01T23:59:59.000Z

218

Excess Weapons Plutonium Disposition: Plutonium Packaging, Storage and Transportation and Waste Treatment, Storage and Disposal Activities  

SciTech Connect

A fifth annual Excess Weapons Plutonium Disposition meeting organized by Lawrence Livermore National Laboratory (LLNL) was held February 16-18, 2004, at the State Education Center (SEC), 4 Aerodromnya Drive, St. Petersburg, Russia. The meeting discussed Excess Weapons Plutonium Disposition topics for which LLNL has the US Technical Lead Organization responsibilities. The technical areas discussed included Radioactive Waste Treatment, Storage, and Disposal, Plutonium Oxide and Plutonium Metal Packaging, Storage and Transportation and Spent Fuel Packaging, Storage and Transportation. The meeting was conducted with a conference format using technical presentations of papers with simultaneous translation into English and Russian. There were 46 Russian attendees from 14 different Russian organizations and six non-Russian attendees, four from the US and two from France. Forty technical presentations were made. The meeting agenda is given in Appendix B and the attendance list is in Appendix C.

Jardine, L J; Borisov, G B

2004-07-21T23:59:59.000Z

219

Tank waste remediation system retrieval and disposal mission initial updated baseline summary  

SciTech Connect

This document provides a summary of the Tank Waste Remediation System (TWRS) Retrieval and Disposal Mission Initial Updated Baseline (scope, schedule, and cost), developed to demonstrate Readiness-to-Proceed (RTP) in support of the TWRS Phase 1B mission. This Updated Baseline is the proposed TWRS plan to execute and measure the mission work scope. This document and other supporting data demonstrate that the TWRS Project Hanford Management Contract (PHMC) team is prepared to fully support Phase 1B by executing the following scope, schedule, and cost baseline activities: Deliver the specified initial low-activity waste (LAW) and high-level waste (HLW) feed batches in a consistent, safe, and reliable manner to support private contractors` operations starting in June 2002; Deliver specified subsequent LAW and HLW feed batches during Phase 1B in a consistent, safe, and reliable manner; Provide for the interim storage of immobilized HLW (IHLW) products and the disposal of immobilized LAW (ILAW) products generated by the private contractors; Provide for disposal of byproduct wastes generated by the private contractors; and Provide the infrastructure to support construction and operations of the private contractors` facilities.

Swita, W.R.

1998-01-09T23:59:59.000Z

220

Standard for Communicating Waste Characterization and DOT Hazard Classification Requirements for Low Specific Activity Materials and Surface Contaminated Objects  

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

STD-5507-2013 STD-5507-2013 February 2013 DOE STANDARD Standard for Communicating Waste Characterization and DOT Hazard Classification Requirements for Low Specific Activity Materials and Surface Contaminated Objects [This Standard describes acceptable, but not mandatory means for complying with requirements. Standards are not requirements documents and are not to be construed as requirements in any audit or appraisal for compliance with associated rule or directives.] U.S. Department of Energy SAFT Washington, D.C. 20585 Distribution Statement: A. Approved for public release; distribution is unlimited This document has been reproduced directly from the best available copy. Available to DOE and DOE contractors from ES&H Technical Information Services,

Note: This page contains sample records for the topic "activity waste law" 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

Law and technologyKeeping track of telecommunications surveillance  

Science Conference Proceedings (OSTI)

The creation of a statistical index of U.S. telecommunications surveillance activities and their results will benefit both civil liberties and law enforcement.

Paul M. Schwartz

2009-09-01T23:59:59.000Z

222

Radioactive Waste Management Basis  

SciTech Connect

The purpose of this Radioactive Waste Management Basis is to describe the systematic approach for planning, executing, and evaluating the management of radioactive waste at LLNL. The implementation of this document will ensure that waste management activities at LLNL are conducted in compliance with the requirements of DOE Order 435.1, Radioactive Waste Management, and the Implementation Guide for DOE Manual 435.1-1, Radioactive Waste Management Manual. Technical justification is provided where methods for meeting the requirements of DOE Order 435.1 deviate from the DOE Manual 435.1-1 and Implementation Guide.

Perkins, B K

2009-06-03T23:59:59.000Z

223

Industrial Solid Waste Landfill Facilities (Ohio) | Department of Energy  

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

Industrial Solid Waste Landfill Facilities (Ohio) Industrial Solid Waste Landfill Facilities (Ohio) Industrial Solid Waste Landfill Facilities (Ohio) < Back Eligibility Agricultural Industrial Investor-Owned Utility Municipal/Public Utility Rural Electric Cooperative State/Provincial Govt Utility Program Info State Ohio Program Type Environmental Regulations Provider Ohio Environmental Protection Agency This chapter of the law establishes that the Ohio Environmental Protection Agency provides rules and guidelines for landfills, including those that treat waste to generate electricity. The law provides information for permitting, installing, maintaining, monitoring, and closing landfills. There are no special provisions or exemptions for landfills used to generate electricity. However, the law does apply to landfills that do

224

Iron Phosphate Glass-Containing Hanford Waste Simulant  

SciTech Connect

Resolution of the nation’s high level tank waste legacy requires the design, construction, and operation of large and technically complex one-of-a-kind processing waste treatment and vitrification facilities. While the ultimate limits for waste loading and melter efficiency have yet to be defined or realized, significant reductions in glass volumes for disposal and mission life may be possible with advancements in melter technologies and/or glass formulations. This test report describes the experimental results from a small-scale test using the research scale melter (RSM) at Pacific Northwest National Laboratory (PNNL) to demonstrate the viability of iron phosphate-based glass with a selected waste composition that is high in sulfates (4.37 wt% SO3). The primary objective of the test was to develop data to support a cost-benefit analysis as related to the implementation of phosphate-based glasses for Hanford low activity waste (LAW) and/or other high-level waste streams within the U.S. Department of Energy complex. The testing was performed by PNNL and supported by Idaho National Laboratory, Savannah River National Laboratory, and Mo-Sci Corporation.

Sevigny, Gary J.; Kimura, Marcia L.; Fischer, Christopher M.; Schweiger, Michael J.; Kim, Dong-Sang

2011-08-01T23:59:59.000Z

225

Iron Phosphate Glass-Containing Hanford Waste Simulant  

SciTech Connect

Resolution of the nation's high-level tank waste legacy requires the design, construction, and operation of large and technically complex one-of-a-kind processing waste treatment and vitrification facilities. While the ultimate limits for waste loading and melter efficiency have yet to be defined or realized, significant reductions in glass volumes for disposal and mission life may be possible with advancements in melter technologies and/or glass formulations. This test report describes the experimental results from a small-scale test using the research-scale melter (RSM) at Pacific Northwest National Laboratory (PNNL) to demonstrate the viability of iron-phosphate-based glass with a selected waste composition that is high in sulfate (4.37 wt% SO3). The primary objective of the test was to develop data to support a cost-benefit analysis related to the implementation of phosphate-based glasses for Hanford low-activity waste (LAW) and/or other high-level waste streams within the U.S. Department of Energy complex. The testing was performed by PNNL and supported by Idaho National Laboratory, Savannah River National Laboratory, Missouri University of Science and Technology, and Mo-Sci Corporation.

Sevigny, Gary J.; Kimura, Marcia L.; Fischer, Christopher M.; Schweiger, M. J.; Rodriguez, Carmen P.; Kim, Dong-Sang; Riley, Brian J.

2012-01-18T23:59:59.000Z

226

Iron Phosphate Glass-Containing Hanford Waste Simulant  

SciTech Connect

Resolution of the nation's high-level tank waste legacy requires the design, construction, and operation of large and technically complex one-of-a-kind processing waste treatment and vitrification facilities. While the ultimate limits for waste loading and melter efficiency have yet to be defined or realized, significant reductions in glass volumes for disposal and mission life may be possible with advancements in melter technologies and/or glass formulations. This test report describes the experimental results from a small-scale test using the research-scale melter (RSM) at Pacific Northwest National Laboratory (PNNL) to demonstrate the viability of iron-phosphate-based glass with a selected waste composition that is high in sulfate (4.37 wt% SO3). The primary objective of the test was to develop data to support a cost-benefit analysis related to the implementation of phosphate-based glasses for Hanford low-activity waste (LAW) and/or other high-level waste streams within the U.S. Department of Energy complex. The testing was performed by PNNL and supported by Idaho National Laboratory, Savannah River National Laboratory, Missouri University of Science and Technology, and Mo-Sci Corporation.

Sevigny, Gary J.; Kimura, Marcia L.; Fischer, Christopher M.; Schweiger, M. J.; Rodriguez, Carmen P.; Kim, Dong-Sang; Riley, Brian J.

2012-01-18T23:59:59.000Z

227

Next Generation Waste Glass Melters  

activities as described in EM Tank Waste R&D Plan. Melter project in support of this activity. Facets of WTP processing being investigated/enhanced include:

228

Solid Waste Disposal, Hazardous Waste Management Act, Underground Storage  

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

Disposal, Hazardous Waste Management Act, Underground Disposal, Hazardous Waste Management Act, Underground Storage Act (Tennessee) Solid Waste Disposal, Hazardous Waste Management Act, Underground Storage Act (Tennessee) < Back Eligibility Agricultural Commercial Construction Developer Fuel Distributor Industrial Installer/Contractor Institutional Investor-Owned Utility Local Government Municipal/Public Utility Nonprofit Rural Electric Cooperative Schools State/Provincial Govt Systems Integrator Tribal Government Utility Program Info State Tennessee Program Type Environmental Regulations Siting and Permitting Provider Tennessee Department Of Environment and Conservation The Solid Waste Disposal Laws and Regulations are found in Tenn. Code 68-211. These rules are enforced and subject to change by the Public Waste Board (PWB), which is established by the Division of Solid and Hazardous

229

Underground waste barrier structure  

DOE Patents (OSTI)

Disclosed is an underground waste barrier structure that consists of waste material, a first container formed of activated carbonaceous material enclosing the waste material, a second container formed of zeolite enclosing the first container, and clay covering the second container. The underground waste barrier structure is constructed by forming a recessed area within the earth, lining the recessed area with a layer of clay, lining the clay with a layer of zeolite, lining the zeolite with a layer of activated carbonaceous material, placing the waste material within the lined recessed area, forming a ceiling over the waste material of a layer of activated carbonaceous material, a layer of zeolite, and a layer of clay, the layers in the ceiling cojoining with the respective layers forming the walls of the structure, and finally, covering the ceiling with earth.

Saha, Anuj J. (Hamburg, NY); Grant, David C. (Gibsonia, PA)

1988-01-01T23:59:59.000Z

230

Strip Mine Law (Missouri)  

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

This law authorizes the Land Reclamation Commission of the Department of Natural Resources to adopt and promulgate rules and regulations pertaining to strip mining of coal and reclamation, review...

231

Causal Newton Gravity Law  

E-Print Network (OSTI)

The equations of the relativistic causal Newton gravity law for the planets of the solar system are studied in the approximation when the Sun rests at the coordinates origin and the planets do not iteract between each other.

Yury M. Zinoviev

2012-01-17T23:59:59.000Z

232

Potential Conservation Laws  

E-Print Network (OSTI)

We prove that potential conservation laws have characteristics depending only on local variables if and only if they are induced by local conservation laws. Therefore, characteristics of pure potential conservation laws have to essentially depend on potential variables. This statement provides a significant generalization of results of the recent paper by Bluman, Cheviakov and Ivanova [J. Math. Phys., 2006, V.47, 113505]. Moreover, we present extensions to gauged potential systems, Abelian and general coverings and general foliated systems of differential equations. An example illustrating possible applications of proved statements is considered. A special version of the Hadamard lemma for fiber bundles and the notions of weighted jet spaces are proposed as new tools for the investigation of potential conservation laws.

Michael Kunzinger; Roman O. Popovych

2008-03-07T23:59:59.000Z

233

Transmittal of Immobilized Low Activity Waste (ILAW) Disposal Preliminary RAM Analysis Report (formerly PLG-1412)  

Science Conference Proceedings (OSTI)

This report presents the results of the preliminary reliability, availability, and maintainability analysis of operations at the ILAW Disposal Facility, Project W-520, to be performed during Phase I activities in support of the WTP

CALMUS, R.B.

2002-12-04T23:59:59.000Z

234

Memorandum of Understanding Between the United States Department of Energy and the Washington State Department of Ecology for Development of the Hanford Site Tank Closure and Waste Management EIS ("TC&WM EIS")  

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

THE THE UNITED STATES DEPARTMENT OF ENERGY, AND THE WASHINGTON STATE DEPARTMENT OF ECOLOGY, FOR DEVELOPMENT OF THE HANFORD SITE TANK CLOSURE AND WASTE MANAGEMENT EIS ("TC&WM EIS") I. INTRODUCTION The U.S. Department of Energy (DOE) and Washington State Department of Ecology (Ecology) have mutual responsibilities for accomplishing cleanup of the Hanford Site as well as continuing ongoing waste management activities consistent with applicable federal and state laws and regulations. The Hanford Federal Facility Agreement and Consent Order (otherwise called the "Tri-Party Agreement", or "TPA") contains various enforceable milestones that apply to tank waste management activities. DOE is also required to comply with applicable requirements of

235

WIPP WASTE MINIMIZATION PROGRAM DESCRIPTION  

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

Carlsbad, New Mexico 8822 Carlsbad, New Mexico 8822 1 NOV 2 3 2011 Mr. John Kieling , Acting Bureau Chief Hazardous Waste Bureau New Mexico Environme nt Department 2905 Rodeo Park Drive East, Building 1 Santa Fe, New Mexico 87505-6303 Subject: Transmittal of the Waste Isolation Pilot Plant Annual Waste Minimization Report Dear Mr. Kieling: This letter provides the submittal of the Waste Isolation Pilot Plant Annual Waste Minimization Report. This report is required by and has bee n prepared in accordance with the WIPP Hazardous Waste Facility Perm it Part 2, Permit Condition 2.4. We certify under penalty of law that this document and all enclosures were prepared under our direction or supervision according to a system designed to assure that qualified personnel properly gather and evaluate the information submitted

236

Sulfur polymer stabilization/solidification (SPSS) treatment of mixed waste mercury recovered from environmental restoration activities at BNL  

SciTech Connect

Over 1,140 yd{sup 3} of radioactively contaminated soil containing toxic mercury (Hg) and several liters of mixed-waste elemental mercury were generated during a Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) removal action at Brookhaven National Laboratory (BNL). The US Department of Energy's (DOE) Office of Science and Technology Mixed Waste Focus Area (DOE MWFA) is sponsoring a comparison of several technologies that may be used to treat these wastes and similar wastes at BNL and other sites across the DOE complex. This report describes work conducted at BNL on the application and pilot-scale demonstration of the newly developed Sulfur Polymer Stabilization/Solidification (SPSS) process for treatment of contaminated mixed-waste soils containing high concentrations ({approximately} 5,000 mg/L) of mercury and liquid elemental mercury. BNL's SPSS (patent pending) process chemically stabilizes the mercury to reduce vapor pressure and leachability and physically encapsulates the waste in a solid matrix to eliminate dispersion and provide long-term durability. Two 55-gallon drums of mixed-waste soil containing high concentrations of mercury and about 62 kg of radioactive contaminated elemental mercury were successfully treated. Waste loadings of 60 wt% soil were achieved without resulting in any increase in waste volume, while elemental mercury was solidified at a waste loading of 33 wt% mercury. Toxicity Characteristic Leaching Procedure (TCLP) analyses indicate the final waste form products pass current Environmental Protection Agency (EPA) allowable TCLP concentrations as well as the more stringent proposed Universal Treatment Standards. Mass balance measurements show that 99.7% of the mercury treated was successfully retained within the waste form, while only 0.3% was captured in the off gas system.

Kalb, P.; Adams, J.; Milian, L.

2001-01-29T23:59:59.000Z

237

Program on Technology Innovation: Volume Reduction Methods and Waste Form Changes for High-Activity Spent Resin  

Science Conference Proceedings (OSTI)

The Electric Power Research Institute (EPRI) has initiated a series of studies to mitigate the impact of limited disposal-site access on continued light water reactor operations. Previous reports investigated two Class B/C low-level radioactive waste minimization techniques. The first was an advanced volume-reduction technique for non-metal filter waste, while the second was a compilation of advanced waste-segregation strategies that were aimed at minimizing the generation of Class B/C waste. This report...

2012-06-28T23:59:59.000Z

238

Certification Plan, low-level waste Hazardous Waste Handling Facility  

SciTech Connect

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

Albert, R.

1992-06-30T23:59:59.000Z

239

The Nuclear Waste Policy Act, as amended, with appropriations acts appended. Revision 1  

SciTech Connect

This act provides for the development of repositories for the disposal of high-level radioactive wastes, low-level radioactive wastes, and spent nuclear fuels. In addition, it establishes research and development programs, as well as demonstration programs regarding the disposal of these wastes. This Act consists of the Act of Jan. 7, 1983 (Public Law 97-425; 96 Stat. 2201), as amended by Public Law 100-203 and Public Law 102-486.

NONE

1995-02-01T23:59:59.000Z

240

State Weights and Measures Law  

Science Conference Proceedings (OSTI)

... Pennsylvania Statutes. Rhode Island Statutes. South Dakota Codified Laws and Administrative Rules. Utah Statutes. Vermont Statutes. ...

2010-10-01T23:59:59.000Z

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


241

High rate mesophilic, thermophilic, and temperature phased anaerobic digestion of waste activated sludge: A pilot scale study  

SciTech Connect

Highlights: Black-Right-Pointing-Pointer High temperatures were tested in single and two-stage anaerobic digestion of waste activated sludge. Black-Right-Pointing-Pointer The increased temperature demonstrated the possibility of improving typical yields of the conventional mesophilic process. Black-Right-Pointing-Pointer The temperature phased anaerobic digestion process (65 + 55 Degree-Sign C) showed the best performances with yields of 0.49 m{sup 3}/kgVS{sub fed}. Black-Right-Pointing-Pointer Ammonia and phosphate released from solids destruction determined the precipitation of struvite in the reactor. - Abstract: The paper reports the findings of a two-year pilot scale experimental trial for the mesophilic (35 Degree-Sign C), thermophilic (55 Degree-Sign C) and temperature phased (65 + 55 Degree-Sign C) anaerobic digestion of waste activated sludge. During the mesophilic and thermophilic runs, the reactor operated at an organic loading rate of 2.2 kgVS/m{sup 3}d and a hydraulic retention time of 20 days. In the temperature phased run, the first reactor operated at an organic loading rate of 15 kgVS/m{sup 3}d and a hydraulic retention time of 2 days while the second reactor operated at an organic loading rate of 2.2 kgVS/m{sup 3}d and a hydraulic retention time of 18 days (20 days for the whole temperature phased system). The performance of the reactor improved with increases in temperature. The COD removal increased from 35% in mesophilic conditions, to 45% in thermophilic conditions, and 55% in the two stage temperature phased system. As a consequence, the specific biogas production increased from 0.33 to 0.45 and to 0.49 m{sup 3}/kgVS{sub fed} at 35, 55, and 65 + 55 Degree-Sign C, respectively. The extreme thermophilic reactor working at 65 Degree-Sign C showed a high hydrolytic capability and a specific yield of 0.33 gCOD (soluble) per gVS{sub fed}. The effluent of the extreme thermophilic reactor showed an average concentration of soluble COD and volatile fatty acids of 20 and 9 g/l, respectively. Acetic and propionic acids were the main compounds found in the acids mixture. Because of the improved digestion efficiency, organic nitrogen and phosphorus were solubilised in the bulk. Their concentration, however, did not increase as expected because of the formation of salts of hydroxyapatite and struvite inside the reactor.

Bolzonella, David, E-mail: david.bolzonella@univr.it [University of Verona, Department of Biotechnology, Strada Le Grazie, 15, 37134 Verona (Italy); Cavinato, Cristina, E-mail: cavinato@unive.it [University of Venice, Department of Environmental Sciences, Computer Science and Statistics, Dorsoduro 2137, 30123 Venice (Italy); Fatone, Francesco, E-mail: francesco.fatone@univr.it [University of Verona, Department of Biotechnology, Strada Le Grazie, 15, 37134 Verona (Italy); Pavan, Paolo, E-mail: pavan@unive.it [University of Venice, Department of Environmental Sciences, Computer Science and Statistics, Dorsoduro 2137, 30123 Venice (Italy); Cecchi, Franco, E-mail: franco.cecchi@univr.it [University of Verona, Department of Biotechnology, Strada Le Grazie, 15, 37134 Verona (Italy)

2012-06-15T23:59:59.000Z

242

A strategic analysis study-based approach to integrated risk assessment: Occupational health risks from environmental restoration and waste management activities at Hanford  

SciTech Connect

The goal of environmental restoration and waste management activities is to reduce public health risks or to delay risks to the future when new technology will be available for improved cleanup solutions. Actions to remediate the wastes on the Hanford Site will entail risks to workers, the public, and the environment that do not currently exist. In some circumstances, remediation activities will create new exposure pathways that are not present without cleanup activities. In addition, cleanup actions will redistribute existing health risks over time and space, and will likely shift health risks to cleanup workers in the short term. This report describes an approach to occupational risk assessment based on the Hanford Strategic Analysis Study and illustrates the approach by comparing worker risks for two options for remediation of N/K fuels, a subcategory of unprocessed irradiated fuels at Hanford.

Mahaffey, J.A.; Doctor, P.G.; Buschbom, R.L.; Glantz, C.S.; Daling, P.M.; Sever, L.E.; Vargo, G.J. Jr.; Strachan, D.M. (Pacific Northwest Lab., Richland, WA (United States)); Pajunen, A.L.; Hoyt, R.C.; Ludowise, J.D. (Westinghouse Hanford Co., Richland, WA (United States))

1993-06-01T23:59:59.000Z

243

THE ROLE OF LIQUID WASTE PRETREATMENT TECHNOLOGIES IN SOLVING THE DOE CLEAN-UP MISSION  

Science Conference Proceedings (OSTI)

The objective of this report is to describe the pretreatment solutions that allow treatment to be tailored to specific wastes, processing ahead of the completion schedules for the main treatment facilities, and reduction of technical risks associated with future processing schedules. Wastes stored at Hanford and Savannah River offer challenging scientific and engineering tasks. At both sites, space limitations confound the ability to effectively retrieve and treat the wastes. Additionally, the radiation dose to the worker operating and maintaining the radiochemical plants has a large role in establishing the desired radioactivity removal. However, the regulatory requirements to treat supernatant and saltcake tank wastes differ at the two sites. Hanford must treat and remove radioactivity from the tanks based on the TriParty Agreement and Waste Incidental to Reprocessing (WIR) documentation. These authorizing documents do not specify treatment technologies; rather, they specify endstate conditions. Dissimilarly, Waste Determinations prepared at SRS in accordance with Section 3116 of the 2005 National Defense Authorization Act along with state operating permits establish the methodology and amounts of radioactivity that must be removed and may be disposed of in South Carolina. After removal of entrained solids and site-specific radionuclides, supernatant and saltcake wastes are considered to be low activity waste (LAW) and are immobilized in glass and disposed of at the Hanford Site Integrated Disposal Facility (IDF) or formulated into a grout for disposal at the Savannah River Site Saltstone Disposal Facility. Wastes stored at the Hanford Site or SRS comprise saltcake, supernate, and sludges. The supernatant and saltcake waste fractions contain primarily sodium salts, metals (e.g., Al, Cr), cesium-137 (Cs-137), technetium-99 (Tc-99) and entrained solids containing radionuclides such as strontium-90 (Sr-90) and transuranic elements. The sludges contain many of the transition metal hydroxides that precipitate when the spent acidic process solutions are rendered alkaline with sodium hydroxide. The sludges contain Sr-90 and transuranic elements. The wastes stored at each site have been generated and stored for over fifty years. Although the majority of the wastes were generated to support nuclear weapons production and reprocessing, the wastes differ substantially between the sites. Table 5 shows the volumes and total radioactivity (including decay daughters) of the waste phases stored in tanks at each site. At Hanford, there are 177 tanks that contain 56.5 Mgal of waste. SRS has 51 larger tanks, of which 2 are closed, that contain 36.5 Mgal. Mainly due to recovery operations, the waste stored at Hanford has less total curies than that stored at Savannah River. The total radioactivity of the Hanford wastes contains approximately 190 MCi, and the total radioactivity of the Savannah River wastes contains 400 MCi.

Wilmarth, B; Sheryl Bush, S

2008-10-31T23:59:59.000Z

244

Pump Jet Mixing and Pipeline Transfer Assessment for High-Activity Radioactive Wastes in Hanford Tank 241-AZ-102  

SciTech Connect

The authors evaluated how well two 300-hp mixer pumps would mix solid and liquid radioactive wastes stored in Hanford double-shell Tank 241-AZ-102 (AZ-102) and confirmed the adequacy of a three-inch (7.6-cm) pipeline system to transfer the resulting mixed waste slurry to the AP Tank Farm and a planned waste treatment (vitrification) plant on the Hanford Site. Tank AZ-102 contains 854,000 gallons (3,230 m{sup 3}) of supernatant liquid and 95,000 gallons (360 m{sup 3}) of sludge made up of aging waste (or neutralized current acid waste). The study comprises three assessments: waste chemistry, pump jet mixing, and pipeline transfer. The waste chemical modeling assessment indicates that the sludge, consisting of the solids and interstitial solution, and the supernatant liquid are basically in an equilibrium condition. Thus, pump jet mixing would not cause much solids precipitation and dissolution, only 1.5% or less of the total AZ-102 sludge. The pump jet mixing modeling indicates that two 300-hp mixer pumps would mobilize up to about 23 ft (7.0 m) of the sludge nearest the pump but would not erode the waste within seven inches (0.18 m) of the tank bottom. This results in about half of the sludge being uniformly mixed in the tank and the other half being unmixed (not eroded) at the tank bottom.

Y Onishi; KP Recknagle; BE Wells

2000-08-09T23:59:59.000Z

245

On mathematical laws of software  

Science Conference Proceedings (OSTI)

Recent studies on the laws and mathematical constraints of softwarehave resulted in fundamental discoveries in computing and software engineeringtoward exploring the nature of software. It was recognized that software isnot constrained by any physical ... Keywords: RTPA, algebraic laws, analysis, computational intelligence, denotational mathematics, generic model of software, laws of meta-processes, laws of process compositions, laws of process relations, mathematical models, modeling, process models, programs, software, software engineering, software science

Yingxu Wang

2008-01-01T23:59:59.000Z

246

Hazardous waste management in the Texas construction industry  

E-Print Network (OSTI)

This pilot study reports the statewide, regulatory compliance of general construction contractors in Texas who generated regulated amounts of hazardous waste during 1990, defined by existing state and federal hazardous-waste-management regulations: specifically, the Resource Conservation and Recovery Act (RCRA) and the Texas Solid Waste Disposal Act (TSWDA). The study was needed because there is presently no knowledge of how well general contractors in Texas are complying with laws enacted to protect human health and the environment from the mismanagement of hazardous waste. The importance of this study is that it addresses the issue of whether regulatory compliance is a problem for general contractors in Texas and the construction industry in general. The implications for this stem from the potential that both environmental harm and enforcement activity could increase as a consequence . Using a combination of survey and archival design methods, the study derived two counts: (1) actual number of general contractors in Texas who generate regulated amounts of hazardous waste and observe regulatory requirements; and (2) estimated number of contractors in Texas who generate regulated amounts of hazardous waste. The comparison equates to one of "compilers" versus "should be complying." Dividing the count of compilers by the count of should-be compilers, equals the degree of regulatory compliance. Using a 95% confidence interval, the study observed that during 1990 only 1 out of 28 general contractors, generating regulated amounts of hazardous waste complied with regulatory requirements (a strong showing of noncompli-ance). In order to resolve the problem of non-compliance, the study recommends that related efforts be undertaken to: (a) expand this study, both in scope and detail to verify the problem identified; (b) improve industry understanding of waste management regulations; (c) promote observance of proper waste-management procedures; (d) summon government support for outreach programs aimed at improving waste management in the construction industry - in particular hazardous waste; (e) initiate further research to design solutions for hazardous-waste-management problems; and (f) implement hazardous-waste minimization and recovery practices in the construction industry.

Sprinkle, Donald Lee

1991-01-01T23:59:59.000Z

247

International low level waste disposal practices and facilities  

SciTech Connect

The safe management of nuclear waste arising from nuclear activities is an issue of great importance for the protection of human health and the environment now and in the future. The primary goal of this report is to identify the current situation and practices being utilized across the globe to manage and store low and intermediate level radioactive waste. The countries included in this report were selected based on their nuclear power capabilities and involvement in the nuclear fuel cycle. This report highlights the nuclear waste management laws and regulations, current disposal practices, and future plans for facilities of the selected international nuclear countries. For each country presented, background information and the history of nuclear facilities are also summarized to frame the country's nuclear activities and set stage for the management practices employed. The production of nuclear energy, including all the steps in the nuclear fuel cycle, results in the generation of radioactive waste. However, radioactive waste may also be generated by other activities such as medical, laboratory, research institution, or industrial use of radioisotopes and sealed radiation sources, defense and weapons programs, and processing (mostly large scale) of mineral ores or other materials containing naturally occurring radionuclides. Radioactive waste also arises from intervention activities, which are necessary after accidents or to remediate areas affected by past practices. The radioactive waste generated arises in a wide range of physical, chemical, and radiological forms. It may be solid, liquid, or gaseous. Levels of activity concentration can vary from extremely high, such as levels associated with spent fuel and residues from fuel reprocessing, to very low, for instance those associated with radioisotope applications. Equally broad is the spectrum of half-lives of the radionuclides contained in the waste. These differences result in an equally wide variety of options for the management of radioactive waste. There is a variety of alternatives for processing waste and for short term or long term storage prior to disposal. Likewise, there are various alternatives currently in use across the globe for the safe disposal of waste, ranging from near surface to geological disposal, depending on the specific classification of the waste. At present, there appears to be a clear and unequivocal understanding that each country is ethically and legally responsible for its own wastes, in accordance with the provisions of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management. Therefore the default position is that all nuclear wastes will be disposed of in each of the 40 or so countries concerned with nuclear power generation or part of the fuel cycle. To illustrate the global distribution of radioactive waste now and in the near future, Table 1 provides the regional breakdown, based on the UN classification of the world in regions illustrated in Figure 1, of nuclear power reactors in operation and under construction worldwide. In summary, 31 countries operate 433 plants, with a total capacity of more than 365 gigawatts of electrical energy (GW[e]). A further 65 units, totaling nearly 63 GW(e), are under construction across 15 of these nations. In addition, 65 countries are expressing new interest in, considering, or actively planning for nuclear power to help address growing energy demands to fuel economic growth and development, climate change concerns, and volatile fossil fuel prices. Of these 65 new countries, 21 are in Asia and the Pacific region, 21 are from the Africa region, 12 are in Europe (mostly Eastern Europe), and 11 in Central and South America. However, 31 of these 65 are not currently planning to build reactors, and 17 of those 31 have grids of less than 5 GW, which is said to be too small to accommodate most of the reactor designs available. For the remaining 34 countries actively planning reactors, as of September 2010: 14 indicate a strong intention to precede w

Nutt, W.M. (Nuclear Engineering Division)

2011-12-19T23:59:59.000Z

248

Waste Logic™ Liquid Waste Manager (WL-LWM) Software, Version 2.0  

Science Conference Proceedings (OSTI)

In response to continuing industry efforts to reduce operating expenditures, EPRI developed the Waste Logic&trade: Liquid Waste Manager code to analyze costs associated with liquid waste processing and the disposition of its resultant solid waste. EPRI's Waste Logic: Liquid Waste Manager software for windows-based PC computers provides a detailed economic and performance view of liquid waste processing activities. The software will help nuclear utilities evaluate the costs associated with liquid radwaste...

2002-06-05T23:59:59.000Z

249

Automated Sampling and Sample Pneumatic Transport of High Level Tank Wastes at the Hanford Waste Treatment Plant  

Science Conference Proceedings (OSTI)

This paper describes the development work, and design and engineering tasks performed, to provide a fully automated sampling system for the Waste Treatment Plant (WTP) project at the Hanford Site in southeastern Washington State, USA. WTP is being built to enable the emptying and immobilization of highly active waste resulting from processing of irradiated nuclear fuel since the 1940's. The Hanford Tank Wastes are separated into Highly Level Waste (HLW), and Low Active Waste (LAW) fractions, which are separately immobilized by vitrification into borosilicate glass. Liquid samples must be taken of the waste and Glass Forming Chemicals (GFCs) before vitrification, and analyzed to insure the glass products will comply with specifications established in the WTP contract. This paper describes the non-radioactive testing of the sampling of the HLW and LAW melter feed simulants that was performed ahead of final equipment design. These trials were essential to demonstrate the effectiveness and repeatability of the integrated sampling system to collect representative samples, free of cross-contamination. Based on existing tried and proven equipment, the system design is tailored to meet the WTP project's specific needs. The design provides sampling capabilities from 47 separate sampling points and includes a pneumatic transport system to move the samples from the 3 separate facilities to the centralized analytical laboratory. The physical and rheological compositions of the waste simulants provided additional challenges in terms of the sample delivery, homogenization, and sample capture equipment design requirements. The activity levels of the actual waste forms, specified as 486 E9 Bq/liter (Cs-137), 1.92 E9 Bq/liter (Co-60), and 9.67 E9 Bq/liter (Eu-154), influenced the degree of automation provided, and justified the minimization of manual intervention needed to obtain and deliver samples from the process facilities to the analytical laboratories. Maintaining high integrity primary and secondary confinement, including during the cross-site transportation of the samples, is a key requirement that is achieved and assured at all times. (authors)

Phillips, C.; Richardson, J. E. [BNG America, 2345 Stevens Drive, Richland, WA, 99354 (United States)

2006-07-01T23:59:59.000Z

250

DIFFERENCES AND SIMILARITIES IN ANDRA'S ASSESSMENT OF ACTIVITIES CARRIED OUT BY RADIOACTIVE WASTE GENERATORS AND AFFECTING THE QUALITY OF IL-LL SHORT-LIVED WASTE PACKAGES AND HL-IL LONG-LIVED WASTE PACKAGES  

Science Conference Proceedings (OSTI)

In both cases of packages for either low-level and intermediate-level short-lived (LL-IL/SL) or high-level and intermediate-level long-lived (HL-IL/LL) radioactive waste, Andra has defined a quality reference system, manages it, follows up its appropriate implementation in production plants and verifies its effectiveness in production. The purpose of such a reference system is to ensure, in the first case, that waste packages comply with the Centre de l'Aube's acceptance criteria and, in the second case, that the characteristics submitted by the waste generators to Andra as input data for the deep geological repository project reflect the actual production conditions. In that context, the three management steps of the quality reference system include differences due to the fact that HL-IL/SL packages have not been submitted yet to any technical acceptance criterion. Compliance with any such criterion should be the subject of a characterization report during the qualification phase and of a examination during the verification phase. The management of the quality reference system also involves similarities that facilitate the joint work carried out by Andra with the waste generators, especially in the facilities where both package types are produced.

Trentesaux, C.; Cairon, P.; Dumont, J.-N.; Felix, B.; Losada, F.

2003-02-27T23:59:59.000Z

251

Fluidized Bed Steam Reforming of Hanford LAW Using THORsm Mineralizing Technology  

SciTech Connect

The U.S. Department of Energy (DOE) documented, in 2002, a plan for accelerating cleanup of the Hanford Site, located in southeastern Washington State, by at least 35 years. A key element of the plan was acceleration of the tank waste program and completion of ''tank waste treatment by 2028 by increasing the capacity of the planned Waste Treatment Plant (WTP) and using supplemental technologies for waste treatment and immobilization.'' The plan identified steam reforming technology as a candidate for supplemental treatment of as much as 70% of the low-activity waste (LAW). Mineralizing steam reforming technology, offered by THOR Treatment Technologies, LLC would produce a denitrated, granular mineral waste form using a high-temperature fluidized bed process. A pilot scale demonstration of the technology was completed in a 15-cm-diameter reactor vessel. The pilot scale facility was equipped with a highly efficient cyclone separator and heated sintered metal filters for particulate removal, a thermal oxidizer for reduced gas species and NOx destruction, and a packed activated carbon bed for residual volatile species capture. The pilot scale equipment is owned by the DOE, but located at the Science and Technology Applications Research (STAR) Center in Idaho Falls, ID. Pilot scale testing was performed August 2–5, 2004. Flowsheet chemistry and operational parameters were defined through a collaborative effort involving Idaho National Engineering and Environmental Laboratory, Savannah River National Laboratory (SRNL), and THOR Treatment Technologies personnel. Science Application International Corporation, owners of the STAR Center, personnel performed actual pilot scale operation. The pilot scale test achieved a total of 68.7 hrs of cumulative/continuous processing operation before termination in response to a bed de-fluidization condition. 178 kg of LAW surrogate were processed that resulted in 148 kg of solid product, a mass reduction of about 17%. The process achieved essentially complete bed turnover within approximately 40 hours. Samples of mineralized solid product materials were analyzed for chemical/physical properties. SRNL will report separately the results of product performance testing that were accomplished.

Olson, Arlin L.; Nicholas R Soelberg; Douglas W. Marshall; Gary L. Anderson

2004-11-01T23:59:59.000Z

252

Municipal Waste Planning, Recycling and Waste Reduction Act (Pennsylvania)  

Open Energy Info (EERE)

Waste Planning, Recycling and Waste Reduction Act (Pennsylvania) Waste Planning, Recycling and Waste Reduction Act (Pennsylvania) No revision has been approved for this page. It is currently under review by our subject matter experts. Jump to: navigation, search Last modified on February 13, 2013. EZFeed Policy Place Pennsylvania Name Municipal Waste Planning, Recycling and Waste Reduction Act (Pennsylvania) Policy Category Other Policy Policy Type Environmental Regulations Affected Technologies Biomass/Biogas, Coal with CCS, Concentrating Solar Power, Energy Storage, Fuel Cells, Geothermal Electric, Hydroelectric, Hydroelectric (Small), Natural Gas, Nuclear, Solar Photovoltaics, Wind energy Active Policy Yes Implementing Sector State/Province Program Administrator Pennsylvania Department of Environmental Protection

253

Hanford Waste Vitrification Plant Project Waste Form Qualification Program Plan  

SciTech Connect

The US Department of Energy has created a waste acceptance process to help guide the overall program for the disposal of high-level nuclear waste in a federal repository. This Waste Form Qualification Program Plan describes the hierarchy of strategies used by the Hanford Waste Vitrification Plant Project to satisfy the waste form qualification obligations of that waste acceptance process. A description of the functional relationship of the participants contributing to completing this objective is provided. The major activities, products, providers, and associated scheduling for implementing the strategies also are presented.

Randklev, E.H.

1993-06-01T23:59:59.000Z

254

DM100 AND DM1200 MELTER TESTING WITH HIGH WASTE LOADING GLASS FORMULATIONS FOR HANFORD HIGH-ALUMINUM HLW STREAMS  

SciTech Connect

This Test Plan describes work to support the development and testing of high waste loading glass formulations that achieve high glass melting rates for Hanford high aluminum high level waste (HLW). In particular, the present testing is designed to evaluate the effect of using low activity waste (LAW) waste streams as a source of sodium in place ofchemical additives, sugar or cellulose as a reductant, boehmite as an aluminum source, and further enhancements to waste processing rate while meeting all processing and product quality requirements. The work will include preparation and characterization of crucible melts in support of subsequent DuraMelter 100 (DM 100) tests designed to examine the effects of enhanced glass formulations, glass processing temperature, incorporation of the LAW waste stream as a sodium source, type of organic reductant, and feed solids content on waste processing rate and product quality. Also included is a confirmatory test on the HLW Pilot Melter (DM1200) with a composition selected from those tested on the DM100. This work builds on previous work performed at the Vitreous State Laboratory (VSL) for Department of Energy's (DOE's) Office of River Protection (ORP) to increase waste loading and processing rates for high-iron HLW waste streams as well as previous tests conducted for ORP on the same waste composition. This Test Plan is prepared in response to an ORP-supplied statement of work. It is currently estimated that the number of HLW canisters to be produced in the Hanford Tank Waste Treatment and Immobilization Plant (WTP) is about 12,500. This estimate is based upon the inventory ofthe tank wastes, the anticipated performance of the sludge treatment processes, and current understanding of the capability of the borosilicate glass waste form. The WTP HLW melter design, unlike earlier DOE melter designs, incorporates an active glass bubbler system. The bubblers create active glass pool convection and thereby improve heat transfer and glass melting rate. The WTP HLW melter has a glass surface area of 3.75 m{sup 2} and depth of {approx}1.1 m. The two melters in the HLW facility together are designed to produce up to 7.5 MT of glass per day at 100% availability. Further increases in HLW waste processing rates can potentially be achieved by increasing the melter operating temperature above 1150 C and by increasing the waste loading in the glass product Increasing the waste loading also has the added benefit of decreasing the number of canisters for storage. The current estimates and glass formulation efforts have been conservative in terms of achievable waste loadings. These formulations have been specified to ensure that the glasses are homogenous, contain essentially no crystalline phases, are processable in joule-heated, ceramic-lined melters and meet WTP contract requirements. The WTP's overall mission will require the immobilization oftank waste compositions that are dominated by mixtures of aluminum (Al), chromium (Cr), bismuth (Bi), iron (Fe), phosphorous (P), zirconium (Zr), and sulfur (S) compounds as waste-limiting components. Glass compositions for these waste mixtures have been developed based upon previous experience and current glass property models. Recently, DOE has initiated a testing program to develop and characterize HLW glasses with higher waste loadings. Results of this work have demonstrated the feasibility of increases in waste-loading from about 25 wt% to 33-50 wt% (based on oxide loading) in the glass depending on the waste stream. It is expected that these higher waste loading glasses will reduce the HLW canister production requirement by about 25% or more.

KRUGER AA; MATLACK KS; KOT WK; PEGG IL; JOSEPH I

2009-12-30T23:59:59.000Z

255

Waste acceptance criteria for closure generated waste  

Science Conference Proceedings (OSTI)

The PORTS Facility has been operating since 1954. The PORTS Facility is used to enrich uranium for nuclear navy applications and commercial nuclear reactors. The PORTS process uses molecular diffusion techniques to separate the U-235 isotope from the U-238 isotope. The PORTS Facility consists of a complex cascade of compressors and converters through which gaseous uranium hexafluoride feed is processed. The feed contains approximately 0.7 percent U-235 by weight while products contain from 4 to 97 percent U-235 by weight, depending on the final application. In general, the majority of the closure wastes generated at PORTS consists of personal protective equipment (PPE), rags, soils, decontamination solutions, and construction related debris. These hazardous wastes will be predominately characterized on the basis of process knowledge. PORTS assumes its conservative waste characterizations that are based on process knowledge are correct unless and until further investigation and/or analysis proves the constituents are not present or are present at concentrations below characteristic regulatory thresholds. Waste Acceptance Criteria for wastes generated by the closure of active and inactive RCRA facilities at PORTS has been developed. The criteria presented in this document govern the activities that are performed during the closure and subsequent generation of waste and relocation from the closure locations to the storage unit. These criteria are intended to ensure the proper handling, classification, processing, and storage of wastes in order to prevent hazardous waste release that may pose a threat to human health or the environment. Any wastes currently stored at each of the facilities that are to be closed will be transferred to the X-326 or X-7725 Storage Units. The waste transfers will be accomplished in accordance with the Container Transfer Plan.

Not Available

1992-05-01T23:59:59.000Z

256

Waste minimization handbook, Volume 1  

Science Conference Proceedings (OSTI)

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

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

1995-12-01T23:59:59.000Z

257

ZERO WASTE.  

E-Print Network (OSTI)

??The aim of the thesis was to develop a clear vision on better waste management system. The thesis introduced the sustainable waste management along with… (more)

Upadhyaya, Luv

2013-01-01T23:59:59.000Z

258

Annual Progress Report on the Development of Waste Tank Leak Monitoring and Detection and Mitigation Activities in Support of M-45-08  

SciTech Connect

Milestone M-45-09E of the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement or TPA) [TPA 1996] requires submittal of an annual progress report on the development of waste tank leak detection, monitoring, and mitigation (LDMM) activities associated with the retrieval of waste from single-shell tanks (SSTs). This report details progress for fiscal year 2000, building on the current LDMM strategy and including discussion of technologies, applications, cost, schedule, and technical data. The report also includes discussion of demonstrations conducted and recommendations for additional testing. Tri-Party Agreement Milestones M-45-08A and M-45-08B required design and demonstration of LDMM systems for initial retrieval of SST waste. These specific milestones have recently been deleted as part of the M-45-00A change package. Future LDMM development work has been incorporated into specific technology demonstration milestones and SST waste retrieval milestones in the M-45-03 and M-45-05 milestone series.

DEFIGH PRICE, C.

2000-09-25T23:59:59.000Z

259

Hyperbolic Conservation Laws The 1D conservation law  

E-Print Network (OSTI)

Hyperbolic Conservation Laws The 1D conservation law wt + f(w)x = 0 (where w and f have m of linearly independent eigenvectors). Then solutions to the conservation law can be viewed in terms of propagating waves. Finite Volume Methods Finite volume methods are conservative by construction. Define

Gardner, Carl

260

EVALUATION OF THOR MINERALIZED WASTE FORMS FOR THE DOE ADVANCED REMEDIATION TECHNOLOGIES PHASE 2 PROJECT  

SciTech Connect

The U.S. Department of Energy's (DOE) Office of River Protection (ORP) is responsible for the retrieval, treatment, immobilization, and disposal of Hanford's tank waste. Currently there are approximately 56 million gallons of highly radioactive mixed wastes awaiting treatment. A key aspect of the River Protection Project (RPP) cleanup mission is to construct and operate the Waste Treatment and Immobilization Plant (WTP). The WTP will separate the tank waste into high-level and low-activity waste (LAW) fractions, both of which will subsequently be vitrified. The projected throughput capacity of the WTP LAW Vitrification Facility is insufficient to complete the RPP mission in the time frame required by the Hanford Federal Facility Agreement and Consent Order, also known as the Tri-Party Agreement (TPA), i.e. December 31, 2047. Therefore, Supplemental Treatment is required both to meet the TPA treatment requirements as well as to more cost effectively complete the tank waste treatment mission. The Supplemental Treatment chosen will immobilize that portion of the retrieved LAW that is not sent to the WTP's LAW Vitrification facility into a solidified waste form. The solidified waste will then be disposed on the Hanford site in the Integrated Disposal Facility (IDF). In addition, the WTP LAW Vitrification facility off-gas condensate known as WTP Secondary Waste (WTP-SW) will be generated and enriched in volatile components such as Cs-137, I-129, Tc-99, Cl, F, and SO{sub 4} that volatilize at the vitrification temperature of 1150 C in the absence of a continuous cold cap. The current waste disposal path for the WTP-SW is to recycle it to the supplemental LAW treatment to avoid a large steady state accumulation in the pretreatment-vitrification loop. Fluidized Bed Steam Reforming (FBSR) offers a moderate temperature (700-750 C) continuous method by which LAW and/or WTP-SW wastes can be processed irrespective of whether they contain organics, nitrates, sulfates/sulfides, chlorides, fluorides, volatile radionuclides or other aqueous components. The FBSR technology can process these wastes into a crystalline ceramic (mineral) waste form. The mineral waste form that is produced by co-processing waste with kaolin clay in an FBSR process has been shown to be as durable as LAW glass. Monolithing of the granular FBSR product, which is one of the objectives of this current study, is being investigated to prevent dispersion during transport or burial/storage but is not necessary for performance. FBSR testing of a Hanford LAW simulant and a WTP-SW simulant at the pilot scale was performed by THOR Treatment Technologies, LLC at Hazen Research Inc. in April/May 2008. The Hanford LAW simulant was the Rassat 68 tank blend and the target concentrations for the LAW was increased by a factor of 10 for Sb, As, Ag, Cd, and Tl; 100 for Ba and Re (Tc surrogate); 1,000 for I; and 254,902 for Cs based on discussions with the DOE field office and the environmental regulators and an evaluation of the Hanford Tank Waste Envelopes A, B, and C. It was determined through the evaluation of the actual tank waste metals concentrations that some metal levels were not sufficient to achieve reliable detection in the off-gas sampling. Therefore, the identified metals concentrations were increased in the Rassat simulant processed by TTT at HRI to ensure detection and enable calculation of system removal efficiencies, product retention efficiencies, and mass balance closure without regard to potential results of those determinations or impacts on product durability response such as Toxicity Characteristic Leach Procedure (TCLP). A WTP-SW simulant based on melter off-gas analyses from Vitreous State Laboratory (VSL) was also tested at HRI in the 15-inch diameter Engineering Scale Test Demonstration (ESTD) dual reformer at HRI in 2008. The target concentrations for the Resource Conservation and Recovery Act (RCRA) metals were increased by 16X for Se, 29X for Tl, 42X for Ba, 48X for Sb, by 100X for Pb and Ni, 1000X for Ag, and 1297X for Cd to ensure detection by the an

Crawford, C.; Jantzen, C.

2012-02-02T23:59:59.000Z

Note: This page contains sample records for the topic "activity waste law" 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

Cesium Ion Exchange Program at the Hanford River Protection Project Waste Treatment Plant  

SciTech Connect

The Hanford Waste Treatment and Immobilization Plant (WTP) will use cesium ion exchange to remove Cs-137 from Low Activity Waste (LAW) down to a maximum activity of 0.3 Ci/m3 in the Immobilized LAW (ILAW) product. The WTP Project baseline for cesium ion exchange is the elutable SuperLig(R) 644 (SL-644) resin (registered trademark of IBC Advanced Technologies, Inc., American Fork, UT) or a U. S. Department of Energy (DOE) approved equivalent. SL-644 is solely available through IBC Advanced Technologies. The WTP Project is conducting a three-stage process for selecting and qualifying an alternative ion exchange resin. Resorcinol formaldehyde (RF) is being pursued as a potential alternative to SL-644, to provide a backup resin supply. Resin cost relative to SL-644 is a primary driver. Phase I of the testing plan examined the viability of RF resin and recommended that a spherical form of RF resin be examined further. Phases II and III, now underway, include batch testing to determine the isotherm of this resin, kinetics to address the impacts of bead diameter and high sodium feed levels on processing Hanford waste with the resin, and multicycle column testing to determine how temperature and chemical cycling affects waste processing. Phases II and III also examine resin performance against simulated WTP feeds, radiolytic and thermal stability, and scale-up to pilot scale performance. We will discuss early results obtained from Phase II testing here.

CHARLES, NASH

2005-02-27T23:59:59.000Z

262

APSUO By-laws  

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

Advanced Photon Source Users Organization By-laws Advanced Photon Source Users Organization By-laws Name This organization will be called the Advanced Photon Source Users Organization (APSUO). Purpose The purpose of this Organization is to facilitate the availability and effective use of the Advanced Photon Source by the synchrotron radiation research community so that the greatest overall scientific and technical benefits are realized. Organization Membership All badged APS users are APSUO members. Meetings Annual User Meetings will be held at the APS site. The APSUO Steering Committee shall be responsible for the programs of the User Meetings. APSUO members shall receive appropriate advance notice of the Meetings. Steering Committee A Steering Committee will conduct the business of the APSUO. Four members

263

DOE Waste Treatability Group Guidance  

Science Conference Proceedings (OSTI)

This guidance presents a method and definitions for aggregating U.S. Department of Energy (DOE) waste into streams and treatability groups based on characteristic parameters that influence waste management technology needs. Adaptable to all DOE waste types (i.e., radioactive waste, hazardous waste, mixed waste, sanitary waste), the guidance establishes categories and definitions that reflect variations within the radiological, matrix (e.g., bulk physical/chemical form), and regulated contaminant characteristics of DOE waste. Beginning at the waste container level, the guidance presents a logical approach to implementing the characteristic parameter categories as part of the basis for defining waste streams and as the sole basis for assigning streams to treatability groups. Implementation of this guidance at each DOE site will facilitate the development of technically defined, site-specific waste stream data sets to support waste management planning and reporting activities. Consistent implementation at all of the sites will enable aggregation of the site-specific waste stream data sets into comparable national data sets to support these activities at a DOE complex-wide level.

Kirkpatrick, T.D.

1995-01-01T23:59:59.000Z

264

Oak Ridge National Laboratory Waste Management Plan  

Science Conference Proceedings (OSTI)

The objective of the Oak Ridge National Laboratory Waste Management Plan is to compile and to consolidate information annually on how the ORNL Waste Management Program is conducted, which waste management facilities are being used to manage wastes, what forces are acting to change current waste management systems, what activities are planned for the forthcoming fiscal year (FY), and how all of the activities are documented.

Not Available

1992-12-01T23:59:59.000Z

265

Joint Degree Program in Social Work and Law  

E-Print Network (OSTI)

Joint Degree Program in Social Work and Law MSW and JD The complexity of current national debates and programs, and social work advocacy activities, including clinical practice, and the law. It is therefore work to remain in good standing and for graduation, the MSW Program follows the Graduate School

Peterson, Blake R.

266

Mixed waste characterization reference document  

SciTech Connect

Waste characterization and monitoring are major activities in the management of waste from generation through storage and treatment to disposal. Adequate waste characterization is necessary to ensure safe storage, selection of appropriate and effective treatment, and adherence to disposal standards. For some wastes characterization objectives can be difficult and costly to achieve. The purpose of this document is to evaluate costs of characterizing one such waste type, mixed (hazardous and radioactive) waste. For the purpose of this document, waste characterization includes treatment system monitoring, where monitoring is a supplement or substitute for waste characterization. This document establishes a cost baseline for mixed waste characterization and treatment system monitoring requirements from which to evaluate alternatives. The cost baseline established as part of this work includes costs for a thermal treatment technology (i.e., a rotary kiln incinerator), a nonthermal treatment process (i.e., waste sorting, macronencapsulation, and catalytic wet oxidation), and no treatment (i.e., disposal of waste at the Waste Isolation Pilot Plant (WIPP)). The analysis of improvement over the baseline includes assessment of promising areas for technology development in front-end waste characterization, process equipment, off gas controls, and monitoring. Based on this assessment, an ideal characterization and monitoring configuration is described that minimizes costs and optimizes resources required for waste characterization.

1997-09-01T23:59:59.000Z

267

Summary of expenditures of rebates from the low-level radioactive waste surcharge escrow account for calendar year 1991. Report to Congress in response to Public Law 99-240  

SciTech Connect

This is the sixth report submitted to Congress under section 5(d)(2)(E)(ii)(II) of the Low-Level Radioactive Waste Policy Act of 1985 (the Act). This section of the Act directs the Department of Energy (DOE) to summarize the annual expenditures of funds disbursed from the DOE surcharge escrow account and to assess compliance of these expenditures with the limitations specified in the Act. In addition to placing limitations on the use of these funds, the Act also requires the nonsited compact regions and nonmember States to provide DOE with an itemized report of their expenditures on December 31 of each year in which funds are expended. Within 6 months after receiving the individual reports, the Act requires the Secretary to furnish Congress with a summary of the reported expenditures and an assessment of compliance with the specified usage limitations. This report fulfills that requirement. DOE disbursed funds totaling $15,037,778.91 to the States and compact regions following the July 1, 1986, January 1, 1988, and January 1, 1990, milestones specified in the Act. Of this amount, $3,517,020.56 was expended during calendar year 1991 and $6,602,546.24 was expended during the prior 5 years. At the end of December 1991, $4,918,212.11 was unexpended. DOE has reviewed each of the reported expenditures and concluded that all reported expenditures comply with the spending limitations stated in section 5(d)(2)(E)(i) of the Act.

Not Available

1992-06-01T23:59:59.000Z

268

Sulfate Volatilization in Simulated Nuclear Waste Glasses  

Science Conference Proceedings (OSTI)

Radioactive Demonstrations of Fluidized Bed Steam Reforming (FBSR) with Hanford Low Activity Wastes · Radionuclide Behavior and Geochemistry in Boom

269

CLAB Transuranic Waste Spreadsheets  

Science Conference Proceedings (OSTI)

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

Leyba, J.D.

2000-08-11T23:59:59.000Z

270

Estimating Waste Inventory and Waste Tank Characterization |...  

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

Estimating Waste Inventory and Waste Tank Characterization Estimating Waste Inventory and Waste Tank Characterization Summary Notes from 28 May 2008 Generic Technical Issue...

271

Solar Easements & Rights Laws | Department of Energy  

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

Solar Easements & Rights Laws Solar Easements & Rights Laws Eligibility Agricultural Commercial Fed. Government Industrial Institutional Local Government Nonprofit Residential...

272

Summary report: Low-level radioactive waste management activities in the states and compacts, Volume 5, Number 1  

Science Conference Proceedings (OSTI)

Information is given on the ten compacts and their host state, describing the governing body, member states, date established, current waste management, and siting, licensing, and projected date of a disposal facility. Reports are also given on the eight states that remain unaffiliated with a compact commission.

Norris, C. [ed.

1997-01-01T23:59:59.000Z

273

Summary report: Low-level radioactive waste management activities in the states and compacts, Volume 5, Number 2  

Science Conference Proceedings (OSTI)

Information is given on the ten compacts and their host state, describing the governing body, member states, date established, current waste management, and siting, licensing, and projected date of a disposal facility. Reports are also given on the eight states that remain unaffiliated with a compact commission.

Norris, C. [ed.

1997-07-01T23:59:59.000Z

274

Reduced Pressure Electron Beam Welding Evaluation Activities on a Ni-Cr-Mo Alloy for Nuclear Waste Packages  

SciTech Connect

The current waste package design for the proposed repository at Yucca Mountain Nevada, USA, employs gas tungsten arc welding (GTAW) in fabricating the waste packages. While GTAW is widely used in industry for many applications, it requires multiple weld passes. By comparison, single-pass welding methods inherently use lower heat input than multi-pass welding methods which results in lower levels of weld distortion and also narrower regions of residual stresses at the weld TWI Ltd. has developed a Reduced Pressure Electron Beam (RPEB) welding process which allows EB welding in a reduced pressure environment ({le} 1 mbar). As it is a single-pass welding technique, use of RPEB welding could (1) achieve a comparable or better materials performance and (2) lead to potential cost savings in the waste package manufacturing as compared to GTAW. Results will be presented on the initial evaluation of the RPEB welding on a Ni-Cr-Mo alloy (a candidate alloy for the Yucca Mountain waste packages) in the areas of (a) design and manufacturing simplifications, (b) material performance and (c) weld reliability.

Wong, F; Punshon, C; Dorsch, T; Fielding, P; Richard, D; Yang, N; Hill, M; DeWald, A; Rebak, R; Day, S; Wong, L; Torres, S; McGregor, M; Hackel, L; Chen, H-L; Rankin, J

2003-09-11T23:59:59.000Z

275

Laboratory Testing of Bulk Vitrified Low-Activity Waste Forms to Support the 2005 Integrated Disposal Facility Performance Assessment  

Science Conference Proceedings (OSTI)

The purpose of this report is to document the results from laboratory testing of the bulk vitri-fied (BV) waste form that was conducted in support of the 2005 integrated disposal facility (IDF) performance assessment (PA). Laboratory testing provides a majority of the key input data re-quired to assess the long-term performance of the BV waste package with the STORM code. Test data from three principal methods, as described by McGrail et al. (2000a; 2003a), are dis-cussed in this testing report including the single-pass flow-through test (SPFT) and product con-sistency test (PCT). Each of these test methods focuses on different aspects of the glass corrosion process. See McGrail et al. (2000a; 2003a) for additional details regarding these test methods and their use in evaluating long-term glass performance. In addition to evaluating the long-term glass performance, this report discusses the results and methods used to provided a recommended best estimate of the soluble fraction of 99Tc that can be leached from the engineer-ing-scale BV waste package. These laboratory tests are part of a continuum of testing that is aimed at improving the performance of the BV waste package.

Pierce, Eric M.; McGrail, B. Peter; Bagaasen, Larry M.; Rodriguez, Elsa A.; Wellman, Dawn M.; Geiszler, Keith N.; Baum, Steven R.; Reed, Lunde R.; Crum, Jarrod V.; Schaef, Herbert T.

2006-06-30T23:59:59.000Z

276

Liquid and Gaseous Waste Operations Department Annual Operating Report, CY 1993  

SciTech Connect

This report summarizes the activities of the waste management operations section of the liquid and gaseous waste operations department at ORNL for 1993. The process waste, liquid low-level waste, gaseous waste systems activities are reported, as well as the low-level waste solidification project. Upgrade activities is the various waste processing and treatment systems are summarized. A maintenance activity overview is provided, and program management, training, and other miscellaneous activities are covered.

Maddox, J.J.; Scott, C.B.

1994-02-01T23:59:59.000Z

277

Waste Isolation Pilot Plant - Reports  

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

Reports Reports Waste Isolation Pilot Plant Review Report 2013 Review of the Waste Isolation Pilot Plant Work Planning and Control Activities, April 2013 Review Report 2012 Review of Site Preparedness for Severe Natural Phenomena Events at the Waste Isolation Pilot Plant, November 2012 Activity Reports 2011 Orientation Visit to the Waste Isolation Pilot Plant, September 2011 Review Reports 2007 Independent Oversight Inspection of Emergency Management at the Carlsbad Field Office and Waste Isolation Pilot Plant, December 2007 Review Reports 2002 Inspection of Environment, Safety, and Health and Emergency Management at the Waste Isolation Pilot Plant - Summary Report, August 2002 Inspection of Environment, Safety, and Health Management at the Waste Isolation Pilot Plant - Volume I, August 2002

278

Evaluation of the impact of RCRA amendments on waste-to-energy activities by using a system simulation computer code  

DOE Green Energy (OSTI)

The primary methodology that is used for disposal of municipal solid waste is the use of land fills; 80--85% of the municipal solid waste (MSW) produced in the country currently is land filled. The two other disposal alternatives used are recycling and incineration. Waste-to-energy technology (WTE) which incinerates MSW to produce electricity and/or steam is attractive in other cases since it reduces landfill volume, reduces the consumption of fossil and other fuels, and produces a revenue stream from the sale of the electricity or steam. The gaseous effluents from landfills can also be used to fuel power plants. Recycling and material separation programs can have a substantial impact on the throughput and heating value of MSW collected and thus impact WTE plant economics; the magnitude of the impact will depend upon a number of factors such as what materials and what fraction are separated and recycled, the design of the WTE plant itself (its operating window); the contractual arrangements relative to maintaining throughput (ability to adjust catchment area), limitations on adjusting tipping fees, etc. Mandated increased recycling and landfill gaseous effluent control -- could alter substantially the economics and competitive position of the MSW-WTE industry. The objectives of this study are: (1) to simulate typical WTE plants fired with a national average waste stream, (2) to evaluate the parametric effects of waste component recycling on the performance of the typical WTE plants, and (3) to assess the impact of RCRA recycling amendments on the performance of the typical WTE plants and on the potential methane generation of typical landfills. The relevant technical issues, technical approach, results and conclusions are presented.

Chang, S.L.; Petrick, M.; Stodolsky, F.; Freckmann, A.B.

1994-09-01T23:59:59.000Z

279

Waste Form Release Data Package for the 2005 Integrated Disposal Facility Performance Assessment  

SciTech Connect

This data package documents the experimentally derived input data on the representative waste glasses; LAWA44, LAWB45, and LAWC22. This data will be used for Subsurface Transport Over Reactive Multi-phases (STORM) simulations of the Integrated Disposal Facility (IDF) for immobilized low-activity waste (ILAW). The STORM code will be used to provide the near-field radionuclide release source term for a performance assessment to be issued in July 2005. Documented in this data package are data related to 1) kinetic rate law parameters for glass dissolution, 2) alkali (Na+)-hydrogen (H+) ion exchange rate, 3) chemical reaction network of secondary phases that form in accelerated weathering tests, and 4) thermodynamic equilibrium constants assigned to these secondary phases. The kinetic rate law and Na+-H+ ion exchange rate were determined from single-pass flow-through experiments. Pressurized unsaturated flow (PUF) and product consistency (PCT) tests where used for accelerated weathering or aging of the glasses in order to determine a chemical reaction network of secondary phases that form. The majority of the thermodynamic data used in this data package were extracted from the thermody-namic database package shipped with the geochemical code EQ3/6, version 8.0. Because of the expected importance of 129I release from secondary waste streams being sent to IDF from various thermal treatment processes, parameter estimates for diffusional release and solubility-controlled release from cementitious waste forms were estimated from the available literature.

Pierce, Eric M.; McGrail, B. Peter; Rodriguez, Elsa A.; Schaef, Herbert T.; Saripalli, Prasad; Serne, R. Jeffrey; Krupka, Kenneth M.; Martin, P. F.; Baum, Steven R.; Geiszler, Keith N.; Reed, Lunde R.; Shaw, Wendy J.

2004-09-01T23:59:59.000Z

280

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

SciTech Connect

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

Note: This page contains sample records for the topic "activity waste law" 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

Missouri Clean Water Law (Missouri) | Department of Energy  

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

Missouri Clean Water Law (Missouri) Missouri Clean Water Law (Missouri) Missouri Clean Water Law (Missouri) < Back Eligibility Agricultural Commercial Construction Industrial Institutional Investor-Owned Utility Local Government Municipal/Public Utility Rural Electric Cooperative Tribal Government Utility Program Info State Missouri Program Type Environmental Regulations Provider Missouri Department of Natural Resources The public policy of the state of Missouri is to conserve the waters of the state and to protect, maintain, and improve their quality for public water supplies and for domestic, agricultural, industrial, recreational and other legitimate beneficial uses and for the propagation of wildlife, fish and aquatic life, as well as to provide for the prevention, abatement, and control of new or existing water pollution. No waste may be discharged into

282

Hazardous Waste  

Science Conference Proceedings (OSTI)

Table 6   General refractory disposal options...D landfill (b) Characterized hazardous waste by TCLP

283

Site-specific waste management instruction - radiological screening facility  

DOE Green Energy (OSTI)

This Site-Specific Waste Management Instruction provides guidance for managing waste generated from radiological sample screening operations conducted to support the Environmental Restoration Contractor`s activities. This document applies only to waste generated within the radiological screening facilities.

G. G. Hopkins

1997-12-31T23:59:59.000Z

284

TUTORIALS: Bragg's Law and Diffraction  

Science Conference Proceedings (OSTI)

Jul 8, 2007 ... CITATION: "Bragg's Law and Diffraction: How waves reveal the atomic structure of crystals," Project Java, State University of New York at Stony ...

285

Solid Waste Management Program Plan  

SciTech Connect

The objective of the Solid Waste Management Program Plan (SWMPP) is to provide a summary level comprehensive approach for the storage, treatment, and disposal of current and future solid waste received at the Hanford Site (from onsite and offsite generators) in a manner compliant with current and evolving regulations and orders (federal, state, and Westinghouse Hanford Company (Westinghouse Hanford)). The Plan also presents activities required for disposal of selected wastes currently in retrievable storage. The SWMPP provides a central focus for the description and control of cost, scope, and schedule of Hanford Site solid waste activities, and provides a vehicle for ready communication of the scope of those activities to onsite and offsite organizations. This Plan represents the most complete description available of Hanford Site Solid Waste Management (SWM) activities and the interfaces between those activities. It will be updated annually to reflect changes in plans due to evolving regulatory requirements and/or the SWM mission. 8 refs., 9 figs., 4 tabs.

Duncan, D.R.

1990-08-01T23:59:59.000Z

286

Central waste complex interim safety basis  

Science Conference Proceedings (OSTI)

This interim safety basis provides the necessary information to conclude that hazards at the Central Waste Complex are controlled and that current and planned activities at the CWC can be conducted safely. CWC is a multi-facility complex within the Solid Waste Management Complex that receives and stores most of the solid wastes generated and received at the Hanford Site. The solid wastes that will be handled at CWC include both currently stored and newly generated low-level waste, low-level mixed waste, contact-handled transuranic, and contact-handled TRU mixed waste.

Cain, F.G.

1995-05-15T23:59:59.000Z

287

NEVADA TEST SITE WASTE ACCEPTANCE CRITERIA  

Science Conference Proceedings (OSTI)

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

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

2005-07-01T23:59:59.000Z

288

Biological treatment of concentrated hazardous, toxic, and radionuclide mixed wastes without dilution  

E-Print Network (OSTI)

Report. DOE/MWIP-26. Mixed Waste Integrated Program, U. S.Trial burn activities for a mixed waste incinerator. WasteBiological Treatment of Mixed Wastes Containing Acetonitrile

Stringfellow, William T.; Komada, Tatsuyuki; Chang, Li-Yang

2004-01-01T23:59:59.000Z

289

Biohazardous Waste Disposal Guidelines Sharps Waste Solid Lab Waste Liquid Waste Animals Pathological Waste  

E-Print Network (OSTI)

Biohazardous Waste Disposal Guidelines Sharps Waste Solid Lab Waste Liquid Waste Animals Pathological Waste Description Biohazard symbol Address: UCSD 9500 Gilman Drive La Jolla, CA 92093 (858) 534) and identity of liquid waste Biohazard symbol Address: UCSD 9500 Gilman Drive La Jolla, CA 92093 (858) 534

Russell, Lynn

290

Biohazardous Waste Disposal Guidelines Sharps Waste Solid Lab Waste Liquid Waste Animals Pathological Waste  

E-Print Network (OSTI)

2/2009 Biohazardous Waste Disposal Guidelines Sharps Waste Solid Lab Waste Liquid Waste Animals Pathological Waste Description Biohazard symbol Address: UCSD 200 West Arbor Dr. San Diego, CA 92103 (619 (9:1) OR Biohazard symbol (if untreated) and identity of liquid waste Biohazard symbol Address

Firtel, Richard A.

291

SMALL-SCALE MELTER TESTING WITH LAW SIMULANTS TO ASSESS THE IMPACT OF HIGHER TEMPERATURE MELTER OPERATIONS - Final Report, VSL-04R49801-1, Rev. 0, 2/13/03, Vitreous State Laboratory, The Catholic University of America, Washington, D.C.  

Science Conference Proceedings (OSTI)

About 50 million gallons of high-level mixed waste is currently in storage in underground tanks at The United States Department of Energy's (DOE's) Hanford site in the State of Washington. The Hanford Tank Waste Treatment and Immobilization Plant (WTP) will provide DOE's Office of River Protection (ORP) with a means of treating this waste by vitrification for subsequent disposal. The tank waste will be separated into low- and high-activity fractions, which will then be vitrified respectively into Immobilized Low Activity Waste (ILAW) and Immobilized High Level Waste (IHLW) products. The ILAW product will be disposed of in an engineered facility on the Hanford site while the IHL W product will be directed to the national deep geological disposal facility for high-level nuclear waste. The ILAW and IHLW products must meet a variety of requirements with respect to protection of the environment before they can be accepted for disposal. The Office of River Protection is currently examining options to optimize the Low Activity Waste (LAW) facility and the LAW glass waste form. One option under evaluation is to enhance the waste processing rate of the vitrification plant currently under construction. It is likely that the capacity of the LAW vitrification plant can be increased incrementally by implementation of a variety of low-risk, high-probability changes, either separately or in combination. These changes include: (1) Operating at the higher processing rates demonstrated at the LAW Pilot Melter; (2) Increasing the glass pool surface area within the existing external melter envelope; (3) Increasing plant availability; (4) Increasing the glass waste loading; (5) Removing sulfate from the LAW stream; (6) Operating the melter at slightly higher temperature; (7) Installing the third LAW melter into the WTP plant; and (8) Other smaller impact changes. The tests describes in this report utilized blended feed (glass formers plus waste simulant) prepared by Optima Chemicals according to VSL specifications. Sufficient feed was prepared to produce nearly two metric tons of glass. Sugar was added (at VSL) to the feed at a ratio of 0.5 (1 mole sucrose per 16 mole NOx). The DM100-WV melter was used in order to provide a direct comparison with the LAW tests previously conducted on the same melter. Two 75-hour melter tests were conducted at two elevated temperatures, 1175 and 1225 C. These tests were preceded by the production of sufficient glass to turn over the melt pool to the target composition. Key operating parameters were held constant to investigate the effects of the operating temperature on processing characteristics, particularly melting rate. At each operating temperature, the feed rate was adjusted to provide a near-complete cold cap 99-100% of melt surface covered with feed. Quantitative measurements of glass production rates, melter operating conditions (temperatures, pressures, power, flows, etc.), and off-gas characteristics (NOx, SO{sub 2}, CO, particulate load and composition, and acid gases) were made for each test.

KRUGER AA; MATLACK KS

2012-02-07T23:59:59.000Z

292

Transuranic Waste Tabletop  

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

Transuranic (TRU) Waste Transuranic (TRU) Waste (Hazard Class 7 Radioactive) Moderator's Version of Tabletop Prepared for the Department of Energy Office of Transportation and Emergency Management 02B00215-07D.p65 This page intentionally left blank table of contents Transportation Emergency Preparedness Program (TEPP) planning tools planning tools planning tools planning tools T T T T Tr r r r ransur ansur ansur ansur ansuranic (TRU) W anic (TRU) W anic (TRU) W anic (TRU) W anic (TRU) Waste aste aste aste aste (Hazar (Hazar (Hazar (Hazar (Hazard Class 7 Radio d Class 7 Radio d Class 7 Radio d Class 7 Radio d Class 7 Radioactiv activ activ activ active) e) e) e) e) Moder Moder Moder Moder Moderat at at at ator' or' or' or' or's V s V s V s V s Version of T ersion of T ersion of T ersion of T ersion of Tablet ablet ablet ablet abletop

293

Spent fuel assembly hardware: Characterization and 10 CFR 61 classification for waste disposal: Volume 1, Activation measurements and comparison with calculations for spent fuel assembly hardware  

Science Conference Proceedings (OSTI)

Consolidation of spent fuel is under active consideration as the US Department of Energy plans to dispose of spent fuel. During consolidation, the fuel pins are removed from an intact fuel assembly and repackaged into a more compact configuration. After repackaging, approximately 30 kg of residual spent fuel assembly hardware per assembly remains that is also radioactive and requires disposal. Understanding the nature of this secondary waste stream is critical to designing a system that will properly handle, package, store, and dispose of the waste. This report presents a methodology for estimating the radionuclide inventory in irradiated spent fuel hardware. Ratios are developed that allow the use of ORIGEN2 computer code calculations to be applied to regions that are outside the fueled region. The ratios are based on the analysis of samples of irradiated hardware from spent fuel assemblies. The results of this research are presented in three volumes. In Volume 1, the development of scaling factors that can be used with ORIGEN2 calculations to estimate activation of spent fuel assembly hardware is documented. The results from laboratory analysis of irradiated spent-fuel hardware samples are also presented in Volume 1. In Volumes 2 and 3, the calculated flux profiles of spent nuclear fuel assemblies are presented for pressurized water reactors and boiling water reactors, respectively. The results presented in Volumes 2 and 3 were used to develop the scaling factors documented in Volume 1. 5 refs., 4 figs., 21 tabs.

Luksic, A.

1989-06-01T23:59:59.000Z

294

HAZARDOUS WASTE OPERATIONS AND EMERGENCY RESPONSE (HAZWOPER)  

E-Print Network (OSTI)

construction activities support closure of contaminated areas in compliance with the RCRA Consent Order) TRU Waste Facility (TRU) Material Disposal Area-C Closure Material Disposal Area-G Closure Waste

US Army Corps of Engineers

295

Technical requirements specification for tank waste retrieval  

Science Conference Proceedings (OSTI)

This document provides the technical requirements specification for the retrieval of waste from the underground storage tanks at the Hanford Site. All activities covered by this scope are conducted in support of the Tank Waste Remediation System (TWRS) mission.

Lamberd, D.L.

1996-09-26T23:59:59.000Z

296

THE DEVELOPMENT OF ATOMIC LAW  

SciTech Connect

Since a uniform federal statute hss not been passed in the German Federal Republic, the development of atomic law has centered around the formation of the Federal Ministry for Atomic Affairs, appeal to the German Commission, and the enactment of temporary laws in several of the states. (J.S.R.)

Fischerhof, H.

1958-08-01T23:59:59.000Z

297

Low Level Radioactive Waste Authority (Michigan) | Department of Energy  

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

Low Level Radioactive Waste Authority (Michigan) Low Level Radioactive Waste Authority (Michigan) Low Level Radioactive Waste Authority (Michigan) < Back Eligibility Utility Fed. Government Investor-Owned Utility Municipal/Public Utility Program Info State Michigan Program Type Safety and Operational Guidelines Provider Department of Environmental Quality Federal laws passed in 1980 and 1985 made each state responsible for the low-level radioactive waste produced within its borders. Act 204 of 1987 created the Low-Level Radioactive Waste Authority (LLRWA) to fulfill state responsibilities under federal law for managing and assuring disposal capacity for the low-level radioactive waste produced in Michigan. The LLRWA began a facility siting process in 1989 under the statutory limits of Act 204. The LLRWA eventually determined that it was impossible to find a

298

Hazardous Waste Program (Alabama)  

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

This rule states criteria for identifying the characteristics of hazardous waste and for listing hazardous waste, lists of hazardous wastes, standards for the management of hazardous waste and...

299

Solid Waste Facilities Regulations (Massachusetts) | Department of Energy  

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

Solid Waste Facilities Regulations (Massachusetts) Solid Waste Facilities Regulations (Massachusetts) Solid Waste Facilities Regulations (Massachusetts) < Back Eligibility Agricultural Commercial Construction Fed. Government Fuel Distributor General Public/Consumer Industrial Installer/Contractor Institutional Investor-Owned Utility Local Government Low-Income Residential Multi-Family Residential Municipal/Public Utility Nonprofit Residential Retail Supplier Rural Electric Cooperative Schools State/Provincial Govt Systems Integrator Transportation Tribal Government Utility Program Info State Massachusetts Program Type Environmental Regulations Provider Department of Environmental Protection This chapter of the Massachusetts General Laws governs the operation of solid waste facilities. It seeks to encourage sustainable waste management

300

Radioactive and mixed waste management plan for the Lawrence Berkeley Laboratory Hazardous Waste Handling Facility  

SciTech Connect

This Radioactive and Mixed Waste Management Plan for the Hazardous Waste Handling Facility at Lawrence Berkeley Laboratory is written to meet the requirements for an annual report of radioactive and mixed waste management activities outlined in DOE Order 5820.2A. Radioactive and mixed waste management activities during FY 1994 listed here include principal regulatory and environmental issues and the degree to which planned activities were accomplished.

NONE

1995-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "activity waste law" 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

On second-law efficiency of solar collectors  

SciTech Connect

Traditionally, the performance of solar collectors has been examined from the standpoint of energy-balance approach (Hahne, 1985; Francy et al., 1985; Lund, 1985; Satyamurty, 1985; Proctor, 1984a; Proctor; 1984b; Proctor, 1984c). It is important to note that this approach gives a very poor indication of how well a particular energy resource is being utilized by a given system to accomplish a specific objective. For example, it is difficult to examine the performance of solar thermal collectors versus solar-photovoltaic panels, strictly based on the first law of thermodynamics. A photovoltaic panel having ten percent first-law efficiency may be better than a solar collector converting 50 percent of useful energy by raising the water temperature from 30 to 50 C. Thus, it has been necessary to resort to the second law of thermodynamics for evaluation of solar systems, particularly collection devices. The second-law efficiency addresses the quality of energy. The quality of energy may be defined as its available portion; that portion which may be used for producing shaft work. It is important to note that the energy be conserved, but the manner in which energy is used must be examined. To use high quality energy for low-quality energy tasks is wasteful. This type of indication can only be examined from the second-law point of view. In this paper, measurements obtained from an experimental solar collector test facility are presented. Analysis of the performance of two flat-plate thermal solar collectors and one photovoltaic panel are analyzed based on both the first and second law of thermodynamics. The measurements presented, indicate very low second-law efficiency (maximum of 17 percent for photovoltaic panel and 11 percent for solar thermal flat-plate collectors), but are merely used as a vehicle for discussion.

Said, S.A.M.; Zubair, S.M. (King Fahd Univ. of Petroleum and Minerals, Dhahran (Saudi Arabia))

1993-02-01T23:59:59.000Z

302

DEVELOPMENT OF A MACRO-BATCH QUALIFICATION STRATEGY FOR THE HANFORD TANK WASTE TREATMENT AND IMMOBILIZATION PLANT  

Science Conference Proceedings (OSTI)

The Savannah River National Laboratory (SRNL) has evaluated the existing waste feed qualification strategy for the Hanford Tank Waste Treatment and Immobilization Plant (WTP) based on experience from the Savannah River Site (SRS) Defense Waste Processing Facility (DWPF) waste qualification program. The current waste qualification programs for each of the sites are discussed in the report to provide a baseline for comparison. Recommendations on strategies are then provided that could be implemented at Hanford based on the successful Macrobatch qualification strategy utilized at SRS to reduce the risk of processing upsets or the production of a staged waste campaign that does not meet the processing requirements of the WTP. Considerations included the baseline WTP process, as well as options involving Direct High Level Waste (HLW) and Low Activity Waste (LAW) processing, and the potential use of a Tank Waste Characterization and Staging Facility (TWCSF). The main objectives of the Hanford waste feed qualification program are to demonstrate compliance with the Waste Acceptance Criteria (WAC), determine waste processability, and demonstrate unit operations at a laboratory scale. Risks to acceptability and successful implementation of this program, as compared to the DWPF Macro-Batch qualification strategy, include: ? Limitations of mixing/blending capability of the Hanford Tank Farm; ? The complexity of unit operations (i.e., multiple chemical and mechanical separations processes) involved in the WTP pretreatment qualification process; ? The need to account for effects of blending of LAW and HLW streams, as well as a recycle stream, within the PT unit operations; and ? The reliance on only a single set of unit operations demonstrations with the radioactive qualification sample. This later limitation is further complicated because of the 180-day completion requirement for all of the necessary waste feed qualification steps. The primary recommendations/changes include the following: ? Collection and characterization of samples for relevant process analytes from the tanks to be blended during the staging process; ? Initiation of qualification activities earlier in the staging process to optimize the campaign composition through evaluation from both a processing and glass composition perspective; ? Definition of the parameters that are important for processing in the WTP facilities (unit operations) across the anticipated range of wastes and as they relate to qualification-scale equipment; ? Performance of limited testing with simulants ahead of the waste feed qualification sample demonstration as needed to determine the available processing window for that campaign; and ? Demonstration of sufficient mixing in the staging tank to show that the waste qualification sample chemical and physical properties are representative of the transfers to be made to WTP. Potential flowcharts for derivatives of the Hanford waste feed qualification process are also provided in this report. While these recommendations are an extension of the existing WTP waste qualification program, they are more in line with the processes currently performed for SRS. The implementation of these processes at SRS has been shown to offer flexibility for processing, having identified potential processing issues ahead of the qualification or facility processing, and having provided opportunity to optimize waste loading and throughput in the DWPF.

Herman, C.

2013-09-30T23:59:59.000Z

303

Waste Management Program. Technical progress report, October-December 1982  

SciTech Connect

This quarterly report provides current information on operations and development programs for the management of radioactive wastes from operation of the Savannah River Plant and offplant participants. The studies on environmental and safety assessments, in situ storage or disposal, waste from development and characterization, process and equipment development, and low-level waste management 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

1983-07-01T23:59:59.000Z

304

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

Science Conference Proceedings (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

305

Physical, Chemical and Structural Evolution of Zeolite - Containing Waste Forms Produced from Metakaolinite and Calcined HLW  

Science Conference Proceedings (OSTI)

During the seventh year of the current grant (DE-FG02-05ER63966) we completed an exhaustive study of cold calcination and began work on the development of tank fill materials to fill empty tanks and control residuals. Cold calcination of low and high NOx low activity waste (LAW) SRS Tank 44 and Hanford AN-107 simulants, respectively with metallic Al + Si powders was evaluated. It was found that a combination of Al and Si powders could be used as reducing agents to reduce the nitrate and nitrite content of both low and high NOx LAW to low enough levels to allow the LAW to be solidified directly by mixing it with metakaolin and allowing it to cure at 90 C. During room temperature reactions, NOx was reduced and nitrogen was emitted as N2 or NH3. This was an important finding because now one can pretreat LAW at ambient temperatures which provides a low-temperature alternative to thermal calcination. The significant advantage of using Al and Si metals for denitration/denitrition of the LAW is the fact that the supernate could potentially be treated in situ in the waste tanks themselves. Tank fill materials based upon a hydroceramic binder have been formulated from mixtures of metakaolinite, Class F fly ash and Class C flue gas desulphurization (FGD) ash mixed with various concentrations of NaOH solution. These harden over a period of hours or days depending on composition. A systematic study of properties of the tank fill materials (leachability) and ability to adsorb and hold residuals is under way.

Grutzeck, Michael

2005-06-01T23:59:59.000Z

306

Conservation and the Law: A Dictionary  

E-Print Network (OSTI)

Conservation and the Law: A Dictionary By Debra L. DonahueConservation and The Law: A Dictionary. Santa Barbara, CA:to Environment and the Law: A Dictionary (1995), which is a

Johnson, William T.

1999-01-01T23:59:59.000Z

307

Waste= Capital.  

E-Print Network (OSTI)

??The evolution of manufacturing practices over the last century has led to the creation of excess waste during the production process, depleting resources and overwhelming… (more)

Stidham, Steve P.

2011-01-01T23:59:59.000Z

308

Successful Use of Remote Engineering Technology to Upgrade Electrical Power Supplies to a Plant Producing Vitrified Highly Active Waste  

Science Conference Proceedings (OSTI)

This paper describes a remote handling intervention project on the Sellafield site in the UK that successfully replaced a critical part of a critical plant in a highly radioactive and contaminated cell. The aim of the project was to replace the existing design of electrical power supplies inside the plant that vitrifies high level liquid waste with a new improved design. The project designed and built a hydraulic manipulator and associated work-heads and tooling to be deployed in cell to remotely replace the power supplies. As part of this replacement process, the project also designed and built a drilling rig to remotely drill holes through the cell wall suitable for the new design of electrical power supplies. (authors)

Harken, J.P. [Nexia Solutions Ltd, Workington, Cumbria CA (United Kingdom)

2007-07-01T23:59:59.000Z

309

Solar and Wind Easements & Rights Laws & Local Option Solar Rights...  

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

and Wind Easements & Rights Laws & Local Option Solar Rights Law Solar and Wind Easements & Rights Laws & Local Option Solar Rights Law Eligibility Agricultural Commercial Fed....

310

Gas Safety Law (Florida) | Department of Energy  

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

Gas Safety Law (Florida) Gas Safety Law (Florida) Eligibility Commercial Construction Industrial Investor-Owned Utility MunicipalPublic Utility Retail Supplier Rural Electric...

311

Laws & Legal Resources | Department of Energy  

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

Resources Laws DOE Administers Guidance & Opinions General Counsel Law Library Research Guides LLRX Provides articles dealing with legal research in a number of subject and...

312

Solar Easements & Rights Laws | Department of Energy  

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

Rights Laws Solar Easements & Rights Laws Eligibility Commercial Fed. Government Industrial Local Government Nonprofit Residential Schools State Government Savings For Heating &...

313

The Readable Delaware General Corporation Law  

E-Print Network (OSTI)

of the United States Internal Revenue Code, or any successorunder the United States internal revenue laws and whosesubsequent United States internal revenue law). Subchapter

LoPucki, Lynn

2013-01-01T23:59:59.000Z

314

Technetium Retention During LAW Vitrification  

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

Technetium Retention During Technetium Retention During LAW Vitrification Ian L. Pegg Vitreous State Laboratory The Catholic University of America Washington, DC November 18, 2010 Overview * Tc in borosilcate glass structure * Re as a surrogate for Tc * Summary of previous data on Tc incorporation into LAW glass * Summary of results from ongoing test program * Single-pass retention vs. retention with recycle * Tc volatilization during container filling Tc in LAW Glass Structure * Tc is present as Tc 7+ and Tc 4+ * Tc 7+ is dominant in more oxidized glasses and Tc 4+ is dominant in reduced glasses * Strongly reducing conditions produce Tc 0 * The structure and local environment of Tc in WTP LAW glasses has been investigated by: * Synchrotron X-Ray Absorption Spectroscopy * Lukens, McKeown, Buechele, Muller, Shuh, and Pegg, Chem. Mater., 19, 559 (2007)

315

Public Law 104-134  

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

4-134 4-134 Debt Collection Improvement Act of 1996 (Public Law 104-134) Updated April 30, 1999 The President has signed into law historic legislation having a major impact on the way the Federal Government makes payments and collects its debts. Within the Omnibus Consolidated Rescissions and Appropriations Act of 1996 (Public Law 104-134) is the Debt Collection Improvement Act of 1996. The legislation provides an excellent opportunity for the Federal Government to move toward its goal of increased electronic commerce and improved cash and debt collection management. It is our intent to expeditiously implement the law to fulfill the Congressional mandate. The Act will enhance debt collection Government-wide, as well as mandate the use of electronic funds transfer (EFT) for Federal payments, allow Federal Reserve Bank

316

Louisiana Air Control Law (Louisiana)  

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

This law states regulations for air quality control and states the powers and duties of the secretary of environmental quality. It provides information about permits and licenses, air quality...

317

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

Science Conference Proceedings (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

318

OFF-GAS MERCURY CONTROL USING SULFUR-IMPREGNATED ACTIVATED CARBON – TEST RESULTS  

SciTech Connect

Several laboratory and pilot-scale tests since the year 2000 have included demonstrations of off-gas mercury control using fixed bed, sulfur-impregnated activated carbon. These demonstrations have included operation of carbon beds with gas streams containing a wide range of mercury and other gas species concentrations representing off-gas from several U.S. Department of Energy (DOE) mixed waste treatment processes including electrical resistance heated (joule-heated) glass melters, fluidized bed calciners, and fluidized bed steam reformers. Surrogates of various DOE mixed waste streams (or surrogates of offgas from DOE mixed waste streams) including INL “sodium bearing waste” (SBW), liquid “low activity waste” (LAW) from the Pacific Northwest National Laboratory, and liquid waste from Savannah River National Laboratory (“Tank 48H waste”) have been tested. Test results demonstrate mercury control efficiencies up to 99.999%, high enough to comply with the Hazardous Waste (HWC) Combustor Maximum Achievable Control Technology (MACT) standards even when the uncontrolled off-gas mercury concentrations exceed 400,000 ug/dscm (at 7% O2), and confirm carbon bed design parameters for such high efficiencies. Results of several different pilot-scale and engineering-scale test programs performed over several years are presented and compared.

Nick Soelberg

2007-05-01T23:59:59.000Z

319

MUSHROOM WASTE MANAGEMENT PROJECT LIQUID WASTE MANAGEMENT  

E-Print Network (OSTI)

#12;MUSHROOM WASTE MANAGEMENT PROJECT LIQUID WASTE MANAGEMENT PHASE I: AUDIT OF CURRENT PRACTICE The Mushroom Waste Management Project (MWMP) was initiated by Environment Canada, the BC Ministry of solid and liquid wastes generated at mushroom producing facilities. Environmental guidelines

320

SRS - Programs - Liquid Waste Disposition  

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

Liquid Waste Disposition Liquid Waste Disposition This includes both the solidification of highly radioactive liquid wastes stored in SRS's tank farms and disposal of liquid low-level waste generated as a by-product of the separations process and tank farm operations. This low-level waste is treated in the Effluent Treatment Facility. High-activity liquid waste is generated at SRS as by-products from the processing of nuclear materials for national defense, research and medical programs. The waste, totaling about 36 million gallons, is currently stored in 49 underground carbon-steel waste tanks grouped into two "tank farms" at SRS. While the waste is stored in the tanks, it separates into two parts: a sludge that settles on the bottom of the tank, and a liquid supernate that resides on top of the sludge. The waste is reduced to about 30 percent of its original volume by evaporation. The condensed evaporator "overheads" are transferred to the Effluent Treatment Project for final cleanup prior to release to the environment. As the concentrate cools a portion of it crystallizes forming solid saltcake. The concentrated supernate and saltcake are less mobile and therefore less likely to escape to the environment in the event of a tank crack or leak.

Note: This page contains sample records for the topic "activity waste law" 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

Hazardous waste management in the Pacific basin  

Science Conference Proceedings (OSTI)

Hazardous waste control activities in Asia and the Pacific have been reviewed. The review includes China (mainland, Hong Kong, and Taiwan), Indonesia, Korea, Malaysia, Papua New Guinea, the Philippines, Singapore, and Thailand. It covers the sources of hazardous waste, the government structure for dealing with hazardous waste, and current hazardous waste control activities in each country. In addition, the hazardous waste program activities of US government agencies, US private-sector organizations, and international organizations are reviewed. The objective of these reviews is to provide a comprehensive picture of the current hazardous waste problems and the waste management approaches being used to address them so that new program activities can be designed more efficiently.

Cirillo, R.R.; Chiu, S.; Chun, K.C.; Conzelmann, G. [Argonne National Lab., IL (United States); Carpenter, R.A.; Indriyanto, S.H. [East-West Center, Honolulu, HI (United States)

1994-11-01T23:59:59.000Z

322

ICDF Complex Operations Waste Management Plan  

SciTech Connect

This Waste Management Plan functions as a management and planning tool for managing waste streams generated as a result of operations at the Idaho CERCLA Disposal Facility (ICDF) Complex. The waste management activities described in this plan support the selected remedy presented in the Waste Area Group 3, Operable Unit 3-13 Final Record of Decision for the operation of the Idaho CERCLA Disposal Facility Complex. This plan identifies the types of waste that are anticipated during operations at the Idaho CERCLA Disposal Facility Complex. In addition, this plan presents management strategies and disposition for these anticipated waste streams.

W.M. Heileson

2006-12-01T23:59:59.000Z

323

Hanford Site Transuranic (TRU) Waste Certification Plan  

SciTech Connect

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

324

Hanford Site Transuranic (TRU) Waste Certification Plan  

SciTech Connect

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

325

WASTE DISPOSAL WORKSHOPS: ANTHRAX CONTAMINATED WASTE  

E-Print Network (OSTI)

WASTE DISPOSAL WORKSHOPS: ANTHRAX CONTAMINATED WASTE January 2010 Prepared for the Interagency DE-AC05-76RL01830 Waste Disposal Workshops: Anthrax-Contaminated Waste AM Lesperance JF Upton SL #12;#12;PNNL-SA-69994 Waste Disposal Workshops: Anthrax- Contaminated Waste AM Lesperance JF Upton SL

326

Utility Energy Service Contracts Laws and Regulations | Department of  

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

Contracts Laws and Regulations Contracts Laws and Regulations Utility Energy Service Contracts Laws and Regulations October 7, 2013 - 2:19pm Addthis The Energy Policy Act (EPAct) of 1992 authorizes and encourages Federal agencies to participate in utility energy efficiency programs. Legislation authorizing utility energy service contracts (UESCs) is outlined below, along with legal opinions outlining the use of UESCs by Federal agencies. Laws and Regulations 42 USC Section 8256 (Energy Policy Act of 1992): Incentives for Federal agencies, legislation addressing contracts, the Federal Energy Efficiency Fund, utility incentive programs, and the Financial Incentive Program for Facility Energy Managers. 10 USC Section 2913: Outlines energy savings contracts and related activities, shared energy savings contracts, participation in gas or

327

PUREX storage tunnels waste analysis plan  

SciTech Connect

Washington Administrative Code 173-303-300 requires that a facility develop and follow a written waste analysis plan which describes the procedures that will be followed to ensure that its dangerous waste is managed properly. This document covers the activities at the PUREX Storage Tunnels used to characterize and designate waste that is generated within the PUREX Plant, as well as waste received from other on-site sources.

Haas, C.R., Westinghouse Hanford

1996-07-10T23:59:59.000Z

328

Engineered waste-package-system design specification  

Science Conference Proceedings (OSTI)

This report documents the waste package performance requirements and geologic and waste form data bases used in developing the conceptual designs for waste packages for salt, tuff, and basalt geologies. The data base reflects the latest geotechnical information on the geologic media of interest. The parameters or characteristics specified primarily cover spent fuel, defense high-level waste, and commercial high-level waste forms. The specification documents the direction taken during the conceptual design activity. A separate design specification will be developed prior to the start of the preliminary design activity.

Not Available

1983-05-01T23:59:59.000Z

329

TRU waste acceptance criteria for the Waste Isolation Pilot Plant: Revision 3  

SciTech Connect

This document is intended to delineate the criteria by which unclassified waste will be accepted for emplacement at the Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico and describe the bases upon which these criteria were established. These criteria are not intended to be specifications but rather limits that will allow waste generating and shipping sites to develop their own procedures and specifications for preparation of TRU waste for shipment to the WIPP. These criteria will also allow waste generating sites to plan future facilities for waste preparation that will produce TRU waste forms compatible with WIPP waste emplacement and isolation requirements. These criteria only apply to contract-handled (CH) and remote-handled (RH) transuranic (TRU) waste forms and are not intended to apply to beta-gamma wastes, spent fuel, high-level waste (HLW), low-level waste (LLW), low specific activity (LSA) waste, or forms of radioactive waste for experimental purposes. Specifications for receipt of experimental waste forms will be prepared by the responsible projects in conjunction with the staff of the WIPP project at a later date. In addition, these criteria only apply to waste emplaced in bedded rock salt. Technical bases for these criteria may differ significantly from those for other host rocks. 25 refs. 4 figs., 1 tab.

1989-01-01T23:59:59.000Z

330

1989 Annual report on low-level radioactive waste management progress  

SciTech Connect

This report summarizes the progress during 1989 of states and compacts in establishing new low-level radioactive waste disposal facilities. It also provides summary information on the volume of low-level waste received for disposal in 1989 by commercially operated low-level waste disposal facilities. This report is in response to Section 7(b) of Title I of Public Law 99--240, the Low-Level Radioactive Waste Policy Amendments Act of 1985. 2 figs., 5 tabs.

Not Available

1990-10-01T23:59:59.000Z

331

Hanford Waste Treatment Plant Construction Quality Review  

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

ARPT-WTP-2011-002 Site: DOE Hanford Waste Treatment Plant Subject: Office of Independent Oversight's Office of Environment, Safety and Health Evaluations Activity Report for the...

332

Epsilon Metal Waste Form Development for Fission Products in ...  

Science Conference Proceedings (OSTI)

Radioactive Demonstrations of Fluidized Bed Steam Reforming (FBSR) with Hanford Low Activity Wastes · Radionuclide Behavior and Geochemistry in Boom  ...

333

Waste Hoist  

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

45-ton Rope-Guide Friction Hoist Completely enclosed (for contamination control), the waste hoist at WIPP is a modern friction hoist with rope guides. With a 45-ton capacity, it...

334

Conservation laws for the Maxwell-Dirac equations with a dual Ohm's law  

E-Print Network (OSTI)

Using a general theorem on conservation laws for arbitrary differential equations proved by Ibragimov, we have derived conservation laws for Dirac's symmetrized Maxwell-Lorentz equations under the assumption that both the electric and magnetic charges obey linear conductivity laws (dual Ohm's law). We find that this linear system allows for conservation laws which are non-local in time.

Nail H. Ibragimov; Raisa Khamitova; Bo Thidé

2007-03-05T23:59:59.000Z

335

CRAD, Radioactive Waste Management - June 22, 2009 | Department of Energy  

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

Radioactive Waste Management - June 22, 2009 Radioactive Waste Management - June 22, 2009 CRAD, Radioactive Waste Management - June 22, 2009 June 22, 2009 Radioactive Waste Management, Inspection Criteria, Approach, and Lines of Inquiry (HSS CRAD 64-33, Rev. 0) The following provides an overview of the typical activities that will be performed to collect information to evaluate the management of radioactive wastes and implementation of integrated safety management. The following Inspection Activities apply to all Inspection Criteria listed below: Review radioactive waste management and control processes and implementing procedures. Interview personnel including waste management supervision, staff, and subject matter experts. Review project policies, procedures, and corresponding documentation related to ISM core function

336

Strategic Environmental Research and Development Project FY 1994: Assessing national remote sensing technologies for use in US Department of Energy Environmental Restoration Activities, Oak Ridge Solid Waste Storage Area 4 case study  

SciTech Connect

During FY 1994, the Oak Ridge Environmental Restoration (ER) Remote Sensing Program teamed with members of the Oak Ridge National Security Program Office (NSPO), the Environmental Research Institute of Michigan (ERIM) under contract to the National Exploitation Laboratory (NEL), the Oak Ridge Waste Area Group 4 (WAG 4) ER Program, and the US Department of Energy (DOE), Offices of Technology Development, Nonproliferation and National Security, and Environmental Restoration, to conduct a test and demonstration of the uses of national remote sensing technologies at DOE hazardous waste sites located in Oak Ridge, Tennessee. Objectives of the Oak Ridge study were to determine if national remote sensing technologies are useful in conducting prescreening, characterization, and/or monitoring activities to expedite the clean-up process at hazardous waste sites and to cut clean-up costs wherever possible. This project was sponsored by the Strategic Environmental Research and Development Project (SERDP).

King, A.L.; Smyre, J.L.; Evers, T.K.

1995-02-01T23:59:59.000Z

337

Waste form product characteristics  

SciTech Connect

The Department of Energy has operated nuclear facilities at the Idaho National Engineering Laboratory (INEL) to support national interests for several decades. Since 1953, it has supported the development of technologies for the storage and reprocessing of spent nuclear fuels (SNF) and the resultant wastes. However, the 1992 decision to discontinue reprocessing of SNF has left nearly 768 MT of SNF in storage at the INEL with unspecified plans for future dispositioning. Past reprocessing of these fuels for uranium and other resource recovery has resulted in the production of 3800 M{sup 3} calcine and a total inventory of 7600 M{sup 3} of radioactive liquids (1900 M{sup 3} destined for immediate calcination and the remaining sodium-bearing waste requiring further treatment before calcination). These issues, along with increased environmental compliance within DOE and its contractors, mandate operation of current and future facilities in an environmentally responsible manner. This will require satisfactory resolution of spent fuel and waste disposal issues resulting from the past activities. A national policy which identifies requirements for the disposal of SNF and high level wastes (HLW) has been established by the Nuclear Waste Policy Act (NWPA) Sec.8,(b) para(3)) [1982]. The materials have to be conditioned or treated, then packaged for disposal while meeting US Environmental Protection Agency (EPA) and Nuclear Regulatory Commission (NRC) regulations. The spent fuel and HLW located at the INEL will have to be put into a form and package that meets these regulatory criteria. The emphasis of Idaho Chemical Processing Plant (ICPP) future operations has shifted toward investigating, testing, and selecting technologies to prepare current and future spent fuels and waste for final disposal. This preparation for disposal may include mechanical, physical and/or chemical processes, and may differ for each of the various fuels and wastes.

Taylor, L.L.; Shikashio, R.

1995-01-01T23:59:59.000Z

338

Resource Conservation and Recovery Act, Part B permit application [for the Waste Isolation Pilot Plant (WIPP)]. Volume 1, Revision 3  

Science Conference Proceedings (OSTI)

This volume includes the following chapters: Waste Isolation Pilot Plant RCRA A permit application; facility description; waste analysis plan; groundwater monitoring; procedures to prevent hazards; RCRA contingency plan; personnel training; corrective action for solid waste management units; and other Federal laws.

Not Available

1993-03-01T23:59:59.000Z

339

Proceedings of the 6th Annual Meeting for Excess Weapons Plutonium Disposition: Plutonium Packaging, Storage and Transportation and WasteTreatment, Storage and Disposal Activities  

SciTech Connect

The sixth annual Excess Weapons Plutonium Disposition meeting organized by Lawrence Livermore National Laboratory (LLNL) was held November 15-17, 2004, at the State Education Center (SEC), 4 Aerodromnya Drive, St. Petersburg, Russia. The meeting discussed Excess Weapons Plutonium Disposition topics for which LLNL has the US Technical Lead Organization responsibilities. The technical areas discussed included Radioactive Waste Treatment, Storage, and Disposal, and Plutonium Oxide and Plutonium Metal Packaging, Storage and Transportation and Spent Fuel Packaging, Storage and Transportation. The meeting was conducted with a conference format using technical presentations of papers with simultaneous translation into English and Russian. There were 55 Russian attendees from 16 different Russian organizations and four non-Russian attendees from the US. Forty technical presentations were made. The meeting agenda is given in Appendix B and the attendance list is in Appendix C. The 16 different Russian design, industrial sites, and scientific organizations in attendance included staff from Rosatom/Minatom, Federal Nuclear and Radiation Safety Authority of Russia (GOSATOMNADZOR, NIERA/GAN), All Russian Designing & Scientific Research Institute of Complex Power Technology (VNIPIET), Khlopin Radium Institute (KRI), A. A. Bochvar All Russian Scientific Research Institute of Inorganic Materials (VNIINM), All Russian & Design Institute of Production Engineering (VNIPIPT), Ministry of Atomic Energy of Russian Federation Specialized State Designing Institute (GSPI), State Scientific Center Research Institute of Atomic Reactors (RIAR), Siberian Chemical Combine Tomsk (SCC), Mayak PO, Mining Chemical Combine (MCC K-26), Institute of Biophysics (IBPh), Sverdlosk Scientific Research Institute of Chemical Machine Building (SNIIChM), Kurchatov Institute (KI), Institute of Physical Chemistry Russian Academy of Science (IPCh RAS) and Radon PO-Moscow. The four non-Russian attendees included one representative from DOE NNSA, and LLNL, and two from Duratek, The meeting was organized into three major sessions: (1) Waste Treatment, Storage and Disposal; (2) Plutonium Packaging, Storage and Transportation; (3) Spent Fuel Packaging, Storage and Transportation. Twenty presentations were made on the topic of Waste Treatment, Storage and Disposal (Session II), ten presentations on Plutonium Packaging, Storage and Transportation (Session III), and four presentations on Spent Fuel Packaging, Storage and Transportation (Session IV). In addition, DOE/NNSA, Minatom/Rosatom and TVEL summarized the bases for the conference at the beginning of the meeting (Session I). Nine months had passed since the last LLNL contracts review meeting. During that time period, LLNL and TVEL have been able to sign six contracts for a total of $1,700,000 in the areas of: (1) Waste treatment, storage and disposal; and (2) Plutonium packaging, storage and transportation. The scope of several other work projects are now in various stages of development in these areas. It is anticipated that more contracts will be signed before the next meeting of this type. These events have allowed us to start work in our technical activities under new direction from TVEL, which is now the single Russian organization to coordinate and conclude contracts with LLNL. The meeting presentations and discussions have defined where we are and where we are going in the near term in regard to our joint interests in excess weapons plutonium disposition. Each topical section of this Proceedings is introduced by a summary of the presentations in that section.

Jardine, L J

2005-06-30T23:59:59.000Z

340

Radioactive Waste Management BasisApril 2006  

Science Conference Proceedings (OSTI)

This Radioactive Waste Management Basis (RWMB) documents radioactive waste management practices adopted at Lawrence Livermore National Laboratory (LLNL) pursuant to Department of Energy (DOE) Order 435.1, Radioactive Waste Management. The purpose of this Radioactive Waste Management Basis is to describe the systematic approach for planning, executing, and evaluating the management of radioactive waste at LLNL. The implementation of this document will ensure that waste management activities at LLNL are conducted in compliance with the requirements of DOE Order 435.1, Radioactive Waste Management, and the Implementation Guide for DOE Manual 435.1-1, Radioactive Waste Management Manual. Technical justification is provided where methods for meeting the requirements of DOE Order 435.1 deviate from the DOE Manual 435.1-1 and Implementation Guide.

Perkins, B K

2011-08-31T23:59:59.000Z

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


341

Independent Oversight Activity Report for Catholic University of America Vitreous State Laboratory Tour and Discussion of Experiments Conducted in Support of Hanford Site Waste Treatment and Immobilization Plant Select Systems Design, November 18, 2013  

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

Report Number: HIAR-VSL-2013-11-18 Site: Catholic University of America - Vitreous State Laboratory (VSL) Subject: Office of Enforcement and Oversight's Office of Safety and Emergency Management Evaluations Activity Report for Catholic University of America Vitreous State Laboratory Tour and Discussion of Experiments Conducted in Support of Hanford Site Waste Treatment and Immobilization Plant Select Systems Design Date of Activity : 11/18/13 Report Preparer: James O. Low Activity Description/Purpose: Bechtel National, Inc. (BNI) is the contractor responsible for the design and construction of the Hanford Site Waste Treatment and Immobilization Plant (WTP) for the U.S. Department of Energy (DOE) Office of River Protection. BNI is

342

Federal Energy Management Program: Laws and Regulations  

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

Laws and Laws and Regulations to someone by E-mail Share Federal Energy Management Program: Laws and Regulations on Facebook Tweet about Federal Energy Management Program: Laws and Regulations on Twitter Bookmark Federal Energy Management Program: Laws and Regulations on Google Bookmark Federal Energy Management Program: Laws and Regulations on Delicious Rank Federal Energy Management Program: Laws and Regulations on Digg Find More places to share Federal Energy Management Program: Laws and Regulations on AddThis.com... Requirements by Subject Requirements by Regulation Notices & Rules Guidance Facility Reporting Fleet Reporting Laws and Regulations EISA 432 Compliance Tracking Track Federal agency progress toward Section 432 of the Energy Independence and Security Act (EISA) of 2007 using FEMP's EISA 432 Compliance Tracking

343

Bases for solid waste volume estimates for tank waste remediation system  

Science Conference Proceedings (OSTI)

This document presents the background and basis for the Tank Waste Remediation System forecast for solid waste submitted in June 1996. The forecast was generated for single-shell tank and double-shell tank activities including operations through retrieval and disposal of chemical tank waste.

Reddick, G.W., Westinghouse Hanford

1996-08-01T23:59:59.000Z

344

Hanford Facility Annual Dangerous Waste Report Calendar Year 2002  

Science Conference Proceedings (OSTI)

Hanford CY 2002 dangerous waste generation and management forms. The Hanford Facility Annual Dangerous Waste Report (ADWR) is prepared to meet the requirements of Washington Administrative Code Sections 173-303-220, Generator Reporting, and 173-303-390, Facility Reporting. In addition, the ADWR is required to meet Hanford Facility RCRA Permit Condition I.E.22, Annual Reporting. The ADWR provides summary information on dangerous waste generation and management activities for the Calendar Year for the Hanford Facility EPA ID number assigned to the Department of Energy for RCRA regulated waste, as well as Washington State only designated waste and radioactive mixed waste. The Solid Waste Information and Tracking System (SWITS) database is utilized to collect and compile the large array of data needed for preparation of this report. Information includes details of waste generated on the Hanford Facility, waste generated offsite and sent to Hanford for management, and other waste management activities conducted at Hanford, including treatment, storage, and disposal. Report details consist of waste descriptions and weights, waste codes and designations, and waste handling codes. In addition, for waste shipped to Hanford for treatment and/or disposal, information on manifest numbers, the waste transporter, the waste receiving facility, and the original waste generators are included. In addition to paper copies, electronic copies of the report are also transmitted to the regulatory agency.

FREEMAN, D.A.

2003-02-01T23:59:59.000Z

345

Management of offshore wastes in the United States.  

SciTech Connect

During the process of finding and producing oil and gas in the offshore environment operators generate a variety of liquid and solid wastes. Some of these wastes are directly related to exploration and production activities (e.g., drilling wastes, produced water, treatment workover, and completion fluids) while other types of wastes are associated with human occupation of the offshore platforms (e.g., sanitary and domestic wastes, trash). Still other types of wastes can be considered generic industrial wastes (e.g., scrap metal and wood, wastes paints and chemicals, sand blasting residues). Finally, the offshore platforms themselves can be considered waste materials when their useful life span has been reached. Generally, offshore wastes are managed in one of three ways--onsite discharge, injection, or transportation to shore. This paper describes the regulatory requirements imposed by the government and the approaches used by offshore operators to manage and dispose of wastes in the US.

Veil, J. A.

1998-10-22T23:59:59.000Z

346

Oversight Reports - Waste Isolation Pilot Plant | Department of Energy  

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

Oversight Reports - Waste Isolation Pilot Plant Oversight Reports - Waste Isolation Pilot Plant Oversight Reports - Waste Isolation Pilot Plant April 22, 2013 Independent Oversight Review, Waste Isolation Pilot Plant - April 2013 Review of the Waste Isolation Pilot Plant Work Planning and Control Activities November 28, 2012 Independent Oversight Review, Waste Isolation Pilot Plant - November 2012 Review of Site Preparedness for Severe Natural Phenomena Events at the Waste Isolation Pilot Plant September 28, 2011 Independent Activity Report, Waste Isolation Pilot Plant - September 2011 Orientation Visit to the Waste Isolation Pilot Plant [HIAR-WIPP-2011-09-07] October 2, 2002 Independent Oversight Inspection, Waste Isolation Pilot Plant, Summary Report - August 2002 Inspection of Environment, Safety, and Health and Emergency Management at

347

Understanding Cement Waste Forms  

Science Conference Proceedings (OSTI)

Oct 29, 2009 ... Ongoing nuclear operations, decontamination and decommissioning, salt waste disposal, and closure of liquid waste tanks result in ...

348

Waste Minimization Contents  

Science Conference Proceedings (OSTI)

About the 1996 International Symposium on Extraction and Processing for the Treatment and Minimization of Wastes: Waste Minimization Contents ...

349

Waste Isolation Pilot Plant Biennial Environmental Compliance Report  

SciTech Connect

This Biennial Environmental Compliance Report (BECR) documents environmental regulatory compliance at the Waste Isolation Pilot Plant (WIPP), a facility designed and authorized for the safe disposal of transuranic (TRU) radioactive waste, for the reporting period of April 1, 2002, to March 31, 2004. As required by the WIPP Land Withdrawal Act (LWA) (Public Law [Pub. L.] 102-579, as amended by Pub. L. 104-201), the BECR documents U.S. Department of Energy (DOE) compliance with applicable environmental protection laws and regulations implemented by agencies of the federal government and the state of New Mexico.

Washington Regulatory and Environmental Services (WRES)

2004-10-25T23:59:59.000Z

350

Constructing Gender Through Sex Discrimination Law  

E-Print Network (OSTI)

for a New Conception of Gender Identity in the Law. ColumbiaMedicine, Re/modeling Gender. Berkeley Women's Law Journal,Review, 26, 1395. Kosbie, J. Gender Identity Expression as

Kosbie, Jeff

2011-01-01T23:59:59.000Z

351

An Economics-Based Second Law Efficiency  

E-Print Network (OSTI)

Second Law efficiency is a useful parameter for characterizing the energy requirements of a system in relation to the limits of performance prescribed by the Laws of Thermodynamics. However, since energy costs typically ...

Mistry, Karan Hemant

352

CEPM 4: optimization of the waste management for construction projects using simulation  

Science Conference Proceedings (OSTI)

Growth in construction activities increases the amount of construction waste generated. Recycling of construction waste is an important component of environmentally responsible construction, as it reduces the amount of waste directed to landfills. In ...

Mala Chandrakanthi; Patrick Hettiaratchi; Bolívar Prado; Janaka Y. Ruwanpura

2002-12-01T23:59:59.000Z

353

Transportation functions of the Civilian Radioactive Waste Management System  

SciTech Connect

Within the framework of Public Law 97.425 and provisions specified in the Code of Federal Regulations, Title 10 Part 961, the US Department of Energy has the responsibility to accept and transport spent fuel and high-level waste from various organizations which have entered into a contract with the federal government in a manner that protects the health and safety of the public and workers. In implementing these requirements, the Office of Civilian Radioactive Waste Management (OCRWM) has, among other things, supported the identification of functions that must be performed by a transportation system (TS) that will accept the waste for transport to a federal facility for storage and/or disposal. This document, through the application of system engineering principles, identifies the functions that must be performed to transport waste under this law.

Shappert, L.B. (ed.); Attaway, C.R.; Pope, R.B. (Oak Ridge National Lab., TN (United States)); Best, R.E.; Danese, F.L. (Science Applications International Corp., Oak Ridge, TN (United States)); Dixon, L.D. (Dixon (L.D.), Martinez, GA (United States)); Jones, R.H. (Jones (R.H.), Los Gatos, CA (United States)); Klimas, M.J. (USDOE Chicago Operations Office, Argonne, IL (United States)); Peterson, R.W

1992-03-01T23:59:59.000Z

354

Conservation laws for a general Lorentz connection  

E-Print Network (OSTI)

We derive conservation laws for energy-momentum (canonical and dynamical) and angular momentum for a general Lorentz connection.

Poplawski, Nikodem J

2007-01-01T23:59:59.000Z

355

Law Enforcement & Emergency Management Liaison | National Nuclear...  

National Nuclear Security Administration (NNSA)

Law Enforcement & Emergency Management Liaison | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy...

356

Price's Law on Nonstationary Spacetimes  

E-Print Network (OSTI)

In this article we study the pointwise decay properties of solutions to the wave equation on a class of nonstationary asymptotically flat backgrounds in three space dimensions. Under the assumption that uniform energy bounds and a weak form of local energy decay hold forward in time we establish a $t^{-3}$ local uniform decay rate (Price's law \\cite{MR0376103}) for linear waves. As a corollary, we also prove Price's law for certain small perturbations of the Kerr metric. This result was previously established by the second author in \\cite{Tat} on stationary backgrounds. The present work was motivated by the problem of nonlinear stability of the Kerr/Schwarzschild solutions for the vacuum Einstein equations, which seems to require a more robust approach to proving linear decay estimates.

Metcalfe, Jason; Tohaneanu, Mihai

2011-01-01T23:59:59.000Z

357

Law of Conservation of Muons  

DOE R&D Accomplishments (OSTI)

A multiplicative selection rule for mu meson-electron transitions is proposed. A "muon parity" = -1 is considered for the muon and its neutrino, while the "muon parity" for all other particles is +1. The selection rule then states that (-1) exp(no. of initial (-1) parity particles) = (-1) exp(no. of final (-1) parity particles). Several reactions that are forbidden by an additive law but allowed by the multiplicative law are suggested; these reactions include mu{sup +} .> e{sup +} + nu{sub mu} + {ovr nu}{sub e}, e{sup -} + e{sup -} .> mu{sup -} + mu{sup -}, and muonium .> antimuonium (mu{sup +} + e{sup -} .> mu{sup -} + e{sup +}). An intermediate-boson hypothesis is suggested. (T.F.H.)

Feinberg, G.; Weinberg, S.

1961-02-00T23:59:59.000Z

358

A logical model of private international law  

Science Conference Proceedings (OSTI)

We provide a logical analysis of private international law, the body of law establishing when courts of a country should decide a case (jurisdiction) and what legal system they should apply to this purpose (choice of law). A formal model of the resulting ...

Phan Minh Dung; Giovanni Sartor

2010-07-01T23:59:59.000Z

359

Law  

National Nuclear Security Administration (NNSA)

rate - c g is the crack propagation speed - c l is the longitudinal elastic wave speed. - R s is the radius of the volume relieved by the crack, taken as a function of the...

360

Law  

National Nuclear Security Administration (NNSA)

to Census: t cens - Number of Mean-Free Paths to Collision: N mfp - Random Number Seed: R seed - Miscellaneous Attributes: number of collisions, last event, breed, domain, cell,...

Note: This page contains sample records for the topic "activity waste law" 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

Law  

National Nuclear Security Administration (NNSA)

- spatial refinement - Relatively simple interlevel operators - Clean Lagrangian hydro 5LC 2005 rbp. 36 Current Limitations * No support yet for: - Parallel problem...

362

The Effects of Lithium Nitrate on Highly Active Liquor in the ...  

Science Conference Proceedings (OSTI)

... of Fluidized Bed Steam Reforming (FBSR) with Hanford Low Activity Wastes ... Level Waste at the Defense Waste Processing Facility through Sludge Batch 7b.

363

Hanford Site waste treatment/storage/disposal integration  

SciTech Connect

In 1998 Waste Management Federal Services of Hanford, Inc. began the integration of all low-level waste, mixed waste, and TRU waste-generating activities across the Hanford site. With seven contractors, dozens of generating units, and hundreds of waste streams, integration was necessary to provide acute waste forecasting and planning for future treatment activities. This integration effort provides disposition maps that account for waste from generation, through processing, treatment and final waste disposal. The integration effort covers generating facilities from the present through the life-cycle, including transition and deactivation. The effort is patterned after the very successful DOE Complex EM Integration effort. Although still in the preliminary stages, the comprehensive onsite integration effort has already reaped benefits. These include identifying significant waste streams that had not been forecast, identifying opportunities for consolidating activities and services to accelerate schedule or save money; and identifying waste streams which currently have no path forward in the planning baseline. Consolidation/integration of planned activities may also provide opportunities for pollution prevention and/or avoidance of secondary waste generation. A workshop was held to review the waste disposition maps, and to identify opportunities with potential cost or schedule savings. Another workshop may be held to follow up on some of the long-term integration opportunities. A change to the Hanford waste forecast data call would help to align the Solid Waste Forecast with the new disposition maps.

MCDONALD, K.M.

1999-02-24T23:59:59.000Z

364

Law-066812 - Argonne National Laboratories, Materials Sicence Division  

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

Law-066812 Law-066812 MATERIALS SCIENCE COLLOQUIUM SPEAKER: PROF. MATT LAW University of California - Irvine TITLE: "Developing Earth Abundant and Quantum Dot Materials for Thin-Film Photovoltaics" DATE: Thursday, June 28, 2012 TIME: 11:00 a.m. PLACE: Building 212 / A-157 HOST: TBA Refreshments will be served at 10:45 a.m. ABSTRACT: This talk describes projects in our group to develop thin-film photovoltaics based on earth-abundant iron pyrite (FeS2) active layers and PbSe quantum dot (QD) solids. I will first introduce the promise and challenge of pyrite, describe solution- and gas-phase syntheses of pyrite films, and present preliminary electrical characterization of pyrite layers and device stacks. Then I will switch gears to highlight several projects

365

Radioactive Waste Management BasisSept 2001  

SciTech Connect

This Radioactive Waste Management Basis (RWMB) documents radioactive waste management practices adopted at Lawrence Livermore National Laboratory (LLNL) pursuant to Department of Energy (DOE) Order 435.1, Radioactive Waste Management. The purpose of this RWMB is to describe the systematic approach for planning, executing, and evaluating the management of radioactive waste at LLNL. The implementation of this document will ensure that waste management activities at LLNL are conducted in compliance with the requirements of DOE Order 435.1, Radioactive Waste Management, and the Implementation Guide for DOE manual 435.1-1, Radioactive Waste Management Manual. Technical justification is provided where methods for meeeting the requirements of DOE Order 435.1 deviate from the DOE Manual 435.1-1 and Implementation Guide.

Goodwin, S S

2011-08-31T23:59:59.000Z

366

WASTE TO WATTS Waste is a Resource!  

E-Print Network (OSTI)

WASTE TO WATTS Waste is a Resource! energy forum Case Studies from Estonia, Switzerland, Germany BREFs and their BATs Next Generation of Waste Fired Power Plants: Getting the most out of your trash Bossart,· ABB Waste-to-Energy Plants Edmund Fleck,· ESWET Marcel van Berlo,· Afval Energie Bedrijf From

Columbia University

367

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

SciTech Connect

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

COZZI, ALEX

2004-02-18T23:59:59.000Z

368

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

SciTech Connect

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

COZZI, ALEX

2004-02-18T23:59:59.000Z

369

Environmental Restoration and Waste Management: Strategic plan  

Science Conference Proceedings (OSTI)

The Brookhaven National Laboratory (BNL) site is currently divided into five major areas, Operable Units (OUs), and several Areas of Concern (AOCs), which are the focus of investigation and clean-up. The primary environmental concern is groundwater contamination and a major emphasis of the restoration activities is focused on this medium. Each year, BNL generates 60 tons of hazardous waste and 7,000 to 8,000 cubic feet of radioactive waste that result from research activities. These wastes are collected at a central location, packaged and shipped off site for disposal. The operations for Hazardous and Radioactive Waste Management are conducted in compliance with EPA and DOE regulations. BNL has continued to actively pursue means by which these wastes may be minimized. Activities in both the remediation and waste management arenas are intimately connected with the future vision of BNL. The long-range goal for remediation in conjunction with vigorous monitoring of BNL`s activities is to restore the site and maintain strong environmental controls. The goals of the waste minimization program include activities to find environmentally safe alternatives to materials currently in use. By careful planning, BNL will minimize the amount of all waste, including sanitary, that is generated on site.

Not Available

1994-09-01T23:59:59.000Z

370

Borosilicate Glass Formulations for CCIM  

Hanford AZ-101 high-level waste (HLW) Hanford AN-105 low-activity waste (LAW) 3. Selection of Wastes Initially focused on Hanford waste streams

371

Categorical Exclusion 4565, Waste Management Construction Support  

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

FornI FornI Project Title: Waste Management Construction Support (4565) Program or Program Office: Y -12 Site Office Location: Oak Ridge Tennessee Project Description: This work scope is an attempt to cover the general activities that construction would perform in support of Waste Management activities. Work includes construction work performed in support of Waste Management Sustainability and Stewardship projects and programs to include: load waste into containers; open, manipulate containers; empty containers; decommission out-of-service equipment (includes removal of liquids, hazardous, and universal wastes); apply fabric and gravel to ground; transport equipment; transport materials; transport waste; remove vegetation; place barriers; place erosion controls; operate wheeled and tracked equipment; general carpentry. Work will be performed on dirt, vegetated, graveled, or paved surfaces in

372

Excellence in radioactive waste volume reduction  

SciTech Connect

The Brunswick plant is a two-unit boiling water reactor located at the mouth of the Cape Fear River near Wilmington, North Carolina. The plant has a once-through cooling system with highly brackish water. The operations subunit is responsible for liquid radwaste processing. The radiation control subunit is responsible for dry active waste processing and the transportation of all radioactive wast off-site. For the Brunswick plant, the development of an effective radioactive waste volume reduction program was a process involving a tremendous amount of grass-roots worker participation. With radioactive waste responsibilities divided between two separate groups, this process took place on a somewhat different schedule for liquid process waste and dry active waste. However, this development process did not begin until dedicated personnel were assigned to manage radwaste independently of other plant duties.

Henderson, J.

1987-01-01T23:59:59.000Z

373

DURABILITY TESTING OF FLUIDIZED BED STEAM REFORMER WASTE FORMS FOR SODIUM BEARING WASTE AT IDAHO NATIONAL LABORATORY  

SciTech Connect

Fluidized Bed Steam Reforming (FBSR) processing of Sodium Bearing Waste simulants was performed in December 2006 by THOR{sup sm} Treatment Technologies LLC (TTT) The testing was performed at the Hazen Research Inc. (HRI) pilot plant facilities in Golden, CO. FBSR products from these pilot tests on simulated waste representative of the SBW at the Idaho Nuclear Technology and Engineering Center (INTEC) were subsequently transferred to the Savannah River National Laboratory (SRNL) for characterization and leach testing. Four as-received Denitration and Mineralization Reformer (DMR) granular/powder samples and four High Temperature Filter (HTF) powder samples were received by SRNL. FBSR DMR samples had been taken from the ''active'' bed, while the HTF samples were the fines collected as carryover from the DMR. The process operated at high fluidizing velocities during the mineralization test such that nearly all of the product collected was from the HTF. Active bed samples were collected from the DMR to monitor bed particle size distribution. Characterization of these crystalline powder samples shows that they are primarily Al, Na and Si, with > 1 wt% Ca, Fe and K. The DMR samples contained less than 1 wt% carbon and the HTF samples ranged from 13 to 26 wt% carbon. X-ray diffraction analyses show that the DMR samples contained significant quantities of the Al{sub 2}O{sub 3} startup bed. The DMR samples became progressively lower in starting bed alumina with major Na/Al/Si crystalline phases (nepheline and sodium aluminosilicate) present as cumulative bed turnover occurred but 100% bed turnover was not achieved. The HTF samples also contained these major crystalline phases. Durability testing of the DMR and HTF samples using the ASTM C1285 Product Consistency Test (PCT) 7-day leach test at 90 C was performed along with several reference glass samples. Comparison of the normalized leach rates for the various DMR and HTF components was made with the reference glasses and the Low Activity Waste (LAW) specification for the Hanford Waste Treatment and Vitrification Plant (WTP). Normalized releases from the DMR and HTF samples were all less than 1 g/m{sup 2}. For comparison, normalized release from the High-Level Waste (HLW) benchmark Environmental Assessment (EA) glass for Si, Li, Na and B ranges from 2 to 8 g/m{sup 2}. The normalized release specification for LAW glass for the Hanford WTP is 2 g/m{sup 2}. The Toxicity Characteristic Leach Test (TCLP) was performed on DMR and HTF as received samples and the tests showed that these products meet the criteria for the EPA RCRA Universal Treatment Standards for all of the constituents contained in the starting simulants such as Cr, Pb and Hg (RCRA characteristically hazardous metals) and Ni and Zn (RCRA metals required for listed wastes).

Crawford, C; Carol Jantzen, C

2007-08-27T23:59:59.000Z

374

HANFORD FACILITY ANNUAL DANGEROUS WASTE REPORT CY2005  

Science Conference Proceedings (OSTI)

The Hanford Facility Annual Dangerous Waste Report (ADWR) is prepared to meet the requirements of Washington Administrative Code Sections 173-303-220, Generator Reporting, and 173-303-390, Facility Reporting. In addition, the ADWR is required to meet Hanford Facility RCR4 Permit Condition I.E.22, Annual Reporting. The ADWR provides summary information on dangerous waste generation and management activities for the Calendar Year for the Hanford Facility EPA ID number assigned to the Department of Energy for RCRA regulated waste, as well as Washington State only designated waste and radioactive mixed waste. An electronic database is utilized to collect and compile the large array of data needed for preparation of this report. Information includes details of waste generated on the Hanford Facility, waste generated offsite and sent to Hanford for management, and other waste management activities conducted at Hanford, including treatment, storage, and disposal. Report details consist of waste descriptions and weights, waste codes and designations, and waste handling codes, In addition, for waste shipped to Hanford for treatment and/or disposal, information on manifest numbers, the waste transporter, the waste receiving facility, and the original waste generators are included. In addition to paper copies, the report is also transmitted electronically to a web site maintained by the Washington State Department of Ecology.

SKOLRUD, J.O.

2006-02-15T23:59:59.000Z

375

GP-8 LAWS AND REGULATIONS  

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

DOP (5-2011) DOP (5-2011) Supersedes (7-2010) issue DECLARATION of OCCUPATIONAL MEDICINE PROVIDER GENERAL INFORMATION PURPOSE All Contractors and their lower-tier subcontractors must comply with the Department of Energy's Worker Safety and Health Program regulation, 10 CFR 851, "Worker Safety and Health Program (WSHP). The WSHP enforces worker safety and health requirements including, but not limited to, standards of the Occupational Safety and Health Administration (OSHA), American National Standards Institute (ANSI) and Workers Compensation Laws as incorporated in the SNL WSHP. APPLICABILITY Contractors at all tiers which meet the applicability criteria must establish and provide comprehensive

376

Simple laws of urban growth  

E-Print Network (OSTI)

By analysing the evolution of the street network of Greater London from the late 1700s to the present, we are able to shed light on the inner mechanisms that lie behind the growth of a city. First we define an object called a city as a spatial discontinuous phenomena, from clustering the density of street intersections. Second, we find that the city growth mechanisms can be described by two logistic laws, hence can be determined by a simple model of urban network growth in the presence of competition for limited space.

Masucci, Paolo; Batty, Michael

2012-01-01T23:59:59.000Z

377

Waste Hoist  

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

Primary Hoist: 45-ton Rope-Guide Friction Hoist Largest friction hoist in the world when it was built in 1985 Completely enclosed (for contamination control), the waste hoist at WIPP is a modern friction hoist with rope guides (uses a balanced counterweight and tail ropes). With a 45-ton capacity, it was the largest friction hoist in the world when it was built in 1986. Hoist deck footprint: 2.87m wide x 4.67m long Hoist deck height: 2.87m wide x 7.46m high Access height to the waste hoist deck is limited by a high-bay door at 4.14m high Nominal configuration is 2-cage (over/under), with bottom (equipment) cage interior height of 4.52m The photo, at left, shows the 4.14m high-bay doors at the top collar of the waste hoist shaft. The perpendicular cross section of the opening is 3.5m x 4.14m, but the bottom cage cross section is 2.87m x 4.5m (and 4.67m into the plane of the photo).

378

Renewable Energy Easements & Rights Laws | Department of Energy  

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

Easements & Rights Laws Renewable Energy Easements & Rights Laws Eligibility Commercial Industrial Residential Savings For Heating & Cooling Commercial Heating & Cooling Solar...

379

Liquid and Gaseous Waste Operations Department annual operating report CY 1996  

SciTech Connect

This annual report summarizes operating activities dealing with the process waste system, the liquid low-level waste system, and the gaseous waste system. It also describes upgrade activities dealing with the process and liquid low-level waste systems, the cathodic protection system, a stack ventilation system, and configuration control. Maintenance activities are described dealing with nonradiological wastewater treatment plant, process waste treatment plant and collection system, liquid low-level waste system, and gaseous waste system. Miscellaneous activities include training, audits/reviews/tours, and environmental restoration support.

Maddox, J.J.; Scott, C.B.

1997-03-01T23:59:59.000Z

380

Baseline Glass Development for Combined Fission Products Waste Streams  

SciTech Connect

Borosilicate glass was selected as the baseline technology for immobilization of the Cs/Sr/Ba/Rb (Cs), lanthanide (Ln) and transition metal fission product (TM) waste steams as part of a cost benefit analysis study.[1] Vitrification of the combined waste streams have several advantages, minimization of the number of waste forms, a proven technology, and similarity to waste forms currently accepted for repository disposal. A joint study was undertaken by Pacific Northwest National Laboratory (PNNL) and Savannah River National Laboratory (SRNL) to develop acceptable glasses for the combined Cs + Ln + TM waste streams (Option 1) and Cs + Ln combined waste streams (Option 2) generated by the AFCI UREX+ set of processes. This study is aimed to develop baseline glasses for both combined waste stream options and identify key waste components and their impact on waste loading. The elemental compositions of the four-corners study were used along with the available separations data to determine the effect of burnup, decay, and separations variability on estimated waste stream compositions.[2-5] Two different components/scenarios were identified that could limit waste loading of the combined Cs + LN + TM waste streams, where as the combined Cs + LN waste stream has no single component that is perceived to limit waste loading. Combined Cs + LN waste stream in a glass waste form will most likely be limited by heat due to the high activity of Cs and Sr isotopes.

Crum, Jarrod V.; Billings, Amanda Y.; Lang, Jesse B.; Marra, James C.; Rodriguez, Carmen P.; Ryan, Joseph V.; Vienna, John D.

2009-06-29T23:59:59.000Z

Note: This page contains sample records for the topic "activity waste law" 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.


381

Medical School Biomedical Waste  

E-Print Network (OSTI)

Medical School Biomedical Waste Labware, gloves, pipets, pipet tips Stock cultures, bacterial with or without needles, razor blades, scalpel blades) Key: Pathological waste BL1 & BL2 waste (low risk ­ LR) BL2 waste (moderate risk - MR)/BL3 waste Blood Blood Autoclave Needle box Metal Cart Must either bleach

Cooley, Lynn

382

University of Waste Procedures  

E-Print Network (OSTI)

University of Maryland Hazardous And Regulated Waste Procedures Manual Revised July 2001 #12;Review II. HAZARDOUS WASTE MANAGEMENT III. BIOLOGICAL, PATHOLOGICAL AND MEDICAL WASTE (BPMW) MANAGEMENT IV. LOW-LEVEL RADIOACTIVE WASTE (LLRW) MANAGEMENT V. EMERGENCY PROCEDURES VI. WASTE MINIMIZATION VII

Rubloff, Gary W.

383

DOE publishes guide to state and federal laws for ER projects  

SciTech Connect

The US Department of Energy has published a guide of federal and state environmental laws and regulations that affect enhanced recovery projects. The primary emphasis of the publication is on prevention and control of air and water pollution, protection of underground water sources, and management of solid wastes. Only laws and regulations that apply specifically to features unique to EOR, such as emissions for steam generators or underground injections of chemicals, are dealt with. The National Environmental Policy Act of 1979, the Coastal Zone Management Act, the Endangered Species Act, and the Noise Control Act, prinicpal federal laws affecting the siting or operation of EOR facilities, are listed in the handbook, and requirements under these laws are detailed. Tentative requirements under some environmental laws not yet implemented, such as the Underground Injection Control and Resource Conservation and Recovery Act, also are included. The relevant state environmental laws, regulation and permit requirements of 16 major oil-producing states where EOR techniques are important, or could become important, to future oil recovery, are included in the handbook (Alabama, California, Colorado, Illinois, Kansas, Kentucky, Louisiana, Mississippi, Montana, New Mexico, Ohio, Oklahoma, Pennsylvania, Texas, West Virginia, and Wyoming).

Not Available

1981-03-01T23:59:59.000Z

384

Borges Dilemma, Fundamental Laws, and Systems Biology  

E-Print Network (OSTI)

A well-known folk-law in biology is that there is no general law in biology because of exceptions. In her recent elegant essay E.F. Keller gave a particular nice presentation on the exceptions to rules or laws in biology [1]. Her example of scaling laws was especially illuminative. Nevertheless, for this cherished folk-law the present author is wondering about its exceptions, too. Several examples immediately jump into his minds. One, of course, would be the folk-law itself: It had no exception in biology. This would be a bit disappointing because it would only permit us to work as what the cartographers did in J.L. Borges ’ fable [2]. Though eventually a map as big and as detail as the empire itself might be obtained, one would then ask where is the understanding within such an immense object? More disappointedly, such folk-law is really not biological. It has been used by some philosophers to argue against the unity of science [3]. Another example is distinctively biological and would be more exciting, and the author believes its existence should be not surprising to biologists: Evolution by Variation and Selection by Darwin and Wallace. To the author’s knowledge this dynamical law has no exception in biology. Nevertheless, under the influence of above folk-law this marvelous dynamics has been named Darwin’s principle, just falling short to regard it as a fundamental law [4]. Any scientists and mathematicians would know better

Ping Ao

2008-01-01T23:59:59.000Z

385

Microsoft Word - Tank Waste Report 9-30-05.doc  

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

Accelerated Tank Waste Retrieval Accelerated Tank Waste Retrieval Activities at the Hanford Site DOE/IG-0706 October 2005 REPORT ON THE ACCELERATED TANK WASTE RETRIEVAL ACTIVITIES AT THE HANFORD SITE TABLE OF CONTENTS Tank Waste Retrieval Details of Finding 1 Recommendations and Comments 4 Appendices Objective, Scope, and Methodology 6 Prior Reports 7 Management Comments 8 Tank Waste Retrieval Page 1 Details of Finding Tank Waste The Department will not meet Tri-Party Agreement (Agreement) Retrieval Activities milestones for the retrieval of waste from the single-shell tanks located at the C-Tank Farm within schedule and cost. Based on the current C-Tank Farm retrieval schedule and the amount of waste retrieved to date, the Department will not accomplish its

386

WIPP waste acceptance criteria and transportation system  

Science Conference Proceedings (OSTI)

The Waste Isolation Pilot Plant (WIPP), located near Carlsbad, New Mexico, USA, is a US Department of Energy (DOE) facility designed as a permanent repository for transuranic wastes in the center of a 2,000-foot-thick salt bed situated 2,150 feet underground. Construction of the facility started in 1975, under a congressional act of site selection. In 1979, demonstration of safe disposal at the WIPP was authorized by Public Law 96-164. The operational philosophy and practice at the facility are: (1) start clean -- stay clean, (2) meet or exceed regulatory requirements, and (3) control radiation exposure levels to as low as reasonably achievable (ALARA). Strict safety measures must be taken in the areas of waste preparation, transportation, and facility operation.

Wu, C.F.; Ward, T.R.; Gregory, P.C.

1991-12-31T23:59:59.000Z

387

Democracy, Judicial Attitudes and Heterogeneity: The Civil Versus Common Law Tradition  

E-Print Network (OSTI)

law, instead, achieves the 9Implicit in (4) and (5), there is the assumption that both side transfers and collective action costs do not entail social wastes: relaxing it does not change the qualitative message of the model—see footnote 12. Only... the one under the mixed system where bright line rules are used. Discretion will be introduced if ? ?¯, the hybrid tradition prevails. Germany, Switzerland and the Scandinavian countries are examples...

Guerriero, C

388

SRS Public Involvement in Waste Management Has Resulted in Effective Decisions Supported by the Public Including Disposal Changes and Top-to-Bottom Review Initiative Consensus  

Science Conference Proceedings (OSTI)

In the Savannah River Site's (SRS') Solid Waste Management Program, a key to success is the Public Involvement Program. The Solid Waste Division at SRS manages the site's transuranic, low-level, mixed, and hazardous wastes. All decisions associated with management of this waste are of interest to the public and successful program implementation would be impossible without a vigorous public involvement program. The SRS Solid Waste Division (SWD) and its Department of Energy (DOE) customer developed, implemented, and maintain a comprehensive public participation and communications program. It is staffed by public participation and technical specialists to ensure information is presented in a manner that is technically accurate while being tailored for understanding by people without a technical background. The program provides the public with accurate, complete, timely information and early meaningful participation opportunities. It also fulfills the public participation activities required by laws, regulations, DOE Orders, and negotiated agreements. The primary goal of the SWD Public Participation Program is to fulfill the objectives of the SWD and SRS Strategic Plans to ''build trust and communicate openly, honestly, and responsibly with employees, customers, stakeholders, and regulators,'' and to ''work to extend the support of external stakeholders for the pursuit of SRS and DOE Complex business goals.'' This paper focuses on the public participation program goals, the implementation through formal plans and objectives, targeted waste management programs and specific audiences, and specific effects of the program on waste management activities. A discussion of the DOE and contractor teaming along with how plans are carried out is also included.

Goldston, W. T.; Villasor, H. P.

2003-02-27T23:59:59.000Z

389

Radioactive Waste Management (Minnesota)  

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

This section regulates the transportation and disposal of high-level radioactive waste in Minnesota, and establishes a Nuclear Waste Council to monitor the federal high-level radioactive waste...

390

Waste Management Program  

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

Waste Management Facility ISO 14001 Registered A wide range of wastes are generated during the normal course of business at BNL. These waste streams are common to many businesses...

391

The second laws of quantum thermodynamics  

E-Print Network (OSTI)

The second law of thermodynamics tells us which state transformations are so statistically unlikely that they are effectively forbidden. Its original formulation, due to Clausius, states that "Heat can never pass from a colder to a warmer body without some other change, connected therewith, occurring at the same time". The second law applies to systems composed of many particles interacting; however, we are seeing that one can make sense of thermodynamics in the regime where we only have a small number of particles interacting with a heat bath. Is there a second law of thermodynamics in this regime? Here, we find that for processes which are cyclic or very close to cyclic, the second law for microscopic systems takes on a very di?erent form than it does at the macroscopic scale, imposing not just one constraint on what state transformations are possible, but an entire family of constraints. In particular, we find a family of free energies which generalise the traditional one, and show that they can never increase. We further find that there are three regimes which determine which family of second laws govern state transitions, depending on how cyclic the process is. In one regime one can cause an apparent violation of the usual second law, through a process of embezzling work from a large system which remains arbitrarily close to its original state. These second laws are not only relevant for small systems, but also apply to individual macroscopic systems interacting via long-range interactions, which only satisfy the ordinary second law on average. By making precise the definition of thermal operations, the laws of thermodynamics take on a simple form with the first law defining the class of thermal operations, the zeroeth law emerging as a unique condition ensuring the theory is nontrivial, and the remaining laws being a monotonicity property of our generalised free energies.

Fernando G. S. L. Brandao; Micha? Horodecki; Nelly Huei Ying Ng; Jonathan Oppenheim; Stephanie Wehner

2013-05-22T23:59:59.000Z

392

Mixed Waste Focus Area program management plan  

SciTech Connect

This plan describes the program management principles and functions to be implemented in the Mixed Waste Focus Area (MWFA). The mission of the MWFA is to provide acceptable technologies that enable implementation of mixed waste treatment systems developed in partnership with end-users, stakeholders, tribal governments and regulators. The MWFA will develop, demonstrate and deliver implementable technologies for treatment of mixed waste within the DOE Complex. Treatment refers to all post waste-generation activities including sampling and analysis, characterization, storage, processing, packaging, transportation and disposal.

Beitel, G.A.

1996-10-01T23:59:59.000Z

393

Environmental restoration waste materials co-disposal  

Science Conference Proceedings (OSTI)

Co-disposal of radioactive and hazardous waste is a highly efficient and cost-saving technology. The technology used for final treatment of soil-washing size fractionization operations is being demonstrated on simulated waste. Treated material (wasterock) is used to stabilize and isolate retired underground waste disposal structures or is used to construct landfills or equivalent surface or subsurface structures. Prototype equipment is under development as well as undergoing standardized testing protocols to prequalify treated waste materials. Polymer and hydraulic cement solidification agents are currently used for geotechnical demonstration activities.

Phillips, S.J.; Alexander, R.G.; England, J.L.; Kirdendall, J.R.; Raney, E.A.; Stewart, W.E. [Westinghouse Hanford Co., Richland, WA (United States); Dagan, E.B.; Holt, R.G. [Dept. of Energy, Richland, WA (United States). Richland Operations Office

1993-09-01T23:59:59.000Z

394

Waste Logic Decommissioning Waste Manager 2.0 Users Manual  

Science Conference Proceedings (OSTI)

The Decommissioning Waste Manager, part of EPRI's Waste Logic series of computer programs, analyzes decommissioning waste cost and volume reduction strategies with the intent of quantifying the existing waste management program for any given waste generator.

2001-10-29T23:59:59.000Z

395

Conservation laws for vacuum tetrad gravity  

E-Print Network (OSTI)

Ten conservation laws in useful polynomial form are derived from a Cartan form and Exterior Differential System (EDS) for the tetrad equations of vacuum relativity. The Noether construction of conservation laws for well posed EDS is introduced first, and an illustration given, deriving 15 conservation laws of the free field Maxwell Equations from symmetries of its EDS. The Maxwell EDS and tetrad gravity EDS have parallel structures, with their numbers of dependent variables, numbers of generating 2-forms and generating 3-forms, and Cartan character tables all in the ratio of 1 to 4. They have 10 corresponding symmetries with the same Lorentz algebra, and 10 corresponding conservation laws.

Frank B. Estabrook

2005-08-20T23:59:59.000Z

396

Laws and Regulations | Department of Energy  

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

Laws and Regulations Laws and Regulations Laws and Regulations Federal laws and regulations set multiple energy management requirements for Federal agencies spanning energy efficiency, renewable energy, water conservation, and alternative fuel use. This section outlines Federal energy management authorities through: Requirements by Subject Requirements by Regulation. The Federal Energy Management Program (FEMP) analyzes energy management authorities and develops rules and guidance to help Federal agencies comply with applicable requirements. Reporting requirements and Federal Government performance reports are also available through: Notices and Rules Facility Reporting Fleet Reporting. EISA 432 Compliance Tracking Track Federal agency progress toward Section 432 of the Energy Independence and Security Act (EISA) of 2007 using FEMP's EISA 432

397

Fisher info and thermodynamics' first law  

E-Print Network (OSTI)

1991); B. H. Lavenda, Thermodynamics of Extremes (Al- bion,Fisher information and thermodynamics’ 1st. law A. Plastinotransform (LT) of thermodynamics can be microscopically

Plastino, A; Plastino, A R; Soffer, Bernard H

2006-01-01T23:59:59.000Z

398

Solar Easements & Rights Laws | Department of Energy  

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

Policy Solar access provisions in the General Laws of Massachusetts allow for the creation of voluntary solar easements to protect solar exposure and authorizes zoning rules...

399

Solar Easements & Local Option Solar Rights Laws  

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

Utah's solar easement provisions are similar to easement provisions in many other states. Parties may voluntarily enter into written solar easement contracts that are enforceable by law. An...

400

Patent Harmonization: Creating Uniform Patent Laws  

Science Conference Proceedings (OSTI)

Patent Harmonization: Creating Uniform Patent Laws. David V. Radack. You may have seen or heard the phrase "patent harmonization" used when discussing ...

Note: This page contains sample records for the topic "activity waste law" 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.


401

US Retail Pricing Laws and Regulations 2009  

Science Conference Proceedings (OSTI)

... accessories, intended (1) for use in the diagnosis, cure, mitigation, treatment, or prevention ... c) Group 3: Frozen ... IDAHO No pricing laws or regulations ...

2011-03-21T23:59:59.000Z

402

Architects' perspectives on construction waste reduction by design  

SciTech Connect

The construction, demolition and excavation waste arising in England was estimated at 91 million tonnes in 2003. The current thinking on construction waste minimisation is heavily focussed on several issues relating to physical construction waste and recycling guides. Indeed, much had been published on ways to improve on-site waste management and recycling activities but very few attempts made to address the effect of design practices on waste generation. However, there is a consensus in the literature that the architect has a decisive role to play in helping to reduce waste by focussing on designing out waste. This paper examines previous studies on architects' approach towards construction waste minimisation; and by means of a postal questionnaire, investigates: the origins of waste; waste minimisation design practices in the UK; and responsibilities and barriers within the UK architectural profession. The findings reveal that waste management is not a priority in the design process. Additionally, the architects seemed to take the view that waste is mainly produced during site operations and rarely generated during the design stages; however, about one-third of construction waste could essentially arise from design decisions. Results also indicate that a number of constraints, namely: lack of interest from clients; attitudes towards waste minimisation; and training all act as disincentives to a proactive and sustainable implementation of waste reduction strategies during the design process.

Osmani, M. [Department of Civil and Building Engineering, Loughborough University, Loughborough, Leicestershire LE11 3TU (United Kingdom)], E-mail: M.Osmani@lboro.ac.uk; Glass, J.; Price, A.D.F. [Department of Civil and Building Engineering, Loughborough University, Loughborough, Leicestershire LE11 3TU (United Kingdom)

2008-07-01T23:59:59.000Z

403

Modulated power-law behaviour in Stirling's approximation  

E-Print Network (OSTI)

DEVELOPMENT OF THFEGENERAL ELECTRIC STIRLING ENGINE GAS HEAT PUMP R. C. Meier, Program Manager, Gas heating and cooling, particu- larly in northern climates. The use of waste heat from the Stirling engine, in conjunction with the inherent high engine efficiency, makes the Stirling/Rankine Heat Activated Heat Pump

Hatton, Les

404

Basis for a Waste Management Public Communication Policy: Actual Situation Analysis and Implementation of Corrective Actions  

SciTech Connect

Argentina will require new sites for the location of radioactive waste final disposal systems. It is currently mandatory to have social and political consensus to obtain the corresponding agreements. The experience obtained with the cancellation of the project ''Feasibility Study and Engineering Project--Repository for High Level Radioactive Waste'', reinforces even more the necessity to count with the acceptance of the public to carry out projects of this kind. The first phase of the former was developed in the 80's: geological, geophysical and hydrogeological studies were performed in a compact granitic rock located in Sierra del Medio, Chubut province. This project had to be called off in the early 90's due to strong social rejection. This decision was closely related to the poor attention given to social communication issues. The governmental decision-makers in charge underwent a lot of pressure from social groups claiming for the cancellation of the project due to the lack of information and the fear it triggered. Thus, the lesson learnt: ''social communication activities must be carefully undertaken in order to achieve the appropriate management of the radioactive waste produced in our country.'' The same as in other countries, the specific National Law demands the formulation of a Strategic Plan which will not only include the research into radioactive waste, but the design of a Social Communication Programme as well. The latter will be in charge of informing the population clearly and objectively about the latest scientific and technological advances in the issue. A tentative perception-attitude pattern of the Argentine society about the overall nuclear issue is outlined in this paper. It is meant to contribute to the understanding of the public's adverse reaction to this kind of project. A communication programme is also presented. Its objective is to install the waste management topic in the public's opinion with a positive real outlook.

Jolivet, L. A.; Maset, E. R.

2002-02-28T23:59:59.000Z

405

Corporate Board By-Laws  

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

May 2011 May 2011 By-Laws Office of Environmental Management Quality Assurance Corporate Board Article 1 Name The name shall be the Environmental Management (EM) Quality Assurance (QA) Corporate Board (hereafter referred to as the Board). Article 2 Mission The Board will serve a leadership role within EM for facilitating, championing, and overseeing the effectiveness of a consistent and graded approach to implementing the corporate QA program, policies and requirements, and disseminating lessons learned and best practices such that a consistent and effective approach to quality is obtained through independently managed federal and contractor QA Programs. The Board will serve as a consensus-building body to facilitate institutionalization of a streamlined and efficient QA

406

Disaster waste management: A review article  

SciTech Connect

Depending on their nature and severity, disasters can create large volumes of debris and waste. The waste can overwhelm existing solid waste management facilities and impact on other emergency response and recovery activities. If poorly managed, the waste can have significant environmental and public health impacts and can affect the overall recovery process. This paper presents a system overview of disaster waste management based on existing literature. The main literature available to date comprises disaster waste management plans or guidelines and isolated case studies. There is ample discussion on technical management options such as temporary storage sites, recycling, disposal, etc.; however, there is little or no guidance on how these various management options are selected post-disaster. The literature does not specifically address the impact or appropriateness of existing legislation, organisational structures and funding mechanisms on disaster waste management programmes, nor does it satisfactorily cover the social impact of disaster waste management programmes. It is envisaged that the discussion presented in this paper, and the literature gaps identified, will form a basis for future comprehensive and cohesive research on disaster waste management. In turn, research will lead to better preparedness and response to disaster waste management problems.

Brown, Charlotte, E-mail: charlotte.brown@pg.canterbury.ac.nz [University of Canterbury, Private Bag 4800, Christchurch 8140 (New Zealand); Milke, Mark, E-mail: mark.milke@canterbury.ac.nz [University of Canterbury, Private Bag 4800, Christchurch 8140 (New Zealand); Seville, Erica, E-mail: erica.seville@canterbury.ac.nz [University of Canterbury, Private Bag 4800, Christchurch 8140 (New Zealand)

2011-06-15T23:59:59.000Z

407

Waste management fiscal year 1998 progress report  

SciTech Connect

The Waste Management Program is pleased to issue the Fiscal Year 1998 Progress Report presenting program highlights and major accomplishments of the last year. This year-end update describes the current initiatives in waste management and the progress DOE has made toward their goals and objectives, including the results of the waste management annual performance commitments. One of the most important program efforts continues to be opening the Waste Isolation Pilot Plant (WIPP), located near Carlsbad, New Mexico, for the deep geologic disposal of transuranic waste. A major success was achieved this year by the West Valley Demonstration Project in New York, which in June completed the project`s production phase of high-level waste processing ahead of schedule and under budget. Another significant accomplishment this year was the award of two privatization contracts for major waste management operations, one at Oak ridge for transuranic waste treatment, and one at Hanford for the Tank Waste Remediation System privatization project. DOE is proud of the progress that has been made, and will continue to pursue program activities that allow it to safely and expeditiously dispose of radioactive and hazardous wastes across the complex, while reducing worker, public, and environmental risks.

1998-12-31T23:59:59.000Z