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


1

Transuranic Waste Tabletop  

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

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

2

Transuranic Waste Requirements  

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

The guide provides criteria for determining if a waste is to be managed in accordance with DOE M 435.1-1, Chapter III, Transuranic Waste Requirements.

1999-07-09T23:59:59.000Z

3

Transuranic Waste Transportation Working Group Agenda | Department...  

Office of Environmental Management (EM)

Transuranic Waste Transportation Working Group Agenda Transuranic Waste Transportation Working Group Agenda Transuranic Waste Transportation Working Group Agenda More Documents &...

4

Transuranic (TRU) Waste | Department of Energy  

Office of Environmental Management (EM)

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

5

A brief analysis and description of transuranic wastes in the Subsurface Disposal Area of the radioactive waste management complex at INEL  

SciTech Connect (OSTI)

This document presents a brief summary of the wastes and waste types disposed of in the transuranic contaminated portions of the Subsurface Disposal Area of the radioactive waste management complex at Idaho National Engineering Laboratory from 1954 through 1970. Wastes included in this summary are organics, inorganics, metals, radionuclides, and atypical wastes. In addition to summarizing amounts of wastes disposed and describing the wastes, the document also provides information on disposal pit and trench dimensions and contaminated soil volumes. The report also points out discrepancies that exist in available documentation regarding waste and soil volumes and make recommendations for future efforts at waste characterization. 19 refs., 3 figs., 17 tabs.

Arrenholz, D.A.; Knight, J.L.

1991-08-01T23:59:59.000Z

6

Transuranic Waste Tabletop | Department of Energy  

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

Transuranic Waste Tabletop Transuranic Waste Tabletop Transuranic Waste Tabletop OBJECTIVES Given a simulated radioactive materials transportation accident, applicable procedures, and map references, demonstrate through participatory discussion a working knowledge of the following emergency response and concept of operations elements: „ Concept of operations for the emergency response to a radioactive materials transportation accident, including the Unified Incident Command System utilized in the field. „ Initial and extended response of emergency personnel and the interface between these organizations and Federal and State Regulatory agencies (i.e., Environmental Protection Agency [EPA], Department of Transportation [DOT], and the appropriate State agency). „ Communications between the Incident Commander (IC) and the

7

Radioactive Waste Radioactive Waste  

E-Print Network [OSTI]

#12;Radioactive Waste at UF Bldg 831 392-8400 #12;Radioactive Waste · Program is designed to;Radioactive Waste · Program requires · Generator support · Proper segregation · Packaging · labeling #12;Radioactive Waste · What is radioactive waste? · Anything that · Contains · or is contaminated

Slatton, Clint

8

Voluntary Protection Program Onsite Review, Transuranic Waste...  

Energy Savers [EERE]

Transuranic Waste Processing Center - September 2012 Voluntary Protection Program Onsite Review, Transuranic Waste Processing Center - September 2012 September 2012 Evaluation to...

9

Contact-Handled and Remote-Handled Transuranic Waste Packaging  

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

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

2011-08-09T23:59:59.000Z

10

Transuranic radionuclides in the environment surrounding radioactive waste diposal sites, a bibliography  

SciTech Connect (OSTI)

The purpose of this project was to compile a bibliography of references containing environmental transuranic radionuclide data. Our intent was to identify those parameters affecting transuranic radionuclide transport that may be generic and those that may be dependent on chemical form and/or environmental conditions (i.e. site specific). An understanding of the unique characteristics and similarities between source terms and environmental conditions relative to transuranic radionuclide transport and cycling will provide the ability to assess and predict the long term impact on man and the environment. An additional goal of our literature review, was to extract the ranges of environmental transuranic radionuclide data from the identified references for inclusion in a data base. Related to source term, these ranges of data can be used to calculate the dose to man from the radionuclides, and to perform uncertainty analyses on these dose assessments. In an attempt to gather relevant information about the transuranic radionuclides in a variety of environments, we conducted an extensive literature search. In our literature search we identified over 5700 potential written sources of information for review. In addition, we have identified many references which were not found through the literature searches, but which were known to contain useful data. A total of approximately 2600 documents were determined to contain information which would be useful for an in depth study of radionuclides in different environments. The journal articles, books, reports and other documents were reviewed to obtain the source term of the radionuclides studied. Most references containing laboratory study data were not included in our databases. Although these may contain valuable data, we were trying to compile references with information on the behavior of the transuranics in the specific environment being studied.

Stoker, A.C.; Noshkin, V.E.; Wong, K.M.; Brunk, J.L.; Conrado, C.L.; Jones, H.E.; Kehl, S.; Stuart, M.L.; Wasley, L.M.; Bradsher, R.V. [and others

1994-08-01T23:59:59.000Z

11

Transuranic Waste Transportation Working Group Agenda  

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

States Energy Board States Energy Board Joint Meeting of the Radioactive Materials Transportation Committee and the Transuranic Waste Transportation Working Group The Hilton Knoxville Knoxville, Tennessee May 15, 2012 Tuesday, May 15, 2012 8:30 a.m. Breakfast 9:30 a.m. Welcome / Opening Remarks / Introductions - Christopher Wells, Southern States Energy Board - Sandra Threatt, Chair, SSEB Radioactive Materials Transportation Working Group - Elgan Usrey, Chair, SSEB Transuranic Waste Transportation Working Group 9:45 a.m. WIPP Transportation Program and National TRU Activities - Bill Mackie, Carlsbad Field Office 10:30 a.m. Break 10:45 a.m. Commercial Vehicle Safety Alliance Level VI Program Update - Larry Stern, Commercial Vehicle Safety Alliance

12

Radioactive Waste Management Manual  

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

This Manual further describes the requirements and establishes specific responsibilities for implementing DOE O 435.1, Radioactive Waste Management, for the management of DOE high-level waste, transuranic waste, low-level waste, and the radioactive component of mixed waste. Change 1 dated 6/19/01 removes the requirement that Headquarters is to be notified and the Office of Environment, Safety and Health consulted for exemptions for use of non-DOE treatment facilities. Certified 1-9-07.

1999-07-09T23:59:59.000Z

13

Transuranic waste: long-term planning  

SciTech Connect (OSTI)

Societal concerns for the safe handling and disposal of toxic waste are behind many of the regulations and the control measures in effect today. Transuranic waste, a specific category of toxic (radioactive) waste, serves as a good example of how regulations and controls impact changes in waste processing - and vice versa. As problems would arise with waste processing, changes would be instituted. These changes improved techniques for handling and disposal of transuranic waste, reduced the risk of breached containment, and were usually linked with regulatory changes. Today, however, we face a greater public awareness of and concern for toxic waste control; thus, we must anticipate potential problems and work on resolving them before they can become real problems. System safety analyses are valuable aids in long-term planning for operations involving transuranic as well as other toxic materials. Examples of specific system safety analytical methods demonstrate how problems can be anticipated and resolution initiated in a timely manner having minimal impacts upon allocation of resource and operational goals. 7 refs., 1 fig.

Young, K.C.

1985-07-01T23:59:59.000Z

14

Hanford site transuranic waste certification plan  

SciTech Connect (OSTI)

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

GREAGER, T.M.

1999-05-12T23:59:59.000Z

15

New facility boosts Lab's ability to ship transuranic waste  

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

Lab's ability to ship transuranic waste Lab's ability to ship transuranic waste New facility boosts Lab's ability to ship transuranic waste Construction has begun on a new facility that will help Los Alamos accelerate the shipment of transuranic waste stored in large boxes at Technical Area 54. February 9, 2012 Aerial view of Los Alamos National Laboratory Aerial view of Los Alamos National Laboratory. Contact Colleen Curran Communications Office (505) 664-0344 Email "375 Box Line" facility to allow workers to repackage radioactive items stored in large boxes LOS ALAMOS, New Mexico, February 9, 2012-Construction has begun on a new facility that will help Los Alamos National Laboratory accelerate the shipment of transuranic (TRU) waste stored in large boxes at Technical Area 54, Area G. The new "375 Box Line" facility will allow the Laboratory to repackage

16

Radioactive Waste Management Manual  

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

This Manual further describes the requirements and establishes specific responsibilities for implementing DOE O 435.1, Radioactive Waste Management, for the management of DOE high-level waste, transuranic waste, low-level waste, and the radioactive component of mixed waste. The purpose of the Manual is to catalog those procedural requirements and existing practices that ensure that all DOE elements and contractors continue to manage DOE's radioactive waste in a manner that is protective of worker and public health and safety, and the environment. Does not cancel other directives.

1999-07-09T23:59:59.000Z

17

Final Transuranic Waste Shipment Leaves Rocky Flats | Department of Energy  

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

Final Transuranic Waste Shipment Leaves Rocky Flats Final Transuranic Waste Shipment Leaves Rocky Flats Final Transuranic Waste Shipment Leaves Rocky Flats April 19, 2005 - 12:23pm Addthis Cleanup Ahead of Schedule, On Track to Save Taxpayers Billions GOLDEN, CO. - A major environmental victory was achieved at the Rocky Flats Site in Golden, Colo., today when the final remaining shipment of radioactive, transuranic (TRU) waste left the property on a truck bound for an underground waste repository in New Mexico. This major milestone is another step toward the final conversion of the site to a National Wildlife Refuge managed by the U.S. Fish and Wildlife Service. "This is great news for all of Colorado, and would not have been possible without hand-in-glove cooperation between the Department of Energy, the

18

Annual Transuranic Waste Inventory Report - 2013  

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

ANNUAL TRANSURANIC WASTE INVENTORY REPORT - 2013 (Data Cutoff Date 12312012) DOETRU-13-3425 Revision 1 February 2014 U.S. Department of Energy Carlsbad Field Office DOE...

19

Transuranic Waste Processing Center Contract Awarded to Wastren...  

Office of Environmental Management (EM)

Transuranic Waste Processing Center Contract Awarded to Wastren Advantage, Inc. Transuranic Waste Processing Center Contract Awarded to Wastren Advantage, Inc. October 22, 2009 -...

20

Independent Oversight Review, Oak Ridge Transuranic Waste Processing...  

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

Transuranic Waste Processing Center, September 2013 Independent Oversight Review, Oak Ridge Transuranic Waste Processing Center, September 2013 September 2013 Review of Management...

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


21

Waste Isolation Pilot Plant, National Transuranic Program Have...  

Office of Environmental Management (EM)

Waste Isolation Pilot Plant, National Transuranic Program Have Banner Year in 2013 Waste Isolation Pilot Plant, National Transuranic Program Have Banner Year in 2013 December 24,...

22

Radioactive Waste Management Manual  

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

This Manual further describes the requirements and establishes specific responsibilities for implementing DOE O 435.1, Radioactive Waste Management, for the management of DOE high-level waste, transuranic waste, low-level waste, and the radioactive component of mixed waste. Change 1 dated 6/19/01 removes the requirement that Headquarters is to be notified and the Office of Environment, Safety and Health consulted for exemptions for use of non-DOE treatment facilities. Certified 1-9-07. Admin Chg 2, dated 6-8-11, cancels DOE M 435.1-1 Chg 1.

1999-07-09T23:59:59.000Z

23

Remote-handled transuranic waste study  

SciTech Connect (OSTI)

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

NONE

1995-10-01T23:59:59.000Z

24

Application to ship nonmixed transuranic waste to the Nevada Test Site for interim storage. Waste Cerification Program  

SciTech Connect (OSTI)

This report documents various regulations on radioactive waste processing and discusses how the Waste Isolation Pilot Plant will comply with and meet these requirements. Specific procedures are discussed concerning transuranic, metal scrap, salt block, solid, and glove box wastes.

Not Available

1993-12-01T23:59:59.000Z

25

Hanford Site Transuranic (TRU) Waste Certification Plan  

SciTech Connect (OSTI)

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

GREAGER, T.M.

1999-09-09T23:59:59.000Z

26

Hanford Site Transuranic (TRU) Waste Certification Plan  

SciTech Connect (OSTI)

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

GREAGER, T.M.

1999-12-14T23:59:59.000Z

27

Transuranic Waste Characterization Quality Assurance Program Plan  

SciTech Connect (OSTI)

This quality assurance plan identifies the data necessary, and techniques designed to attain the required quality, to meet the specific data quality objectives associated with the DOE Waste Isolation Pilot Plant (WIPP). This report specifies sampling, waste testing, and analytical methods for transuranic wastes.

NONE

1995-04-30T23:59:59.000Z

28

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

SciTech Connect (OSTI)

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

GREAGER, T.M.

1999-09-09T23:59:59.000Z

29

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

SciTech Connect (OSTI)

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

GREAGER, T.M.

2000-12-06T23:59:59.000Z

30

DOE's Transuranic Waste Processing Center Surpasses 3 Million...  

Office of Environmental Management (EM)

DOE's Transuranic Waste Processing Center Surpasses 3 Million Safe Work Hours DOE's Transuranic Waste Processing Center Surpasses 3 Million Safe Work Hours August 1, 2011 - 12:00pm...

31

First Oak Ridge Remote-Handled Transuranic Waste Shipment Arrives...  

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

First Oak Ridge Remote-Handled Transuranic Waste Shipment Arrives Safely at WIPP First Oak Ridge Remote-Handled Transuranic Waste Shipment Arrives Safely at WIPP March 2, 2009 -...

32

Hanford site transuranic waste sampling plan  

SciTech Connect (OSTI)

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

GREAGER, T.M.

1999-05-13T23:59:59.000Z

33

Process to separate transuranic elements from nuclear waste  

DOE Patents [OSTI]

A process for removing transuranic elements from a waste chloride electrolytic salt containing transuranic elements in addition to rare earth and other fission product elements so the salt waste may be disposed of more easily and the valuable transuranic elements may be recovered for reuse. The salt is contacted with a cadmium-uranium alloy which selectively extracts the transuranic elements from the salt. The waste salt is generated during the reprocessing of nuclear fuel associated with the Integral Fast Reactor (IFR).

Johnson, Terry R. (Wheaton, IL); Ackerman, John P. (Downers Grove, IL); Tomczuk, Zygmunt (Orland Park, IL); Fischer, Donald F. (Glen Ellyn, IL)

1989-01-01T23:59:59.000Z

34

MANAGEMENT ALERT Remediation of Selected Transuranic Waste Drums...  

Office of Environmental Management (EM)

MANAGEMENT ALERT Remediation of Selected Transuranic Waste Drums at Los Alamos National Laboratory - Potential Impact on the Shutdown of the Department's Waste Isolation Plant DOE...

35

22 - Radioactive waste disposal  

Science Journals Connector (OSTI)

Publisher Summary This chapter discusses the disposal of radioactive wastes that arise from a great variety of sources, including the nuclear fuel cycle, beneficial uses of isotopes, and radiation by institutions. Spent fuel contains uranium, plutonium, and highly radioactive fission products. The spent fuel is accumulating, awaiting the development of a high-level waste repository. It is anticipated that a multi-barrier system involving packaging and geologic media will provide protection of the public over the centuries. The favored method of disposal is in a mined cavity deep underground. In some countries, reprocessing the fuel assemblies permits recycling of materials and disposal of smaller volumes of solidified waste. Transportation of wastes is done by casks and containers designed to withstand severe accidents. Low-level wastes come from research and medical procedures and from a variety of activation and fission sources at a reactor site. They generally can be given near-surface burial. Isotopes of special interest are cobalt-60 and cesium-137. Transuranic wastes are being disposed of in the Waste Isolation Pilot Plant. Decommissioning of reactors in the future will contribute a great deal of low-level radioactive waste.

Raymond L. Murray

2001-01-01T23:59:59.000Z

36

Transuranic contaminated waste form characterization and data base  

SciTech Connect (OSTI)

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

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

1980-07-01T23:59:59.000Z

37

Radiological, physical, and chemical characterization of transuranic wastes stored at the Idaho National Engineering Laboratory  

SciTech Connect (OSTI)

This document provides radiological, physical and chemical characterization data for transuranic radioactive wastes and transuranic radioactive and hazardous (i.e., mixed) wastes stored at the Idaho National Engineering Laboratory and considered for treatment under the Private Sector Participation Initiative Program (PSPI). Waste characterization data are provided in the form of INEL Waste Profile Sheets. These documents provide, for each content code, information on waste identification, waste description, waste storage configuration, physical/chemical waste composition, radionuclide and associated alpha activity waste characterization data, and hazardous constituents present in the waste. Information is provided for 139 waste streams which represent an estimated total volume of 39,380{sup 3} corresponding to a total mass of approximately 19,000,000 kg. In addition, considerable information concerning alpha, beta, gamma, and neutron source term data specific to Rocky Flats Plant generated waste forms stored at the INEL are provided to assist in facility design specification.

Apel, M.L.; Becker, G.K.; Ragan, Z.K.; Frasure, J.; Raivo, B.D.; Gale, L.G.; Pace, D.P.

1994-03-01T23:59:59.000Z

38

Los Alamos National Laboratory Accelerates Transuranic Waste Shipments:  

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

Los Alamos National Laboratory Accelerates Transuranic Waste Los Alamos National Laboratory Accelerates Transuranic Waste Shipments: Spurred by a major wildfire in 2011, Los Alamos National Laboratory's TRU Waste Program accelerates shipments of transuranic waste stored aboveground to the Waste Isolation Pilot Plan Los Alamos National Laboratory Accelerates Transuranic Waste Shipments: Spurred by a major wildfire in 2011, Los Alamos National Laboratory's TRU Waste Program accelerates shipments of transuranic waste stored aboveground to the Waste Isolation Pilot Plan July 2, 2012 - 12:00pm Addthis New Mexico Governor Susana Martinez greets Terry Aguilar, governor of San Ildefonso Pueblo, while Frank Marcinowski (lower right), EM deputy assistant secretary of waste management, and Dan Cox, LANL associate deputy director for environmental affairs, look on.

39

EM Makes Significant Progress on Dispositioning Transuranic Waste at Idaho  

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

EM Makes Significant Progress on Dispositioning Transuranic Waste EM Makes Significant Progress on Dispositioning Transuranic Waste at Idaho Site EM Makes Significant Progress on Dispositioning Transuranic Waste at Idaho Site December 24, 2013 - 12:00pm Addthis Workers treat sludge-bearing, transuranic waste from the Advanced Mixed Waste Treatment Project. Workers treat sludge-bearing, transuranic waste from the Advanced Mixed Waste Treatment Project. A tank at the Materials and Fuels Complex containing residual sodium is moved prior to waste treatment. A tank at the Materials and Fuels Complex containing residual sodium is moved prior to waste treatment. Distillation equipment is shown prior to transport to the Idaho site. Distillation equipment is shown prior to transport to the Idaho site. In these 2010 photographs, unexploded ordnance were collected and then detonated onsite at the Mass Detonation Area.

40

EM Makes Significant Progress on Dispositioning Transuranic Waste at Idaho  

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

EM Makes Significant Progress on Dispositioning Transuranic Waste EM Makes Significant Progress on Dispositioning Transuranic Waste at Idaho Site EM Makes Significant Progress on Dispositioning Transuranic Waste at Idaho Site December 24, 2013 - 12:00pm Addthis Workers treat sludge-bearing, transuranic waste from the Advanced Mixed Waste Treatment Project. Workers treat sludge-bearing, transuranic waste from the Advanced Mixed Waste Treatment Project. A tank at the Materials and Fuels Complex containing residual sodium is moved prior to waste treatment. A tank at the Materials and Fuels Complex containing residual sodium is moved prior to waste treatment. Distillation equipment is shown prior to transport to the Idaho site. Distillation equipment is shown prior to transport to the Idaho site. In these 2010 photographs, unexploded ordnance were collected and then detonated onsite at the Mass Detonation Area.

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


41

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

SciTech Connect (OSTI)

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

GREAGER, T.M.

1999-12-14T23:59:59.000Z

42

Transuranic Waste Processing Center Oak Ridge Site Specific...  

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

Transuranic Waste Processing Update Oak Ridge Site Specific Advisory Board May 14, 2014 Laura Wilkerson, Portfolio Federal Project Director Karen Deacon, Deputy Federal Project...

43

Independent Oversight Review, Oak Ridge Transuranic Waste Processing...  

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

Facility - December 2013 Independent Oversight Review, Oak Ridge Transuranic Waste Processing Facility - December 2013 December 2013 Review of the Fire Protection Program and Fire...

44

D11 WASTE DISPOSAL FACILITIES FOR TRANSURANIC WASTE  

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

10 CFR Ch. X (1-1-12 Edition) Pt. 1022 D11 WASTE DISPOSAL FACILITIES FOR TRANSURANIC WASTE Siting, construction or expansion, and op- eration of disposal facilities for transuranic (TRU) waste and TRU mixed waste (TRU waste also containing hazardous waste as designated in 40 CFR part 261). D12 INCINERATORS Siting, construction, and operation of in- cinerators, other than research and develop- ment incinerators or incinerators for non- hazardous solid waste (as designated in 40 CFR 261.4(b)). PART 1022-COMPLIANCE WITH FLOODPLAIN AND WETLAND EN- VIRONMENTAL REVIEW REQUIRE- MENTS Subpart A-General Sec. 1022.1 Background. 1022.2 Purpose and scope. 1022.3 Policy. 1022.4 Definitions. 1022.5 Applicability. 1022.6 Public inquiries. Subpart B-Procedures for Floodplain and

45

Process to separate transuranic elements from nuclear waste  

DOE Patents [OSTI]

A process is described for removing transuranic elements from a waste chloride electrolytic salt containing transuranic elements in addition to rare earth and other fission product elements so the salt waste may be disposed of more easily and the valuable transuranic elements may be recovered for reuse. The salt is contacted with a cadmium-uranium alloy which selectively extracts the transuranic elements from the salt. The waste salt is generated during the reprocessing of nuclear fuel associated with the Integral Fast Reactor (IFR). 2 figs.

Johnson, T.R.; Ackerman, J.P.; Tomczuk, Z.; Fischer, D.F.

1989-03-21T23:59:59.000Z

46

Process to separate transuranic elements from nuclear waste  

DOE Patents [OSTI]

A process for removing transuranic elements from a waste chloride electrolytic salt containing transuranic elements in addition to rare earth and other fission product elements so the salt waste may be disposed of more easily and the valuable transuranic elements may be recovered for reuse. The salt is contacted with a cadmium-uranium alloy which selectively extracts the transuranic elements from the salt. The waste salt is generated during the reprocessing of nuclear fuel associated with the Integral Fast Reactor (IFR). 2 figs.

Johnson, T.R.; Ackerman, J.P.; Tomczuk, Z.; Fischer, D.F.

1988-07-12T23:59:59.000Z

47

Repackaging Rocky Flats Legacy Transuranic Waste  

SciTech Connect (OSTI)

Repackaging legacy Transuranic (TRU), Transuranic Mixed (TRM), Low Level Waste (LLW), and Low Level Mixed (LLM) waste requires good characterization skills and the ability to adapt to less than ideal conditions. Repackaging legacy waste in a facility that is not undergoing Decontamination and Decommission (D and D) is optimum. However, repackaging any waste in a D and D facility, under cold and dark conditions, can be difficult. Cold and dark conditions are when the heating and air conditioning are no longer in service and the lighting consists of strands of lights hung throughout each of the rooms. Working under these conditions adds an additional level of stress and danger that must be addressed. The use of glovebags was very useful at Rocky Flats during the D and D of many buildings. Glovebags can be adapted for many different types of wastes and unusual conditions. Repackaging of legacy TRU waste, in a D and D facility, can be accomplished safely and cost effectively with the use of glovebags. In conclusion: the use of glovebags to repackage legacy TRU, TRM, LLW, or LLM waste was done safely and cost effectively at Rocky Flats. The cost of using glovebags was minimal. Glovebags are easily adaptable to whatever the waste configuration is. The use of glovebags, for repackaging of Legacy waste, allows D and D efforts to stay on schedule and on task. Without the use of glovebags, additional gloveboxes would have been required at Rocky Flats. Larger items, such as the HEPA filters, would have required the construction of a new large item repackaging glovebox. Repackaging in glovebags allows the freedom to either locate the glovebag by the waste or locate the glovebag in a place that least impacts D and D efforts. The use of glovebags allowed numerous configurations of waste to be repackaged without the use of gloveboxes. During the D and D of the Rocky Flats facility, which was in a cold and dark stage, D and D work was not impacted by the repackaging activity. Glovebags work well in facilities that are in the process of D and D or still in full operations because glovebags are very safe and cost effective.

McTaggart, Jerri Lynne [Los Alamos National Laboratory, 115 N. Main St., Carlsbad, New Mexico, 88220 (United States)

2008-01-15T23:59:59.000Z

48

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

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

Greater-than-Class C Low-Level Radioactive Waste (GTCC LLW) Greater-than-Class C Low-Level Radioactive Waste (GTCC LLW) A transuranic (TRU) waste shipment makes its way to the...

49

Idaho Workers Complete Last of Transuranic Waste Transfers Funded by  

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

Workers Complete Last of Transuranic Waste Transfers Funded Workers Complete Last of Transuranic Waste Transfers Funded by Recovery Act Idaho Workers Complete Last of Transuranic Waste Transfers Funded by Recovery Act American Recovery and Reinvestment Act workers successfully transferred 130 containers of remote-handled transuranic waste – each weighing up to 15 tons – to a facility for repackaging and shipment to a permanent disposal location. As part of a project funded by $90 million from the Recovery Act, the final shipment of the containers from the Materials and Fuels Complex recently arrived at the Idaho Nuclear Technology and Engineering Center (INTEC). Idaho Workers Complete Last of Transuranic Waste Transfers Funded by Recovery Act More Documents & Publications EIS-0203-SA-03: Supplement Analysis

50

Independent Oversight Review, Oak Ridge Transuranic Waste Processing  

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

Oak Ridge Transuranic Waste Oak Ridge Transuranic Waste Processing Center, September 2013 Independent Oversight Review, Oak Ridge Transuranic Waste Processing Center, September 2013 September 2013 Review of Management of Safety Systems at the Oak Ridge Transuranic Waste Processing Center and Associated Feedback and Improvement Processes. This report documents the results of an independent oversight review of the management of safety significant structures, systems, and components at the Oak Ridge Transuranic Waste Processing Center (TWPC). The review was performed April 2-5, April 15-19, and May 19-23, 2013, by the Department of Energy's (DOE) Office of Safety and Emergency Management Evaluations, which is within the DOE Office of Health, Safety and Security. The review was carried out within the broader context of an ongoing program of

51

Savannah River Site Achieves Transuranic Waste Disposition Goal in 2013 |  

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

Savannah River Site Achieves Transuranic Waste Disposition Goal in Savannah River Site Achieves Transuranic Waste Disposition Goal in 2013 Savannah River Site Achieves Transuranic Waste Disposition Goal in 2013 December 24, 2013 - 12:00pm Addthis Workers gather behind a “Safety and Security begins with Me” banner at the Savannah River Site. Workers gather behind a "Safety and Security begins with Me" banner at the Savannah River Site. Workers sort through transuranic waste at the Savannah River Site. Workers sort through transuranic waste at the Savannah River Site. SRR employees Glenn Kelly and Fred Merriweather pour the final amount of grout into Tank 6. SRR employees Glenn Kelly and Fred Merriweather pour the final amount of grout into Tank 6. Workers gather behind a "Safety and Security begins with Me" banner at the Savannah River Site.

52

Independent Oversight Review, Oak Ridge Transuranic Waste Processing  

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

Oak Ridge Transuranic Waste Oak Ridge Transuranic Waste Processing Facility - December 2013 Independent Oversight Review, Oak Ridge Transuranic Waste Processing Facility - December 2013 December 2013 Review of the Fire Protection Program and Fire Protection Systems at the Transuranic Waste Processing Center This report documents the results of an independent oversight review of the fire protection programs and systems at the Oak Ridge Transuranic Waste Processing Center. The review was performed during May 20-23, 2013, and July 15-19, 2013, by the U.S. Department of Energy's (DOE) Office of Safety and Emergency Management Evaluations, which is within the DOE Office of Health, Safety and Security. The review was one part of a targeted assessment of fire protection at nuclear facilities across the DOE complex.

53

Los Alamos National Laboratory Transuranic Waste Program Exceeds Planned  

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

Los Alamos National Laboratory Transuranic Waste Program Exceeds Los Alamos National Laboratory Transuranic Waste Program Exceeds Planned Shipping Goal Los Alamos National Laboratory Transuranic Waste Program Exceeds Planned Shipping Goal May 1, 2012 - 12:00pm Addthis LOS ALAMOS, N.M. - Los Alamos National Laboratory's (LANL) Transuranic (TRU) Waste Program is looking at another record-setting month for the amount of TRU waste leaving Material Disposal Area G, headed to the Waste Isolation Pilot Plant (WIPP) for permanent disposal. LANL exceeded its planned removal of TRU waste from Area G in April, shipping more than 91 cubic meters of waste to WIPP - more than the Lab has ever shipped there in a single month. The Lab is headed for an even more successful May, with 99 cubic meters shipped to WIPP as of May 22. "Our shipping performance reflects the acceleration that began last

54

Waste management facilities cost information for transuranic waste  

SciTech Connect (OSTI)

This report contains preconceptual designs and planning level life-cycle cost estimates for managing transuranic waste. The report`s information on treatment and storage modules can be integrated to develop total life-cycle costs for various waste management options. A procedure to guide the U.S. Department of Energy and its contractor personnel in the use of cost estimation data is also summarized in this report.

Shropshire, D.; Sherick, M.; Biagi, C.

1995-06-01T23:59:59.000Z

55

DOE Seeks Trucking Services for Transuranic Waste Shipments | Department of  

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

Trucking Services for Transuranic Waste Shipments Trucking Services for Transuranic Waste Shipments DOE Seeks Trucking Services for Transuranic Waste Shipments March 30, 2011 - 12:00pm Addthis Media Contact Bill Taylor 513-246-0539 william.taylor@emcbc.doe.gov Cincinnati -- The Department of Energy (DOE) today will issue a Request for Proposals for the continuation of carrier services to transport transuranic waste (TRU) between DOE sites and the Waste Isolation Pilot Plant (WIPP) site, near Carlsbad, New Mexico. The transportation of TRU waste is accomplished by contracted trucking carriers that ship the waste via public highways on custom designed trailers. The contract will be an Indefinite Delivery/ Indefinite Quantity (ID/IQ) contract using firm-fixed- price delivery task orders. The estimated contract cost is $80-$100 million over a five-year contract

56

Transuranic waste characterization sampling and analysis methods manual  

SciTech Connect (OSTI)

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

NONE

1995-05-01T23:59:59.000Z

57

Radioactive Waste Management  

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

To establish policies and guidelines by which the Department of Energy (DOE) manages tis radioactive waste, waste byproducts, and radioactively contaminated surplus facilities.

1984-02-06T23:59:59.000Z

58

Annual Transuranic Waste Inventory Report - 2013  

Office of Environmental Management (EM)

ANNUAL TRANSURANIC WASTE INVENTORY REPORT - 2013 (Data Cutoff Date 12/31/2012) DOE/TRU-13-3425 Revision 0 October 2013 U.S. Department of Energy Carlsbad Field Office DOE/TRU-13-3425 Page 1 of 392 This document has been submitted as required to: U.S. Department of Energy Office of Scientific and Technical Information PO Box 62 Oak Ridge, TN 37831 Phone: (865) 576-8401 Additional information about this document may be obtained by calling 1-800-336-9477. Unlimited, publicly available full-text scientific and technical reports produced since 1991 are available online at Information Bridge (www.osti.gov/bridge). U.S. Department of Energy and its contractors may obtain full-text reports produced prior to 1991 in paper form, for a processing fee, from:

59

Chapter 22 - Radioactive Waste Disposal  

Science Journals Connector (OSTI)

Publisher Summary This chapter discusses safe disposal of radioactive waste in order to provide safety to workers and the public. Radioactive wastes arise from a great variety of sources, including the nuclear fuel cycle, and from beneficial uses of isotopes and radiation by institutions. Spent fuel contains uranium, plutonium, and highly radioactive fission products. In the United States spent fuel is accumulating, awaiting the development of a high-level waste repository. A multi-barrier system involving packaging and geological media will provide protection of the public over the centuries the waste must be isolated. The favored method of disposal is in a mined cavity deep underground. In other countries, reprocessing the fuel assemblies permits recycling of materials and disposal of smaller volumes of solidified waste. Transportation of wastes is by casks and containers designed to withstand severe accidents. Low-level wastes (LLWs) come from research and medical procedures and from a variety of activation and fission sources at a reactor site. They generally can be given near-surface burial. Isotopes of special interest are cobalt-60 and cesium-137. Transuranic wastes are being disposed of in the Waste Isolation Pilot Plant. Establishment of regional disposal sites by interstate compacts has generally been unsuccessful in the United States. Decontamination of defense sites will be long and costly. Decommissioning of reactors in the future will contribute a great deal of low-level radioactive waste.

Raymond L. Murray

2009-01-01T23:59:59.000Z

60

Radioactive Waste Management (Minnesota)  

Broader source: Energy.gov [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...

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


61

Oak Ridge National Laboratory Transuranic Waste Certification Program  

SciTech Connect (OSTI)

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

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

1988-08-01T23:59:59.000Z

62

An assessment of the flammability and explosion potential of transuranic waste  

SciTech Connect (OSTI)

The explosion potential of transuranic (TRU) waste, destined for the Waste Isolation Pilot (WIPP), was recently examined in EEG-45. That investigation focused on the volatile organic compounds (VOCs) in the waste, particularly acetone, and concluded that an explosion due to the VOCs was unlikely. Recent evidence raises serious concerns about drums containing mixed radioactive hazardous waste bound for the WIPP. Static electricity generated by the plastic bags represents a potential ignition source for other fuels, such as methane gas or hydrogen gas, during transportation and during the test phase. The potential danger of explosion due to hydrogen gas or methane gas generation has not yet been resolved. This report investigates that potential hazard and examines documented ignitions, fires, explosions and incidents of overpressurization of containers at generating and storage sites planning to send transuranic waste to the WIPP for disposal. 68 refs., 6 figs.

Silva, M.

1991-06-01T23:59:59.000Z

63

Transuranic waste form characterization and data base. Executive summary  

SciTech Connect (OSTI)

The Transuranic Waste Form Characterization and Data Base (Volume 1) provides a wide range of information from which a comprehensive data base can be established and from which standards and criteria can be developed for the present NRC waste management program. Supplementary information on each of the areas discussed in Volume 1 is presented in Appendices A through K (Volumes 2 and 3). The structure of the study (Volume 1) is outlined and appendices of Volumes 2 and 3 correlate with each main section of the report. The Executive Summary reviews the sources, quantities, characteristics and treatment of transuranic wastes in the United States. Due to the variety of potential treatment processes for transuranic wastes, the end products for long-term storage may have corresponding variations in quantities and characteristics.

Not Available

1980-09-30T23:59:59.000Z

64

Keeping Track of the National Transuranic Program Complex Defense Transuranic Waste  

SciTech Connect (OSTI)

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

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

2007-07-01T23:59:59.000Z

65

Waste Isolation Pilot Plant Transuranic Waste Baseline inventory report. Volume 1. Revision 1  

SciTech Connect (OSTI)

This document provides baseline inventories of transuranic wastes for the WIPP facility. Information on waste forms, forecasting of future inventories, and waste stream originators is also provided. A diskette is provided which contains the inventory database.

NONE

1995-02-01T23:59:59.000Z

66

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

SciTech Connect (OSTI)

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

Anastas, G.; Channell, J. K.

2002-02-26T23:59:59.000Z

67

EA-1146: Radioactive Waste Storage at Rocky Flats Environmental Technology  

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

46: Radioactive Waste Storage at Rocky Flats Environmental 46: Radioactive Waste Storage at Rocky Flats Environmental Technology Site, Golden, Colorado EA-1146: Radioactive Waste Storage at Rocky Flats Environmental Technology Site, Golden, Colorado SUMMARY This EA evaluates the environmental impacts of the proposal to convert buildings at the U.S. Department of Energy Rocky Flats Environmental Technology Site from their former uses to interim waste storage facilities in order to increase storage capacity for low-level waste, low-level mixed waste, transuranic waste, and transuranic mixed waste. PUBLIC COMMENT OPPORTUNITIES None available at this time. DOCUMENTS AVAILABLE FOR DOWNLOAD April 9, 1996 EA-1146: Finding of No Significant Impact Radioactive Waste Storage at Rocky Flats Environmental Technology Site, Golden, Colorado

68

Savannah River Site Achieves Transuranic Waste Disposition Goal...  

Office of Environmental Management (EM)

liquid waste contractor, Savannah River Remediation (SRR): Closed two more underground tanks containing radioactive waste, helping reduce a significant environmental risk to South...

69

Radioactive Waste: 1. Radioactive waste from your lab is  

E-Print Network [OSTI]

Radioactive Waste: 1. Radioactive waste from your lab is collected by the RSO. 2. Dry radioactive waste must be segregated by isotope. 3. Liquid radioactive waste must be separated by isotope. 4. Liquid frequently and change them if contaminated. 5. Use radioactive waste container to collect the waste. 6. Check

Jia, Songtao

70

Independent Oversight Review, Oak Ridge Transuranic Waste Processing Center, September 2013  

Broader source: Energy.gov [DOE]

Review of Management of Safety Systems at the Oak Ridge Transuranic Waste Processing Center and Associated Feedback and Improvement Processes

71

Low-level and transuranic waste transportation, disposal, and facility decommissioning cost sensitivity analysis  

SciTech Connect (OSTI)

The Systems Design Study (SDS) identified technologies available for the remediation of low-level and transuranic waste stored at the Radioactive Waste Management Complex`s Subsurface Disposal Area at the Idaho National Engineering Laboratory. The SDS study intentionally omitted the costs of transportation and disposal of the processed waste and the cost of decommissioning the processing facility. This report provides a follow-on analysis of the SDS to explore the basis for life-cycle cost segments of transportation, disposal, and facility decommissioning; to determine the sensitivity of the cost segments; and to quantify the life-cycle costs of the 10 ex situ concepts of the Systems Design Study.

Schlueter, R. [Bechtel National, Inc., San Francisco, CA (United States); Schafer, J.J. [EG and G Idaho, Inc., Idaho Falls, ID (United States)

1992-05-01T23:59:59.000Z

72

Low-level and transuranic waste transportation, disposal, and facility decommissioning cost sensitivity analysis  

SciTech Connect (OSTI)

The Systems Design Study (SDS) identified technologies available for the remediation of low-level and transuranic waste stored at the Radioactive Waste Management Complex's Subsurface Disposal Area at the Idaho National Engineering Laboratory. The SDS study intentionally omitted the costs of transportation and disposal of the processed waste and the cost of decommissioning the processing facility. This report provides a follow-on analysis of the SDS to explore the basis for life-cycle cost segments of transportation, disposal, and facility decommissioning; to determine the sensitivity of the cost segments; and to quantify the life-cycle costs of the 10 ex situ concepts of the Systems Design Study.

Schlueter, R. (Bechtel National, Inc., San Francisco, CA (United States)); Schafer, J.J. (EG and G Idaho, Inc., Idaho Falls, ID (United States))

1992-05-01T23:59:59.000Z

73

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

SciTech Connect (OSTI)

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

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

1990-08-01T23:59:59.000Z

74

Waste Isolation Pilot Plant Transuranic Waste Baseline inventory report. Volume 2. Revision 1  

SciTech Connect (OSTI)

This document is the Baseline Inventory Report for the transuranic (alpha-bearing) wastes stored at the Waste Isolation Pilot Plant (WIPP) in New Mexico. Waste stream profiles including origin, applicable EPA codes, typical isotopic composition, typical waste densities, and typical rates of waste generation for each facility are presented for wastes stored at the WIPP.

NONE

1995-02-01T23:59:59.000Z

75

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

Energy Savers [EERE]

of waste type and determination of a final disposal path. Per DOE Order 435.1, Change 1, Radioactive Waste Management, and its associated guide, legacy waste at Los Alamos...

76

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

SciTech Connect (OSTI)

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

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

1996-03-01T23:59:59.000Z

77

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

SciTech Connect (OSTI)

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

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

2006-01-19T23:59:59.000Z

78

Leach tests of simulated low-level transuranic waste forms containing transuranic elements  

SciTech Connect (OSTI)

Simulations of waste forms that could be produced by slagging pyrolysis incineration of low-level transuranic (TRU) wastes stored at the Idaho National Engineering Laboratory (INEL) have been fabricated containing the transuranic isotopes /sup 237/Np, /sup 239/Pu, /sup 241/Am, and /sup 244/Cm at levels of approximately 1 ..mu..Ci/g of each. Leach tests were performed on frit; concrete monoliths made with frit and Portland cement; and vitrified monoliths of average INEL TRU waste, INEL soil, and simulated Rocky Flats plant sludge. Static leach tests were performed at 90, 70, 40, and 25/sup 0/C in deionized water for up to 364 days. Leachates were analyzed for the TRU elements by alpha spectrometry. From the leaching results the following generalizations can be made: (1) cemented frit and vitrified sludge waste forms produce leachates with the highest pHs (> 11) and have the lowest TRU leach rates, 10/sup -4/ g/m/sup 2/ d at 90/sup 0/C; (2) neptunium has a higher leach rate than the other three TRU elements by as much as two orders of magnitude for all waste forms tested except cemented frit; and (3) only the vitrified soil samples display a marked temperature dependence for leach rates of all four TRU elements.

Welch, J.M.; Sill, C.W.; Flinn, J.E.

1983-01-01T23:59:59.000Z

79

Leach tests of simulated low-level transuranic waste forms containing transuranic elements  

SciTech Connect (OSTI)

Simulations of waste forms that might be produced by slagging pyrolysis incineration of low-level transuranic (TRU) wastes stored at the Idaho National Engineering Laboratory (INEL) have been fabricated containing the transuranic isotopes /sup 237/Np, /sup 239/Pu, /sup 241/Am, /sup 244/Cm at levels of approximately 1 ..mu..Ci per gram of each. Leach tests were performed using frit and vitrified monolithic specimens of average INEL TRU waste, portland cement monoliths made with frit as aggregate, and vitrified monoliths of INEL soil and simulated Rocky Flats sludge. Static leach tests were performed at 90, 70, 40, and 25/sup 0/C in deionized water for up to 364 days. Leachates were analyzed for the TRU elements by alpha spectrometry. The following generalizations can be made: (1) Cemented frit and vitrified sludge waste forms produce leachates with the highest pHs (>11) and have the lowest TRU leach rates, 10/sup -4/ g/m/sup 2/.d at 90/sup 0/C. (2) Neptunium has a higher leach rate than the other three TRU elements by as much as two orders of magnitude for all waste forms tested except cemented frit. (3) Only the vitrified soil samples display a marked temperature dependence for leach rates of all four TRU elements.

Welch, J.M.; Sill, C.W.; Flinn, J.E.

1982-01-01T23:59:59.000Z

80

Certification document for newly generated contact-handled transuranic waste  

SciTech Connect (OSTI)

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

Box, W.D.; Setaro, J.

1984-01-01T23:59:59.000Z

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


81

Long-range master plan for defense transuranic waste management  

SciTech Connect (OSTI)

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

Not Available

1988-12-01T23:59:59.000Z

82

Annual Transuranic Waste Inventory Report - 2013  

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

of TRU waste streams. Five waste streams have been moved from Potential to WIPP-bound status to be in alignment with the CBFO screening memorandum (Patterson 2010) provided in...

83

Transuranic (TRU) Waste Processing Center- Overview  

Broader source: Energy.gov [DOE]

DOE established the TRU Waste Processing Center (TWPC) as a regional center for the management, treatment, packaging and shipment of DOE TRU waste legacy inventory. TWPC is also responsible for managing and treating Low Level and Mixed Low Level Waste generated at ORNL. TWPC is operated by Wastren Advantage, Inc. (WAI) under contract to the DOE's Oak Ridge Office.

84

Retrieval Of Final Stored Radioactive Waste Resumes  

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

18, 2012 18, 2012 Media Contact: Danielle Miller, DOE-Idaho Operations, 208-526-5709, millerdc@id.doe.gov Rick Dale, Idaho Treatment Group, 208-557-6552, rick.dale@amwtp.inl.gov Retrieval Of Final Stored Radioactive Waste Resumes IDAHO FALLS, ID- Operations to retrieve the estimated 6,900 cubic meters of stored transuranic waste remaining at the Idaho site began this week at the U.S. Department of Energy�s Advanced Mixed Waste Treatment Project. Waste retrieval resumes at the Advanced Mixed Waste Treatment Project. The resumption of work comes after a nearly two-year stoppage of retrieval operations �A significant investment has been made in terms of time and dollars that will allow employees to safely retrieve the final radioactive waste that has been stored aboveground at the Idaho site for more than four

85

Radioactive waste disposal package  

DOE Patents [OSTI]

A radioactive waste disposal package comprising a canister for containing vitrified radioactive waste material and a sealed outer shell encapsulating the canister. A solid block of filler material is supported in said shell and convertible into a liquid state for flow into the space between the canister and outer shell and subsequently hardened to form a solid, impervious layer occupying such space.

Lampe, Robert F. (Bethel Park, PA)

1986-01-01T23:59:59.000Z

86

In situ vitrification: application analysis for stabilization of transuranic waste  

SciTech Connect (OSTI)

The in situ vitrification process builds upon the electric melter technology previously developed for high-level waste immobilization. In situ vitrification converts buried wastes and contaminated soil to an extremely durable glass and crystalline waste form by melting the materials, in place, using joule heating. Once the waste materials have been solidified, the high integrity waste form should not cause future ground subsidence. Environmental transport of the waste due to water or wind erosion, and plant or animal intrusion, is minimized. Environmental studies are currently being conducted to determine whether additional stabilization is required for certain in-ground transuranic waste sites. An applications analysis has been performed to identify several in situ vitrification process limitations which may exist at transuranic waste sites. Based on the process limit analysis, in situ vitrification is well suited for solidification of most in-ground transuranic wastes. The process is best suited for liquid disposal sites. A site-specific performance analysis, based on safety, health, environmental, and economic assessments, will be required to determine for which sites in situ vitrification is an acceptable disposal technique. Process economics of in situ vitrification compare favorably with other in-situ solidification processes and are an order of magnitude less than the costs for exhumation and disposal in a repository. Leachability of the vitrified product compares closely with that of Pyrex glass and is significantly better than granite, marble, or bottle glass. Total release to the environment from a vitrified waste site is estimated to be less than 10/sup -5/ parts per year. 32 figures, 30 tables.

Oma, K.H.; Farnsworth, R.K.; Rusin, J.M.

1982-09-01T23:59:59.000Z

87

Transuranic waste baseline inventory report. Revision No. 3  

SciTech Connect (OSTI)

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

NONE

1996-06-01T23:59:59.000Z

88

Waste Isolation Pilot Plant, National Transuranic Program Have Banner Year  

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

Plant, National Transuranic Program Have Plant, National Transuranic Program Have Banner Year in 2013 Waste Isolation Pilot Plant, National Transuranic Program Have Banner Year in 2013 December 24, 2013 - 12:00pm Addthis Since WIPP became operational in March 1999, it has surpassed receiving 11,000 shipments, which traveled over 14 million safe loaded miles over the nation’s highways through WIPP’s transportation program — equal to about 29 trips around the moon. WIPP has permanently disposed of more than 89,000 cubic meters of TRU waste — enough to fill more than 35 Olympic-size swimming pools. In 2013, WIPP is on course in support of the Los Alamos National Laboratory framework agreement with the State of New Mexico for complete removal of the above ground TRU waste stored at Area G by June 30, 2014. WIPP has cleaned 22 sites of legacy TRU waste.

89

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

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

5506-2007 5506-2007 April 2007 DOE STANDARD Preparation of Safety Basis Documents for Transuranic (TRU) Waste Facilities U.S. Department of Energy Washington, D.C. 20585 AREA-SAFT DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-STD-5506-2007 ii Available on the Department of Energy Technical Standards Program Web Site at Http://tis.eh.doe.gov/techstds/ DOE-STD-5506-2007 iii Foreword This Standard provides analytical assumptions and methods, as well as hazard controls to be used when developing Safety Basis (SB) documents for transuranic (TRU) waste facilities in the U.S. Department of Energy (DOE) Complex. It also provides supplemental technical

90

Transuranic waste characterization sampling and analysis methods manual. Revision 1  

SciTech Connect (OSTI)

This Methods Manual provides a unified source of information on the sampling and analytical techniques that enable Department of Energy (DOE) facilities to comply with the requirements established in the current revision of the Transuranic Waste Characterization Quality Assurance Program Plan (QAPP) for the Waste Isolation Pilot Plant (WIPP) Transuranic (TRU) Waste Characterization Program (the Program) and the WIPP Waste Analysis Plan. This Methods Manual includes all of the testing, sampling, and analytical methodologies accepted by DOE for use in implementing the Program requirements specified in the QAPP and the WIPP Waste Analysis Plan. The procedures in this Methods Manual are comprehensive and detailed and are designed to provide the necessary guidance for the preparation of site-specific procedures. With some analytical methods, such as Gas Chromatography/Mass Spectrometry, the Methods Manual procedures may be used directly. With other methods, such as nondestructive characterization, the Methods Manual provides guidance rather than a step-by-step procedure. Sites must meet all of the specified quality control requirements of the applicable procedure. Each DOE site must document the details of the procedures it will use and demonstrate the efficacy of such procedures to the Manager, National TRU Program Waste Characterization, during Waste Characterization and Certification audits.

Suermann, J.F.

1996-04-01T23:59:59.000Z

91

Identification of potential transuranic waste tanks at the Hanford Site  

SciTech Connect (OSTI)

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

Colburn, R.P.

1995-05-05T23:59:59.000Z

92

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

SciTech Connect (OSTI)

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

Not Available

1990-10-26T23:59:59.000Z

93

DESTRUCTION TECHNOLOGY DEMONSTRATION FOR ORGANICS IN TRANSURANIC WASTE  

SciTech Connect (OSTI)

General Atomics (GA) has recently completed a Phase I program for the development of a two-step alternative to incineration for the destruction of organics in transuranic wastes at the Savannah River Site. This process is known as thermal desorption-supercritical water oxidation, or TD-SCWO. The GA TD process uses heat to volatilize and transport organics from the waste material for subsequent treatment by SCWO. SCWO oxidizes organics in a steam medium at elevated temperatures and pressures in a manner that achieves excellent destruction efficiencies and compliance with all environmental requirements without the need for complex pollution-abatement equipment. This application of TD-SCWO is focused on a full-scale batch process for 55-gallon drums of mixed transuranic waste at the Savannah River Site. The Phase I reduced-scale test results show that the process operates as intended on surrogate waste matrices chosen to be representative of Savannah River Site transuranic mixed wastes. It provides a high degree of hydrogen removal and full containment of the radionuclide surrogate, with minimal requirements for pre-treatment and post-treatment. Other test objectives were to verify that the process produces no dioxins or furans, and meets all applicable regulatory criteria for retention of toxic metals, particulate, and criteria pollutants, while meeting WIPP/WAC and TRUPACT-II requirements. Thermal desorption of surrogate SRS mixed wastes at 500 psi and 1000 F met all tested requirements for WIPP/WAC and TRUPACT-II. SCWO of the desorbed surrogate organic materials at 500 psi and 1500 F also appears to meet all requirements for a nonincineration alternative, although >99.99% DRE for chlorinated solvents has not yet been demonstrated.

Mike Spritzer

2003-02-01T23:59:59.000Z

94

Transuranic (TRU) Waste Phase I Retrieval Plan  

SciTech Connect (OSTI)

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

MCDONALD, K.M.

2000-09-28T23:59:59.000Z

95

Transuranic (TRU) Waste Phase I Retrieval Plan  

SciTech Connect (OSTI)

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

MCDONALD, K.M.

1999-08-27T23:59:59.000Z

96

Idaho Workers Complete Last of Transuranic Waste Transfers Funded by Recovery Act  

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

August 29, 2011 August 29, 2011 IDAHO FALLS, Idaho - American Recovery and Reinvestment Act workers successfully transferred 130 containers of remote-handled transuranic waste - each weighing up to 15 tons - to a facility for repackaging and shipment to a permanent disposal location. As part of a project funded by $90 million from the Recovery Act, the final shipment of the containers from the Materials and Fuels Com- plex recently arrived at the Idaho Nuclear Technology and Engineering Center (INTEC). Each of the containers moved to INTEC is shielded and specially designed and fabricated for highly radioactive waste. Once at INTEC, the containers are cut open, emptied, and repackaged. After the waste is removed and put in casks, it is shipped to the Waste Isolation Pilot

97

Voluntary Protection Program Onsite Review, Transuranic Waste Processing Center- September 2012  

Broader source: Energy.gov [DOE]

Evaluation to determine whether Transuranic Waste Processing Center is continuing to perform at a level deserving DOE-VPP Star recognition.

98

Savannah River Site 2012 Outlook: Transuranic Waste Program Set to Safely  

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

Site 2012 Outlook: Transuranic Waste Program Set to Site 2012 Outlook: Transuranic Waste Program Set to Safely Reach Milestone Savannah River Site 2012 Outlook: Transuranic Waste Program Set to Safely Reach Milestone January 1, 2012 - 12:00pm Addthis By May, Savannah River Nuclear Solutions expects to be shipping transuranic waste to the Waste Isolation Pilot Plant almost continuously, using six TRUPACT-III shipping containers like the one shown here. By May, Savannah River Nuclear Solutions expects to be shipping transuranic waste to the Waste Isolation Pilot Plant almost continuously, using six TRUPACT-III shipping containers like the one shown here. Workers relocate a pipe overpack container used to transport small amounts of excess plutonium oxide destined for long-term storage at the Waste Isolation Pilot Plant in Carlsbad, New Mexico.

99

Safer Transportation and Disposal of Remote Handled Transuranic Waste - 12033  

SciTech Connect (OSTI)

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

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

2012-07-01T23:59:59.000Z

100

Hanford Surpasses Transuranic Waste Milestone: 1,000 Cubic Meters Shipped  

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

Surpasses Transuranic Waste Milestone: 1,000 Cubic Meters Surpasses Transuranic Waste Milestone: 1,000 Cubic Meters Shipped Four Months Ahead of Schedule Hanford Surpasses Transuranic Waste Milestone: 1,000 Cubic Meters Shipped Four Months Ahead of Schedule June 2, 2011 - 12:00pm Addthis Media Contact Cameron Hardy, DOE (509) 376-5365 Cameron.Hardy@rl.doe.gov RICHLAND, WASH. - The U.S. Department of Energy (DOE) at Hanford surpassed a Tri-Party Agreement Milestone by four months in shipping 1,000 cubic meters of transuranic waste off the Hanford Site in route to the Waste Isolation Pilot Plant (WIPP) in New Mexico before September 30, 2011. The milestone for shipping waste was met in May 2011. Since the shipments began in 2000, 620 shipments have left the Hanford Site, a total of 4,137 cubic meters of transuranic waste. Milestones for

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


101

Hanford Surpasses Transuranic Waste Milestone: 1,000 Cubic Meters Shipped  

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

Surpasses Transuranic Waste Milestone: 1,000 Cubic Meters Surpasses Transuranic Waste Milestone: 1,000 Cubic Meters Shipped Four Months Ahead of Schedule Hanford Surpasses Transuranic Waste Milestone: 1,000 Cubic Meters Shipped Four Months Ahead of Schedule June 2, 2011 - 12:00pm Addthis Media Contact Cameron Hardy, DOE (509) 376-5365 Cameron.Hardy@rl.doe.gov RICHLAND, WASH. - The U.S. Department of Energy (DOE) at Hanford surpassed a Tri-Party Agreement Milestone by four months in shipping 1,000 cubic meters of transuranic waste off the Hanford Site in route to the Waste Isolation Pilot Plant (WIPP) in New Mexico before September 30, 2011. The milestone for shipping waste was met in May 2011. Since the shipments began in 2000, 620 shipments have left the Hanford Site, a total of 4,137 cubic meters of transuranic waste. Milestones for

102

Radioactive waste storage issues  

SciTech Connect (OSTI)

In the United States we generate greater than 500 million tons of toxic waste per year which pose a threat to human health and the environment. Some of the most toxic of these wastes are those that are radioactively contaminated. This thesis explores the need for permanent disposal facilities to isolate radioactive waste materials that are being stored temporarily, and therefore potentially unsafely, at generating facilities. Because of current controversies involving the interstate transfer of toxic waste, more states are restricting the flow of wastes into - their borders with the resultant outcome of requiring the management (storage and disposal) of wastes generated solely within a state`s boundary to remain there. The purpose of this project is to study nuclear waste storage issues and public perceptions of this important matter. Temporary storage at generating facilities is a cause for safety concerns and underscores, the need for the opening of permanent disposal sites. Political controversies and public concern are forcing states to look within their own borders to find solutions to this difficult problem. Permanent disposal or retrievable storage for radioactive waste may become a necessity in the near future in Colorado. Suitable areas that could support - a nuclear storage/disposal site need to be explored to make certain the health, safety and environment of our citizens now, and that of future generations, will be protected.

Kunz, D.E.

1994-08-15T23:59:59.000Z

103

Accelerating the disposition of transuranic waste from LANL - 9495  

SciTech Connect (OSTI)

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

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

2009-01-01T23:59:59.000Z

104

RECOVERY ACT LEADS TO CLEANUP OF TRANSURANIC WASTE SITES | Department of  

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

RECOVERY ACT LEADS TO CLEANUP OF TRANSURANIC WASTE SITES RECOVERY ACT LEADS TO CLEANUP OF TRANSURANIC WASTE SITES RECOVERY ACT LEADS TO CLEANUP OF TRANSURANIC WASTE SITES October 1, 2010 - 12:00pm Addthis RECOVERY ACT LEADS TO CLEANUP OF TRANSURANIC WASTE SITES Carlsbad, NM - The recent completion of transuranic (TRU) waste cleanup at Vallecitos Nuclear Center (VNC) and Lawrence Livermore National Laboratory (LLNL) Site 300 in California brings the total number of sites cleared of TRU waste to 17. "Recovery Act funding has made this possible," Carlsbad Field Office (CBFO) Recovery Act Federal Project Director Casey Gadbury said of the VNC and LLNL cleanups funded with about $1.6 million in Recovery Act funds. "The cleanup of these and other small-quantity sites has been and will be accelerated because of the available Recovery Act funds."

105

RECOVERY ACT LEADS TO CLEANUP OF TRANSURANIC WASTE SITES | Department of  

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

RECOVERY ACT LEADS TO CLEANUP OF TRANSURANIC WASTE SITES RECOVERY ACT LEADS TO CLEANUP OF TRANSURANIC WASTE SITES RECOVERY ACT LEADS TO CLEANUP OF TRANSURANIC WASTE SITES October 1, 2010 - 12:00pm Addthis RECOVERY ACT LEADS TO CLEANUP OF TRANSURANIC WASTE SITES Carlsbad, NM - The recent completion of transuranic (TRU) waste cleanup at Vallecitos Nuclear Center (VNC) and Lawrence Livermore National Laboratory (LLNL) Site 300 in California brings the total number of sites cleared of TRU waste to 17. "Recovery Act funding has made this possible," Carlsbad Field Office (CBFO) Recovery Act Federal Project Director Casey Gadbury said of the VNC and LLNL cleanups funded with about $1.6 million in Recovery Act funds. "The cleanup of these and other small-quantity sites has been and will be accelerated because of the available Recovery Act funds."

106

Example of a Risk-Based Disposal Approval: Solidification of Hanford Site Transuranic Waste  

SciTech Connect (OSTI)

The Hanford Site requested, and the U.S. Environmental Protection Agency (EPA) Region 10 approved, a Toxic Substances Control Act of 1976 (TSCA) risk-based disposal approval (RBDA) for solidifying approximately four cubic meters of waste from a specific area of one of the K East Basin: the North Loadout Pit (NLOP). The NLOP waste is a highly radioactive sludge that contained polychlorinated biphenyls (PCBs) regulated under TSCA. The prescribed disposal method for liquid PCB waste under TSCA regulations is either thermal treatment or decontamination. Due to the radioactive nature of the waste, however, neither thermal treatment nor decontamination was a viable option. As a result, the proposed treatment consisted of solidifying the material to comply with waste acceptance criteria at the Waste Isolation Pilot Plant (WIPP) in Carlsbad, New Mexico, or possibly the Environmental Restoration Disposal Facility at the Hanford Site, depending on the resulting transuranic (TRU) content of the stabilized waste. The RBDA evaluated environmental risks associated with potential airborne PCBs. In addition, the RBDA made use of waste management controls already in place at the treatment unit. The treatment unit, the T Plant Complex, is a Resource Conservation and Recovery Act of 1976 (RCRA)-permitted facility used for storing and treating radioactive waste. The EPA found that the proposed activities did not pose an unreasonable risk to human health or the environment. Treatment took place from October 26, 2005 to June 9, 2006, and 332 208-liter (55-gallon) containers of solidified waste were produced. All treated drums assayed to date are TRU and will be disposed at WIPP. (authors)

Barnes, B.M.; Hyatt, J.E.; Martin, P.W.; Prignano, A.L. [Fluor Hanford, Inc., Richland, WA (United States)

2008-07-01T23:59:59.000Z

107

Process Simulation as Applied to Transuranic Waste Management  

SciTech Connect (OSTI)

The National Transuranic Waste System Model (the Model) is a computer simulation designed to evaluate the preparation and flow of TRU waste from generator sites throughout the Department of Energy (the Department) complex to the Waste Isolation Pilot Plant (WIPP) facility for disposal. The Model uses process simulation software to predict waste outputs of waste management operations as a function of time over the life of the WIPP. Process simulation modeling is a tool used by many industries, both private and public, to evaluate complex systems. For example a manufacturing plant might use process simulation to determine the possible effects of increasing the rate of production: will there be adequate resources (labor pool, raw goods, transportation capability); can the new production rate be sustained for an indefinite period of time without adding additional infrastructure. Process simulation modeling is also used by various military branches to ensure adequate supplies are delivered in a timely manner. The Department currently uses this technique as the basis for its National TRU Waste Management Plan Rev. 1 (DOE, 1997).

Brown, M.; Downes, S.; Trone, J.

1999-01-01T23:59:59.000Z

108

DOE Selects Two Small Businesses to Truck Transuranic Waste to New Mexico  

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

Two Small Businesses to Truck Transuranic Waste to New Two Small Businesses to Truck Transuranic Waste to New Mexico Waste Isolation Pilot Plant DOE Selects Two Small Businesses to Truck Transuranic Waste to New Mexico Waste Isolation Pilot Plant January 9, 2012 - 12:00pm Addthis Media Contact Bill Taylor 803-952-8564 bill.taylor@srs.gov Cincinnati - The Department of Energy (DOE) today awarded two small-business contracts to CAST Specialty Transportation, Inc. and Visionary Solutions, LLC, to provide trucking services to transport transuranic (TRU) waste, from DOE and other defense-related TRU waste generator sites to the Waste Isolation Pilot Plant (WIPP) site, near Carlsbad, New Mexico. The contracts are firmfixed-price with cost-reimbursable expenses over five years. CAST Specialty Transportation, Inc. of Henderson, Colorado, will begin

109

DOE Announces Preference for Disposal of Hanford Transuranic Tank Waste at  

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

Announces Preference for Disposal of Hanford Transuranic Tank Announces Preference for Disposal of Hanford Transuranic Tank Waste at WIPP DOE Announces Preference for Disposal of Hanford Transuranic Tank Waste at WIPP March 6, 2013 - 12:00pm Addthis WASHINGTON, D.C. - Today the U.S. Department of Energy (DOE) announced its preferred alternative to retrieve, treat, package, characterize and certify certain Hanford tank waste for disposal at the Waste Isolation Pilot Plant (WIPP) in Carlsbad, New Mexico, if such waste is properly classified in the future as defense-related mixed transuranic tank waste (mixed TRU waste). This preferred alternative, which may cover up to approximately 3.1 million gallons of tank waste contained in up to 20 tanks, will provide DOE with an option to deal with recent information about possible tank leaks and to

110

Evaluation of a self-guided transport vehicle for remote transportation of transuranic and other hazardous waste  

SciTech Connect (OSTI)

Between 1952 and 1970, over two million cubic ft of transuranic mixed waste was buried in shallow pits and trenches in the Subsurface Disposal Area at the Idaho National Engineering Laboratory`s Radioactive Waste Management Complex. Commingled with this two million cubic ft of waste is up to 10 million cubic ft of fill soil. The pits and trenches were constructed similarly to municipal landfills with both stacked and random dump waste forms such as barrels and boxes. The main contaminants are micron-sized particles of plutonium and americium oxides, chlorides, and hydroxides. Retrieval, treatment, and disposal is one of the options being considered for the waste. This report describes the results of a field demonstration conducted to evaluate a technology for transporting exhumed transuranic wastes at the Idaho National Engineering and Environmental Laboratory (INEEL) and at other hazardous or radioactive waste sites through the U.S. Department of Energy complex. The full-scale demonstration, conducted at the INEEL Robotics Center in the summer of 1995, evaluated equipment performance and techniques for remote transport of exhumed buried waste. The technology consisted of a Self-Guided Transport Vehicle designed to remotely convey retrieved waste from the retrieval digface and transport it to a receiving/processing area with minimal human intervention. Data were gathered and analyzed to evaluate performance parameters such as precision and accuracy of navigation and transportation rates.

Rice, P.M.; Moody, S.J.; Peterson, R. [and others

1997-04-01T23:59:59.000Z

111

Radioactive Waste Management  

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

The objective of this Order is to ensure that all Department of Energy (DOE) radioactive waste is managed in a manner that is protective of worker and public health and safety and the environment. Cancels DOE O 5820.2A

1999-07-09T23:59:59.000Z

112

Radioactive waste material disposal  

DOE Patents [OSTI]

The invention is a process for direct conversion of solid radioactive waste, particularly spent nuclear fuel and its cladding, if any, into a solidified waste glass. A sacrificial metal oxide, dissolved in a glass bath, is used to oxidize elemental metal and any carbon values present in the waste as they are fed to the bath. Two different modes of operation are possible, depending on the sacrificial metal oxide employed. In the first mode, a regenerable sacrificial oxide, e.g., PbO, is employed, while the second mode features use of disposable oxides such as ferric oxide. 3 figs.

Forsberg, C.W.; Beahm, E.C.; Parker, G.W.

1995-10-24T23:59:59.000Z

113

Radioactive waste material disposal  

DOE Patents [OSTI]

The invention is a process for direct conversion of solid radioactive waste, particularly spent nuclear fuel and its cladding, if any, into a solidified waste glass. A sacrificial metal oxide, dissolved in a glass bath, is used to oxidize elemental metal and any carbon values present in the waste as they are fed to the bath. Two different modes of operation are possible, depending on the sacrificial metal oxide employed. In the first mode, a regenerable sacrificial oxide, e.g., PbO, is employed, while the second mode features use of disposable oxides such as ferric oxide.

Forsberg, Charles W. (155 Newport Dr., Oak Ridge, TN 37830); Beahm, Edward C. (106 Cooper Cir., Oak Ridge, TN 37830); Parker, George W. (321 Dominion Cir., Knoxville, TN 37922)

1995-01-01T23:59:59.000Z

114

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

SciTech Connect (OSTI)

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

NONE

1997-04-14T23:59:59.000Z

115

A new DOE standard for transuranic waste nuclear safety analysis  

SciTech Connect (OSTI)

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

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

2007-07-01T23:59:59.000Z

116

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

SciTech Connect (OSTI)

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

Not Available

1988-08-01T23:59:59.000Z

117

SUPPLEMENT ANALYSIS OF TRANSURANIC WASTE CHARACTERIZATION AND REPACKAGING A  

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

TRANSURANIC WASTE CHARACTERIZATION AND REPACKAGING A TRANSURANIC WASTE CHARACTERIZATION AND REPACKAGING A C T I V I T I E S AT THE IDAHO NATIONAL ENGINEERING LABORATORY I N SUPPORT OF THE WASTE ISOLATION PILOT PLANT TEST PROGRAM P r e p a r e d by U.S. D e p a r t m e n t o f E n e r g y O f f i c e o f E n v i r o n m e n t a l R e s t o r a t i o n a n d W a s t e Management M a r c h 1 9 9 1 FOREWORD T h i s supplement a n a l y s i s has been prepared t o d e s c r i b e new i n f o r m a t i o n r e l e v a n t t o waste r e t r i e v a l , handling, and c h a r a c t e r i z a t i o n a t t h e Idaho N a t i o n a l E n g i n e e r i n g L a b o r a t o r y (INEL) and t o e v a l u a t e t h e need f o r a d d i t i o n a l documentation t o s a t i s f y t h e N a t i o n a l Environmental Pol i c y A c t (NEPA) - - 4 0 Code o f Federal R e g u l a t i o n s (CFR) 1502.9--and S e c t i o n C, P a r t 2, o f t h e U.S. Department o f Energy (DOE) NEPA G u i d e l i n e s (52 Federal R e g i s t e r [FR] 47662, Dece~iiber 15, 1987).

118

Idaho National Engineering Laboratory code assessment of the Rocky Flats transuranic waste  

SciTech Connect (OSTI)

This report is an assessment of the content codes associated with transuranic waste shipped from the Rocky Flats Plant in Golden, Colorado, to INEL. The primary objective of this document is to characterize and describe the transuranic wastes shipped to INEL from Rocky Flats by item description code (IDC). This information will aid INEL in determining if the waste meets the waste acceptance criteria (WAC) of the Waste Isolation Pilot Plant (WIPP). The waste covered by this content code assessment was shipped from Rocky Flats between 1985 and 1989. These years coincide with the dates for information available in the Rocky Flats Solid Waste Information Management System (SWIMS). The majority of waste shipped during this time was certified to the existing WIPP WAC. This waste is referred to as precertified waste. Reassessment of these precertified waste containers is necessary because of changes in the WIPP WAC. To accomplish this assessment, the analytical and process knowledge available on the various IDCs used at Rocky Flats were evaluated. Rocky Flats sources for this information include employee interviews, SWIMS, Transuranic Waste Certification Program, Transuranic Waste Inspection Procedure, Backlog Waste Baseline Books, WIPP Experimental Waste Characterization Program (headspace analysis), and other related documents, procedures, and programs. Summaries are provided of: (a) certification information, (b) waste description, (c) generation source, (d) recovery method, (e) waste packaging and handling information, (f) container preparation information, (g) assay information, (h) inspection information, (i) analytical data, and (j) RCRA characterization.

NONE

1995-07-01T23:59:59.000Z

119

Spent fuel and radioactive waste inventories, projections, and characteristics  

SciTech Connect (OSTI)

Current inventories and characteristics of commercial spent fuels and both commercial and US Department of Energy (DOE) radioactive wastes were compiled through December 31, 1983, based on the most reliable information available from government sources and the open literature, technical reports, and direct contacts. Future waste and spent fuel to be generated over the next 37 years and characteristics of these materials are also presented, consistent with the latest DOE/Energy Information Administration (EIA) or projection of US commercial nuclear power growth and expected defense-related and private industrial and institutional activities. Materials considered, on a chapter-by-chapter basis, are: spent fuel, high-level waste, transuranic waste, low-level waste, commercial uranium mill tailings, airborne waste, remedial action waste, and decommissioning waste. For each category, current and projected inventories are given through the year 2020, and the radioactivity and thermal power are calculated, based on reported or calculated isotopic compositions. 48 figures, 107 tables.

Not Available

1984-09-01T23:59:59.000Z

120

The largest radioactive waste glassification  

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

largest radioactive waste glassification largest radioactive waste glassification plant in the nation, the Defense Waste Processing Facility (DWPF) converts the liquid nuclear waste currently stored at the Savannah River Site (SRS) into a solid glass form suitable for long-term storage and disposal. Scientists have long considered this glassification process, called "vitrification," as the preferred option for treating liquid nuclear waste. By immobilizing the radioactivity in glass, the DWPF reduces the risks associated with the continued storage of liquid nuclear waste at SRS and prepares the waste for final disposal in a federal repository. About 38 million gallons of liquid nuclear wastes are now stored in 49 underground carbon-steel tanks at SRS. This waste has about 300 million curies of radioactivity, of which the vast majority

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


121

A Close in Place Option for Buried Transuranic Waste at the Nevada...  

National Nuclear Security Administration (NNSA)

of Federal Regulations Part 191 Evaluation of Buried Transuranic Waste at the Nevada Test Site - 8210 G.J. Shott, V. Yucel, L. Desotell National Security Technologies, LLC P.O....

122

Apparatus and method for quantitative assay of generic transuranic wastes from nuclear reactors  

DOE Patents [OSTI]

A combination of passive and active neutron measurements which yields quantitative information about the isotopic composition of transuranic wastes from nuclear power or weapons material manufacture reactors is described. From the measurement of prompt and delayed neutron emission and the incidence of two coincidentally emitted neutrons from induced fission of fissile material in the sample, one can quantify /sup 233/U, /sup 235/U and /sup 239/Pu isotopes in waste samples. Passive coincidence counting, including neutron multiplicity measurement and determination of the overall passive neutron flux additionally enables the separate quantitative evaluation of spontaneous fission isotopes such as /sup 240/Pu, /sup 244/Cm and /sup 252/Cf, and the spontaneous alpha particle emitter /sup 241/Am. These seven isotopes are the most important constituents of wastes from nuclear power reactors and once the mass of each isotope present is determined by the apparatus and method of the instant invention, the overall alpha particle activity can be determined to better than 1 nCi/g from known radioactivity data. Therefore, in addition to the quantitative analysis of the waste sample useful for later reclamation purposes, the alpha particle activity can be determined to decide whether permanent low-level burial is appropriate for the waste sample.

Caldwell, J.T.; Kunz, W.E.; Atencio, J.D.

1982-03-31T23:59:59.000Z

123

RSSC RADIOACTIVE WASTE DISPOSAL 08/2011 7-1 RADIOACTIVE WASTE DISPOSAL  

E-Print Network [OSTI]

RSSC RADIOACTIVE WASTE DISPOSAL 08/2011 7-1 CHAPTER 7 RADIOACTIVE WASTE DISPOSAL PAGE I. Radioactive Waste Disposal ............................................................................................ 7-2 II. Radiation Control Technique #2 Instructions for Preparation of Radioactive Waste

Slatton, Clint

124

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

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

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

125

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

SciTech Connect (OSTI)

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

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

2006-01-18T23:59:59.000Z

126

Identifying Mixed Chemical and Radioactive Waste Mixed waste is: any waste material containing both radioactive materials  

E-Print Network [OSTI]

Identifying Mixed Chemical and Radioactive Waste Mixed waste is: any waste material containing both as noted on the list, you do not have a mixed waste and it may be managed as a normal radioactive waste radioactive waste after initially dating the container, the hold for decay time is extended, but you cannot

Straight, Aaron

127

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

SciTech Connect (OSTI)

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

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

2010-01-01T23:59:59.000Z

128

Bacteria eats radioactive waste  

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

Bacteria eats radioactive waste Bacteria eats radioactive waste Name: deenaharper Status: N/A Age: N/A Location: N/A Country: N/A Date: Around 1993 Question: In my studies, I have found that everything in this world is balanced. When something dies it is converted into life. Is there anything out there that could convert radioactive material into a harmless substance? Some sort of bacteria that consumes radiation? Replies: The reason why radiation is so harmful is that is produces free radicals in living tissue, that is, it de-stabilizes molecules by tearing off electrons due to intense energies. These free radicals start a chain reaction of destruction, de-stabilizing neighboring molecules. If this continues unchecked, cells die, genetic material are mutated, and tissue aging accelerates. It is somewhat like being burned. Fire oxidizes by a similar free radical reaction. (Hence the term "sun burn.") The natural defenses against free radical reactions in biological systems are antioxidants, which are enzymes, nutrients, and other chemicals, which quench free radical reactions. Without them, life would very quickly cease. To my knowledge, no microorganism has an antioxidant capacity great enough to withstand even minimal exposure to any type of radiation. Microorganisms are actually very susceptible to radiation, which is why heat and gamma irradiation are used to sterilize food, instruments, etc. However, you raise an interesting possibility in that perhaps one can be genetically engineered to have super- antioxidant capacity, but that may be beyond current technology. Plus, if any got loose, given the exponential rate of reproduction, they may become an uncontrollable health hazard, as it would be very difficult to destroy them!

129

Radioactive waste processing apparatus  

DOE Patents [OSTI]

Apparatus for use in processing radioactive waste materials for shipment and storage in solid form in a container is disclosed. The container includes a top, and an opening in the top which is smaller than the outer circumference of the container. The apparatus includes an enclosure into which the container is placed, solution feed apparatus for adding a solution containing radioactive waste materials into the container through the container opening, and at least one rotatable blade for blending the solution with a fixing agent such as cement or the like as the solution is added into the container. The blade is constructed so that it can pass through the opening in the top of the container. The rotational axis of the blade is displaced from the center of the blade so that after the blade passes through the opening, the blade and container can be adjusted so that one edge of the blade is adjacent the cylindrical wall of the container, to insure thorough mixing. When the blade is inside the container, a substantially sealed chamber is formed to contain vapors created by the chemical action of the waste solution and fixant, and vapors emanating through the opening in the container. The chamber may be formed by placing a removable extension over the top of the container. The extension communicates with the apparatus so that such vapors are contained within the container, extension and solution feed apparatus. A portion of the chamber includes coolant which condenses the vapors. The resulting condensate is returned to the container by the force of gravity.

Nelson, R.E.; Ziegler, A.A.; Serino, D.F.; Basnar, P.J.

1985-08-30T23:59:59.000Z

130

DOE Reaches Recovery Act Goal With Cleanup of All Legacy Transuranic Waste  

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

Reaches Recovery Act Goal With Cleanup of All Legacy Reaches Recovery Act Goal With Cleanup of All Legacy Transuranic Waste at Sandia National Laboratories DOE Reaches Recovery Act Goal With Cleanup of All Legacy Transuranic Waste at Sandia National Laboratories May 3, 2012 - 12:00pm Addthis Media Contact Deb Gill, U.S. DOE Carlsbad Field Office, (575) 234-7270 CARLSBAD, N.M., May 3, 2012 -The U.S. Department of Energy (DOE) completed cleanup of the Cold War legacy transuranic (TRU) waste at Sandia National Laboratories (Sandia) in Albuquerque, New Mexico when four shipments of remote-handled (RH) TRU waste from Sandia arrived at the Waste Isolation Pilot Plant (WIPP) near Carlsbad, N.M. for permanent disposal on May 2, 2012. The DOE Carlsbad Field Office (CBFO) reached one of its final milestones under the American Recovery and Reinvestment Act (ARRA) with the legacy TRU

131

A Title 40 Code of Federal Regulations Part 191 Evaluation of Buried Transuranic Waste at the Nevada Test Site  

SciTech Connect (OSTI)

In 1986, 21 m{sup 3} of transuranic (TRU) waste was inadvertently buried in a shallow land burial trench at the Area 5 Radioactive Waste Management Site on the Nevada Test Site (NTS). The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office is considered five options for management of the buried TRU waste. One option is to leave the waste in-place if the disposal can meet the requirements of Title 40 Code of Federal Regulations (CFR) Part 191, 'Environmental Radiation Protection Standard for Management and Disposal of Spent Nuclear Fuel, High-Level, and Transuranic Radioactive Wastes'. This paper describes analyses that assess the likelihood that TRU waste in shallow land burial can meet the 40 CFR 191 standards for a geologic repository. The simulated probability of the cumulative release exceeding 1 and 10 times the 40 CFR 191.13 containment requirements is estimated to be 0.009 and less than 0.0001, respectively. The cumulative release is most sensitive to the number of groundwater withdrawal wells drilled through the disposal trench. The mean total effective dose equivalent for a member of the public is estimated to reach a maximum of 0.014 milliSievert (mSv) at 10,000 years, or approximately 10 percent of the 0.15 mSv 40 CFR 191.15 individual protection requirement. The dose is predominantly from inhalation of short-lived Rn-222 progeny in air produced by low-level waste disposed in the same trench. The transuranic radionuclide released in greatest amounts, Pu-239, contributes only 0.4 percent of the dose. The member of public dose is most sensitive to the U-234 inventory and the radon emanation coefficient. Reasonable assurance of compliance with the Subpart C groundwater protection standard is provided by site characterization data and hydrologic processes modeling which support a conclusion of no groundwater pathway within 10,000 years. Limited quantities of transuranic waste in a shallow land burial trench at the NTS can meet the requirements of 40 CFR 191.

G. J. Shott, V. Yucel, L. Desotell

2008-04-01T23:59:59.000Z

132

Civilian Radioactive Waste Management System Requirements Document...  

Office of Environmental Management (EM)

Civilian Radioactive Waste Management System Requirements Document Civilian Radioactive Waste Management System Requirements Document This document specifies the top-level...

133

Radioactive Waste Management Complex Wide Review | Department...  

Office of Environmental Management (EM)

Radioactive Waste Management Complex Wide Review Radioactive Waste Management Complex Wide Review The main goal of this complex-wide review was to obtain feedback from DOE sites...

134

Measurement of radioactive contaminated wastes  

SciTech Connect (OSTI)

At Los Alamos, a comprehensive program is underway for the development of sensitive, practical, nondestructive assay techniques for the quantification of low-level transuranics in bulk solid wastes. The program encompasses a broad range of techniques, including sophisticated active and passive gamma-ray spectroscopy, passive neutron detection systems, pulsed portable neutron generator interrogation systems, and electron accelerator-based techniques. The techniques can be used with either low-level or high-level beta-gamma wastes in either low-density or high-density matrices. The techniques are quite sensitive (< 10 nCi/g detection) and, in many cases, isotopic specific. Waste packages range in size from small cardboard boxes to large metal or wooden crates. Considerable effort is being expended on waste matrix identification to improve assay accuracy.

Caldwell, J.T.; Close, D.A.; Crane, T.W.

1983-01-01T23:59:59.000Z

135

Radioactive waste material melter apparatus  

DOE Patents [OSTI]

An apparatus for preparing metallic radioactive waste material for storage is disclosed. The radioactive waste material is placed in a radiation shielded enclosure. The waste material is then melted with a plasma torch and cast into a plurality of successive horizontal layers in a mold to form a radioactive ingot in the shape of a spent nuclear fuel rod storage canister. The apparatus comprises a radiation shielded enclosure having an opening adapted for receiving a conventional transfer cask within which radioactive waste material is transferred to the apparatus. A plasma torch is mounted within the enclosure. A mold is also received within the enclosure for receiving the melted waste material and cooling it to form an ingot. The enclosure is preferably constructed in at least two parts to enable easy transport of the apparatus from one nuclear site to another.

Newman, Darrell F. (Richland, WA); Ross, Wayne A. (Richland, WA)

1990-01-01T23:59:59.000Z

136

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

SciTech Connect (OSTI)

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

DEROSA, D.C.

2000-01-13T23:59:59.000Z

137

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

SciTech Connect (OSTI)

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

Anastas, G.; Walker, B.A.

2003-02-24T23:59:59.000Z

138

Documentation of acceptable knowledge for LANL Plutonium Facility transuranic waste streams  

SciTech Connect (OSTI)

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

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

1998-07-01T23:59:59.000Z

139

Review of the WIPP draft application to show compliance with EPA transuranic waste disposal standards  

SciTech Connect (OSTI)

The purpose of the New Mexico Environmental Evaluation Group (EEG) is to conduct an independent technical evaluation of the Waste Isolation Pilot Plant (WIPP) Project to ensure the protection of the public health and safety and the environment. The WIPP Project, located in southeastern New Mexico, is being constructed as a repository for the disposal of transuranic (TRU) radioactive wastes generated by the national defense programs. The EEG was established in 1978 with funds provided by the U.S. Department of Energy (DOE) to the State of New Mexico. Public Law 100-456, the National Defense Authorization Act, Fiscal Year 1989, Section 1433, assigned EEG to the New Mexico Institute of Mining and Technology and continued the original contract DE-AC04-79AL10752 through DOE contract DE-AC04-89AL58309. The National Defense Authorization Act for Fiscal Year 1994, Public Law 103-160, continues the authorization. EEG performs independent technical analyses of the suitability of the proposed site; the design of the repository, its planned operation, and its long-term integrity; suitability and safety of the transportation systems; suitability of the Waste Acceptance Criteria and the generator sites` compliance with them; and related subjects. These analyses include assessments of reports issued by the DOE and its contractors, other federal agencies and organizations, as they relate to the potential health, safety and environmental impacts from WIPP. Another important function of EEG is the independent environmental monitoring of background radioactivity in air, water, and soil, both on-site and off-site.

Neill, R.H.; Chaturvedi, L.; Clemo, T.M. [and others

1996-03-01T23:59:59.000Z

140

DEPARTMENT OF ENERGY Disposal of Hanford Defense High-Level, Transuranic, and Tank Wastes, Hanford  

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

Disposal of Hanford Defense High-Level, Transuranic, and Tank Wastes, Hanford Disposal of Hanford Defense High-Level, Transuranic, and Tank Wastes, Hanford Site, Richland, Washington; Record of Decision (ROO). This Record of Decision has been prepared pursuant to the Council on Environme~tal Quality ~egulations for Implementing the Procedural Provisions of the National Environmental Pol icy Act (NEPAl (40 CFR Parts 1500-1508) and the Department of Energy NEPA Guidelines (52 FR 47662, December 15, 1987). It is based on DOE's "Environmental Impact Statement for the Oi sposal of Hanford Defense High-Level, Transuranic, and Tank Wastes'' (OOE/EIS-0113) and consideration of ~11 public and agency comments received on the Environmental Impact Statement (EIS). fJECISION The decision is to implement the ''Preferred Alternative'' as discussed in

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


141

Update on intrusive characterization of mixed contact-handled transuranic waste at Argonne-West  

SciTech Connect (OSTI)

Argonne National Laboratory and Lockheed Martin Idaho Technologies Company have jointly participated in the Department of Energy`s (DOE) Waste Isolation Pilot Plant (WIPP) Transuranic Waste Characterization Program since 1990. Intrusive examinations have been conducted in the Waste Characterization Area, located at Argonne-West in Idaho Falls, Idaho, on over 200 drums of mixed contact-handled transuranic waste. This is double the number of drums characterized since the last update at the 1995 Waste Management Conference. These examinations have provided waste characterization information that supports performance assessment of WIPP and that supports Lockheed`s compliance with the Resource Conservation and Recovery Act. Operating philosophies and corresponding regulatory permits have been broadened to provide greater flexibility and capability for waste characterization, such as the provision for minor treatments like absorption, neutralization, stabilization, and amalgamation. This paper provides an update on Argonne`s intrusive characterization permits, procedures, results, and lessons learned. Other DOE sites that must deal with mixed contact-handled transuranic waste have initiated detailed planning for characterization of their own waste. The information presented herein could aid these other storage and generator sites in further development of their characterization efforts.

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

1997-02-03T23:59:59.000Z

142

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

SciTech Connect (OSTI)

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

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

2003-02-27T23:59:59.000Z

143

Device Assembly Facility (DAF) Glovebox Radioactive Waste Characterization  

SciTech Connect (OSTI)

The Device Assembly Facility (DAF) at the Nevada Test Site (NTS) provides programmatic support to the Joint Actinide Shock Physics Experimental Research (JASPER) Facility in the form of target assembly. The target assembly activities are performed in a glovebox at DAF and include Special Nuclear Material (SNM). Currently, only activities with transuranic SNM are anticipated. Preliminary discussions with facility personnel indicate that primarily two distributions of SNM will be used: Weapons Grade Plutonium (WG-Pu), and Pu-238 enhanced WG-Pu. Nominal radionuclide distributions for the two material types are included in attachment 1. Wastes generated inside glove boxes is expected to be Transuranic (TRU) Waste which will eventually be disposed of at the Waste Isolation Pilot Plant (WIPP). Wastes generated in the Radioactive Material Area (RMA), outside of the glove box is presumed to be low level waste (LLW) which is destined for disposal at the NTS. The process knowledge quantification methods identified herein may be applied to waste generated anywhere within or around the DAF and possibly JASPER as long as the fundamental waste stream boundaries are adhered to as outlined below. The method is suitable for quantification of waste which can be directly surveyed with the Blue Alpha meter or swiped. An additional quantification methodology which requires the use of a high resolution gamma spectroscopy unit is also included and relies on the predetermined radionuclide distribution and utilizes scaling to measured nuclides for quantification.

Dominick, J L

2001-12-18T23:59:59.000Z

144

Microsoft Word - Los Alamos National Laboratory ships remote-handled transuranic waste to WIPP  

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

Los Alamos National Laboratory Ships Remote-Handled Los Alamos National Laboratory Ships Remote-Handled Transuranic Waste to WIPP CARLSBAD, N.M., June 3, 2009 - Cleanup of the nation's defense-related transuranic (TRU) waste has reached an important milestone. Today, the first shipment of remote-handled (RH) TRU waste from Los Alamos National Laboratory (LANL) in New Mexico arrived safely at the U.S. Department of Energy's (DOE) Waste Isolation Pilot Plant (WIPP) in the southeast corner of the state. "Shipping this waste to WIPP is important for our national cleanup mission, but this event is especially important for New Mexicans," said DOE Carlsbad Field Office Manager Dave Moody. "It's great to see progress being made right here in our own state." WIPP's mission includes the safe disposal of two types of defense-related

145

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

SciTech Connect (OSTI)

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

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

1993-01-01T23:59:59.000Z

146

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

SciTech Connect (OSTI)

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

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

1993-02-01T23:59:59.000Z

147

DOE Issues Final Request for Proposal for Oak Ridge Transuranic Waste Processing Center Services  

Broader source: Energy.gov [DOE]

Cincinnati -- The U.S. Department of Energy (DOE) today issued a Final Request for Proposal (RFP), for support services at the Oak Ridge Transuranic Waste Processing Center (TWPC) in Oak Ridge, Tennessee. The total estimated value of the contract is $100 Million - $300 Million.

148

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

SciTech Connect (OSTI)

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

Washington TRU Solutions LLC

2005-12-29T23:59:59.000Z

149

Building 251 Radioactive Waste Characterization by Process Knowledge  

SciTech Connect (OSTI)

Building 251 is the Lawrence Livermore National Laboratory Heavy Elements Facility. Operations that involved heavy elements with uncontained radioisotopes including transuranic elements took place inside of glove boxes and fume hoods. These operations included process and solution chemistry, dissolutions, titrations, centrifuging, etc., and isotope separation. Operations with radioactive material which presently take place outside of glove boxes include storage, assaying, packing and unpacking and inventory verification. Wastes generated inside glove boxes will generally be considered TRU or Greater Than Class C (GTCC). Wastes generated in the RMA, outside glove boxes, is presumed to be low level waste. This process knowledge quantification method may be applied to waste generated anywhere within or around B251. The method is suitable only for quantification of waste which measures below the MDA of the Blue Alpha meter (i.e. only material which measures as Non-Detect with the blue alpha is to be characterized by this method).

Dominick, J L

2002-05-29T23:59:59.000Z

150

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

SciTech Connect (OSTI)

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

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

1994-09-01T23:59:59.000Z

151

Radioactive Waste Incineration: Status Report  

SciTech Connect (OSTI)

Incineration is generally accepted as a method of reducing the volume of radioactive waste. In some cases, the resulting ash may have high concentrations of materials such as Plutonium or Uranium that are valuable materials for recycling. Incineration can also be effective in treating waste that contains hazardous chemicals as well as radioactive contamination. Despite these advantages, the number of operating incinerators currently in the US currently appears to be small and potentially declining. This paper describes technical, regulatory, economic and political factors that affect the selection of incineration as a preferred method of treating radioactive waste. The history of incinerator use at commercial and DOE facilities is summarized, along with the factors that have affected each of the sectors, thus leading to the current set of active incinerator facilities. In summary: Incineration has had a long history of use in radioactive waste processing due to their ability to reduce the volume of the waste while destroying hazardous chemicals and biological material. However, combinations of technical, regulatory, economic and political factors have constrained the overall use of incineration. In both the Government and Private sectors, the trend is to have a limited number of larger incineration facilities that treat wastes from a multiple sites. Each of these sector is now served by only one or two incinerators. Increased use of incineration is not likely unless there is a change in the factors involved, such as a significant increase in the cost of disposal. Medical wastes with low levels of radioactive contamination are being treated effectively at small, local incineration facilities. No trend is expected in this group. (authors)

Diederich, A.R.; Akins, M.J. [WorleyParsons, Reading, PA (United States)

2008-07-01T23:59:59.000Z

152

Remote-Handled Transuranic Waste Drum Venting - Operational Experience and Lessons Learned  

SciTech Connect (OSTI)

Remote-handled transuranic (RH TRU) waste drums must be vented to meet transportation and disposal requirement before shipment to the Waste Isolation Pilot Plant. The capability to perform remote venting of drums was developed and implemented at the Idaho National Laboratory. Over 490 drums containing RH TRU waste were successfully vented. Later efforts developed and implemented a long-stem filter to breach inner waste bags, which reduced layers of confinement and mitigated restrictive transportation wattage limits. This paper will provide insight to the technical specifications for the drum venting system, development, and testing activities, startup, operations, and lessons learned. (authors)

Clements, Th.L.Jr.; Bhatt, R.N.; Troescher, P.D. [CH2M-WG Idaho/Idaho National Laboratory, Idaho Falls, ID (United States); Wickland, T.J.; Anderson, L.; Wood, R. [Nuclear Filter Technology, Golden, CO (United States); Lattin, W.J. [Department of Energy-Idaho Operations Office, Idaho Falls, ID (United States)

2008-07-01T23:59:59.000Z

153

Shielded Payload Containers Will Enhance the Safety and Efficiency of the DOE's Remote Handled Transuranic Waste Disposal Operations  

SciTech Connect (OSTI)

The Waste Isolation Pilot Plant (WIPP) disposal operation currently employs two different disposal methods: one for Contact Handled (CH) waste and another for Remote Handled (RH) waste. CH waste is emplaced in a variety of payload container configurations on the floor of each disposal room. In contrast, RH waste is packaged into a single type of canister and emplaced in pre-drilled holes in the walls of disposal rooms. Emplacement of the RH waste in the walls must proceed in advance of CH waste emplacement. This poses a significant logistical constraint on waste handling operations by requiring significant coordination between waste characterization and preparations for shipping among the various generators. To improve operational efficiency, the Department of Energy (DOE) is proposing a new waste emplacement process for certain RH waste streams that can be safely managed in shielded containers. RH waste with relatively low gamma-emitting activity would be packaged in lead-lined containers, shipped to WIPP in existing certified transportation packages for CH waste, and emplaced in WIPP among the stacks of CH waste containers on the floor of a disposal room. RH waste with high gamma-emitting activity would continue to be emplaced in the boreholes along the walls. The new RH container appears essentially the same as a nominal 208-liter drum, but is built with about 2.5 cm of lead, sandwiched between thick steel sheet. The top and bottom are made of very thick plate steel, for strengthening the package to meet transportation requirements, and provide similar gamma attenuation. This robust configuration provides an overpack for waste that otherwise would be remotely handled. Up to a 3:1 reduction in number of shipments is projected if RH waste were transported in the proposed shielded containers. This paper describes the container design and testing, as well as the regulatory approach used to meet the requirements that apply to WIPP and its associated transportation system. This paper describes the RH transuranic waste inventory that may be candidates for packaging and emplacement in shielded containers. DOE does not propose to use shielded containers to increase the amount of RH waste allowed at WIPP. DOE's approach to gain approval for the transportation of shielded containers and to secure regulatory approval for use of shielded containers from WIPP regulators is discussed. Finally, the paper describes how DOE proposes to count the waste packaged into shielded containers against the RH waste inventory and how this will comply with the volume and radioactivity limitations imposed in the many and sometimes overlapping regulations that apply to WIPP. (authors)

Nelson, R.A. [U. S. Department of Energy, Carlsbad, New Mexico (United States); White, D.S. [Washington Group International, Carlsbad, New Mexico (United States)

2008-07-01T23:59:59.000Z

154

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

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

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

155

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

SciTech Connect (OSTI)

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

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

2010-02-01T23:59:59.000Z

156

Radioactive waste at Ward Valley  

Science Journals Connector (OSTI)

...Data Base for 1992: U.S. Spent Fuel and Radioactive Waste Inventories, Projections and Characteristics, publi. DOE/RW-0006, Rev. 8 (U.S. Department of Energy, Washington, DC, 1989), p. 113. 2. T. Taylor, quoted by S. Salesky...

Earl Budin

1995-09-22T23:59:59.000Z

157

Transuranic contaminated waste container characterization and data base. Revision I  

SciTech Connect (OSTI)

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

Kniazewycz, B.G.

1980-05-01T23:59:59.000Z

158

Characteristics of transuranic waste at Department of Energy sites  

SciTech Connect (OSTI)

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

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

1983-05-01T23:59:59.000Z

159

Gas generation results and venting study for transuranic waste drums  

SciTech Connect (OSTI)

Sixteen waste drums, containing six categories of plutonium-contaminated waste, were monitored for venting and gas generation for six months. The venting devices tested appeared adequate to relieve pressure and prevent hydrogen accumulation. Most of the gas generation, primarily H2 and CO2, was due to radiolytic decomposition of the hydrogenous wastes. Comparison of the gas yields with those obtained previously in laboratory tests showed very reasonable agreement with few exceptions.

Kazanjian, A.R.; Arnold, P.M.; Simmons, W.C.; D'Amico, E.L.

1985-09-23T23:59:59.000Z

160

Sorting and Characterizing Oversized Boxes of Transuranic Waste at the Nevada Test Site  

ScienceCinema (OSTI)

Characterization activities conducted inside the Visual Examination and Repackaging Building at the Area 5 Radioactive Waste Management Complex on the Nevada Test Site.

None

2014-10-28T23:59:59.000Z

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


161

Radioactive waste treatment technologies and environment  

SciTech Connect (OSTI)

The radioactive waste treatment and conditioning are the most important steps in radioactive waste management. At the Slovak Electric, plc, a range of technologies are used for the processing of radioactive waste into a form suitable for disposal in near surface repository. These technologies operated by JAVYS, PLc. Nuclear and Decommissioning Company, PLc. Jaslovske Bohunice are described. Main accent is given to the Bohunice Radwaste Treatment and Conditioning Centre, Bituminization plant, Vitrification plant, and Near surface repository of radioactive waste in Mochovce and their operation. Conclusions to safe and effective management of radioactive waste in the Slovak Republic are presented. (authors)

HORVATH, Jan; KRASNY, Dusan [JAVYS, PLc. - Nuclear and Decommisioning Company, PLc. (Slovakia)

2007-07-01T23:59:59.000Z

162

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

SciTech Connect (OSTI)

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

Not Available

1990-02-01T23:59:59.000Z

163

DOE Comments on Radioactive Waste | Department of Energy  

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

on Radioactive Waste DOE Comments on Radioactive Waste 1. Summary Comments on Draft Branch Technical Position on a Performance Assessment Methodology for Low-Level Radioactive...

164

Northeast High-Level Radioactive Waste Transportation Task Force...  

Office of Environmental Management (EM)

Northeast High-Level Radioactive Waste Transportation Task Force Agenda Northeast High-Level Radioactive Waste Transportation Task Force Agenda Northeast High-Level Radioactive...

165

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

SciTech Connect (OSTI)

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

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

2009-01-01T23:59:59.000Z

166

Transuranic (TRU) Waste Processing Center- Cask Processing Enclosure  

Broader source: Energy.gov [DOE]

Wastren Advantage, Inc., the DOE Prime contractor for the TRU Waste Processing Center (TWPC) conceived, designed, and constructed the new Cask Processing Enclosure (CPE) approach based on experience gained to date from Remote Handled (RH) waste processing. The CPE was designed August to October 2011, constructed from October 2011 to April 2012, and Start-up Readiness activities have just been completed. Initial radiological operations are targeted for July 19, 2012.

167

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

SciTech Connect (OSTI)

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

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

2002-02-26T23:59:59.000Z

168

Recommended strategy for the disposal of remote-handled transuranic waste  

SciTech Connect (OSTI)

The current baseline plan for RH TRU (remote-handled transuranic) waste disposal is to package the waste in special canisters for emplacement in the walls of the waste disposal rooms at the Waste Isolation Pilot Plant (WIPP). The RH waste must be emplaced before the disposal rooms are filled by contact-handled waste. Issues which must be resolved for this plan to be successful include: (1) construction of RH waste preparation and packaging facilities at large-quantity sites; (2) finding methods to get small-quantity site RH waste packaged and certified for disposal; (3) developing transportation systems and characterization facilities for RH TRU waste; (4) meeting lag storage needs; and (5) gaining public acceptance for the RH TRU waste program. Failure to resolve these issues in time to permit disposal according to the WIPP baseline plan will force either modification to the plan, or disposal or long-term storage of RH TRU waste at non-WIPP sites. The recommended strategy is to recognize, and take the needed actions to resolve, the open issues preventing disposal of RH TRU waste at WIPP on schedule. It is also recommended that the baseline plan be upgraded by adopting enhancements such as revised canister emplacement strategies and a more flexible waste transport system.

Bild, R.W. [Sandia National Lab., Albuquerque, NM (United States). Program Integration Dept.

1994-07-01T23:59:59.000Z

169

Transuranic Waste Program Framework Agreement - December Deliverable July 2012  

SciTech Connect (OSTI)

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

Jones, Patricia [Los Alamos National Laboratory

2012-07-19T23:59:59.000Z

170

Application of cryogenic grinding to achieve homogenization of transuranic wastes  

SciTech Connect (OSTI)

This paper describes work done at Los Alamos National Laboratory (LANL) in collaboration with the Department of Energy Rocky Flats Field Office (DOE/RFFO) and with the National Institute of Standards and Technology (NIST), Boulder, Colorado. Researchers on this project have developed a method for cryogenic grinding of mixed wastes to homogenize and, thereby, to acquire a representative sample of the materials. There are approximately 220,000 waste drums owned by the Rocky Flats Environmental Technology Site (RFETS)-50,000 at RFETS and 170,000 at the Idaho National Engineering Laboratory. The cost of sampling the heterogeneous distribution of waste in each drum is prohibitive. In an attempt to produce a homogeneous mixture of waste that would reduce greatly the cost of sampling, researchers at NIST and RFETS are developing a cryogenic grinder. The Los Alamos work herein described addresses the implementation issues of the task. The first issue was to ascertain whether samples of the {open_quotes}small particle{close_quotes} mixtures of materials present in the waste drums at RFETS were representative of actual drum contents. Second, it was necessary to determine at what temperature the grinding operation must be performed in order to minimize or to eliminate the release of volatile organic compounds present in the waste. Last, it was essential to evaluate any effect the liquid cryogen might have on the structural integrity and ventilation capacity of the glovebox system. Results of this study showed that representative samples could be and had been obtained, that some release of organics occurred below freezing because of sublimation, and that operation of the cryogenic grinding equipment inside the glovebox was feasible.

Atkins, W.H.; Hill, D.D.; Lucero, M.E.; Jaramillo, L.; Martinez, H.E. [and others

1996-08-01T23:59:59.000Z

171

Radioactive Waste Management BasisSept 2001  

SciTech Connect (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 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

172

Regulatory standards for permanent disposal of spent nuclear fuel and high-level radioactive waste.  

SciTech Connect (OSTI)

This paper provides a summary of observations drawn from twenty years of personal experience in working with regulatory criteria for the permanent disposal of radioactive waste for both the Waste Isolation Pilot Plant repository for transuranic defense waste and the proposed Yucca Mountain repository for spent nuclear fuel and high-level wastes. Rather than providing specific recommendations for regulatory criteria, my goal here is to provide a perspective on topics that are fundamental to how high-level radioactive waste disposal regulations have been implemented in the past. What are the main questions raised relevant to long-term disposal regulations? What has proven effective in the past? Where have regulatory requirements perhaps had unintended consequences? New regulations for radioactive waste disposal may prove necessary, but the drafting of these regulations may be premature until a broad range of policy issues are better addressed. In the interim, the perspective offered here may be helpful for framing policy discussions.

Swift, Peter N.

2010-08-01T23:59:59.000Z

173

Potential microbial impact on transuranic wastes under conditions expected in the Waste Isolation Pilot Plant (WIPP). Annual report, October 1, 1978-September 30, 1979  

SciTech Connect (OSTI)

Previous results were confirmed showing elevated frequencies of radiation-resistant bacteria in microorganisms isolated from shallow transuranic (TRU) burial soil that exhibits nanocurie levels of beta and gamma radioactivity. Research to determine whether plutonium could be methylated by the microbially produced methyl donor, methylcobalamine, was terminated when literature and consulting radiochemists confirmed that other alkylated transuranic elements are extremely short-lived in the presence of oxygen. Emphasis was placed on investigation of the dissolution of plutonium dioxide by complex formation between plutonium and a polyhydroxamate chelate similar to that produced by microorganisms. New chromatographic and spectrophotometric evidence supports previous results showing enhanced dissolution of alpha radioactivity when /sup 239/Pu dioxide was mixed with the chelate Desferol. Microbial degradation studies of citrate, ethylenediamine tetraacetate (EDTA), and nitrilo triacetate (NTA) chelates of europium are in progress. Current results are summarized. All of the chelates were found to degrade. The average half-life for citrate, NTA, and EDTA was 3.2, 8.0, and 28 years, respectively. Microbial CO/sub 2/ generation is also in progress in 72 tests on several waste matrices under potential WIPP isolation conditions. The mean rate of gas generation was 5.97 ..mu..g CO/sub 2//g waste/day. Increasing temperature increased rates of microbial gas generation across treatments of brine, varying water content, nutrient additions, and anaerobic conditions. No microbial growth was detected in experiments to enumerate and identify the microorganisms in rocksalt cores from the proposed WIPP site. This report contains the year's research results and recommendations derived for the design of safe storage of TRU wastes under geologic repository conditions.

Barnhart, B.J.; Campbell, E.W.; Martinez, E.; Caldwell, D.E.; Hallett, R.

1980-07-01T23:59:59.000Z

174

Rev August 2006 Radiation Safety Manual Section 14 Radioactive Waste  

E-Print Network [OSTI]

Rev August 2006 Radiation Safety Manual Section 14 ­ Radioactive Waste Page 14-1 Section 14 Radioactive Waste Contents A. Proper Collection, Disposal, and Packaging and Putrescible Animal Waste.........................14-8 a. Non-Radioactive Animal Waste

Wilcock, William

175

Hanford Site Hazardous waste determination report for transuranic debris waste streams NPFPDL1A, NPFPDL1B, NPFPDL1C and NPFPDL1D  

SciTech Connect (OSTI)

This Hazardous Waste Determination Report is intended to satisfy the terms of a Memorandum of Agreement (Agreement signed on June 16, 1999) between the U.S. Department of Energy and the New Mexico Environment Department. The Agreement pertains to the exchange of information before a final decision is made on the Waste Isolation Pilot Plant application for a permit under the ''New Mexico Hazardous Waste Act''. The Agreement will terminate upon the effective date of a final ''New Mexico Hazardous Waste Act'' permit for the Waste Isolation Pilot Plant. In keeping with the principles and terms of the Agreement, this report describes the waste stream data and information compilation process, and the physical and chemical analyses that the U.S. Department of Energy has performed on selected containers of transuranic debris waste to confirm that the waste is nonhazardous (non-mixed). This also summarizes the testing and analytical results that support the conclusion that the selected transuranic debris waste is not hazardous and thus, not subject to regulation under the ''Resource Conservation and Recovery Act'' or the ''New Mexico Hazardous Waste Act''. This report will be submitted to the New Mexico Environment Department no later than 45 days before the first shipment of waste from the Hanford Site to the Waste Isolation Pilot Plant, unless the parties mutually agree in writing to a shorter time. The 52 containers of transuranic debris waste addressed in this report were generated, packaged, and placed into storage between 1995 and 1997. Based on reviews of administrative documents, operating procedures, waste records, generator certifications, and personnel interviews, this transuranic debris waste was determined to be nonhazardous. This determination is supported by the data derived from nondestructive examination, confirmatory visual examination, and the results of container headspace gas sampling and analysis. Therefore, it is concluded that this transuranic debris waste, which consists of 52 containers from waste streams NPFPDLIA, NPFPDLIB, NPFPDLIC, and NPFPDLID, is not hazardous waste, and no hazardous waste numbers specified in Title 40 Code of Federal Regulations, Part 261, have been assigned. Accordingly, the 52 containers of transuranic debris waste addressed in this report meet the requirements for transuranic waste as defined by the Department of Energy Waste Acceptance Criteria for the Waste Isolation Pilot Plant. The 52 containers are acceptable for disposal at the Waste Isolation Pilot Plant as nonhazardous transuranic waste.

WINTERHALDER, J.A.

1999-09-29T23:59:59.000Z

176

DOE/EIS-0026-SA-06: Supplement Analysis for the Transportation of Transuranic Waste in TRUPACT-III Containers (9/25/07)  

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

6 6 Supplement Analysis for the Transportation of Transuranic Waste in TRUPACT-III Containers September 2007 U.S. Department of Energy Carlsbad Field Office Supplement Analysis for the Transportation of Transuranic Waste in TRUPACT-III Containers ii This page intentionally blank Supplement Analysis for the Transportation of Transuranic Waste in TRUPACT-III Containers iii TABLE OF CONTENTS Section Page 1.0 INTRODUCTION...........................................................................................................1 2.0 PURPOSE AND NEED FOR ACTION...........................................................................1 3.0 PROPOSED ACTION.....................................................................................................1

177

DOE/EIS-0200-SA-03: Supplement Analysis for the Treatment of Transuranic Waste at the Idaho National Laboratory (DOE/EIS-0200-SA-03) (02/08)  

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

the the Treatment of Transuranic Waste at the Idaho National Laboratory February 2008 U.S. Department of Energy Carlsbad Field Office Su~plement Analysis for the Treatment of Transuranic Waste at the Idaho National Laboratorv This page intentionally blank S u ~ ~ l e m e n t Analysis for the Treatment o f Transuranic Waste at the Idaho National Laboratow TABLE OF CONTENTS Section Page INTRODUCTION .............................................................................................................. 1 PURPOSE AND NEED FOR ACTION ............................................................................. 1 PROPOSED ACTION ........................................................................................................ 2 INL TREATMENT AND CHARACTERIZATION .......................................................... 3

178

INTERNATIONAL UNION OF OPERATING ENGINEERS NATIONAL HAZMAT PROGRAM - HANDSS-55 TRANSURANIC WASTE REPACKAGING MODULE  

SciTech Connect (OSTI)

The Transuranic waste generated at the Savannah River Site from nuclear weapons research, development, and production is currently estimated to be over 10,000 cubic meters. Over half of this amount is stored in 55-gallon drums. The waste in drums is primarily job control waste and equipment generated as the result of routine maintenance performed on the plutonium processing operations. Over the years that the drums have been accumulating, the regulatory definitions of materials approved for disposal have changed. Consequently, many of the drums now contain items that are not approved for disposal at DOE Waste Isolation Pilot Plant (WIPP). The HANDSS-55 technology is being developed to allow remote sorting of the items in these drums and then repackaging of the compliant items for disposal at WIPP.

Unknown

2001-08-31T23:59:59.000Z

179

Office of Civilian Radioactive Waste Management | Department...  

Office of Environmental Management (EM)

Civilian Radioactive Waste Management February 2006 Evaluation of technical impact on the Yucca Mountain Project technical basis resulting from issues raised by emails of former...

180

Annual Transportation Report for Radioactive Waste Shipments...  

National Nuclear Security Administration (NNSA)

ANNUAL TRANSPORTATION REPORT FY 2008 Radioactive Waste Shipments to and from the Nevada Test Site (NTS) February 2009 United States Department of Energy National Nuclear Security...

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


181

Spent fuel and radioactive waste inventories, projections, and characteristics. Revision 1  

SciTech Connect (OSTI)

Current inventories and characteristics of commercial spent fuels and both commercial and US Department of Energy (DOE) radioactive wastes were compiled through December 31, 1984, based on the most reliable information available from government sources and the open literature, technical reports, and direct contacts. Future waste and spent fuel to be generated through the year 2020 and characteristics of these materials are also presented. The information forecasted is consistent with the expected defense-related and private industrial and institutional activities and the latest DOE/Energy Information Administration (EIA) projections of US commercial nuclear power growth. Materials considered, on a chapter-by-chapter basis, are: spent fuel, high-level waste, transuranic waste, low-level waste, commercial uranium mill tailings, remedial action waste, and decommissioning waste. For each category, current and projected inventories are given through the year 2020, and the radioactivity and thermal power are calculated, based on reported or calculated isotopic compositions.

Not Available

1985-12-01T23:59:59.000Z

182

Buried transuranic wastes at ORNL: Review of past estimates and reconciliation with current data  

SciTech Connect (OSTI)

Inventories of buried (generally meaning disposed of) transuranic (TRU) wastes at Oak Ridge National Laboratory (ORNL) have been estimated for site remediation and waste management planning over a period of about two decades. Estimates were required because of inadequate waste characterization and incomplete disposal records. For a variety of reasons, including changing definitions of TRU wastes, differing objectives for the estimates, and poor historical data, the published results have sometimes been in conflict. The purpose of this review was (1) to attempt to explain both the rationale for and differences among the various estimates, and (2) to update the estimates based on more recent information obtained from waste characterization and from evaluations of ORNL waste data bases and historical records. The latter included information obtained from an expert panel`s review and reconciliation of inconsistencies in data identified during preparation of the ORNL input for the third revision of the Baseline Inventory Report for the Waste Isolation Pilot Plant. The results summarize current understanding of the relationship between past estimates of buried TRU wastes and provide the most up-to-date information on recorded burials thereafter. The limitations of available information on the latter and thus the need for improved waste characterization are highlighted.

Trabalka, J.R.

1997-09-01T23:59:59.000Z

183

Canister arrangement for storing radioactive waste  

DOE Patents [OSTI]

The subject invention relates to a canister arrangement for jointly storing high level radioactive chemical waste and metallic waste resulting from the reprocessing of nuclear reactor fuel elements. A cylindrical steel canister is provided with an elongated centrally disposed billet of the metallic waste and the chemical waste in vitreous form is disposed in the annulus surrounding the billet.

Lorenzo, Donald K. (Knoxville, TN); Van Cleve, Jr., John E. (Kingston, TN)

1982-01-01T23:59:59.000Z

184

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

SciTech Connect (OSTI)

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

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

2012-07-01T23:59:59.000Z

185

Final environmental impact statement. Management of commercially generated radioactive waste. Volume 2. Appendices  

SciTech Connect (OSTI)

This EIS analyzes the significant environmental impacts that could occur if various technologies for management and disposal of high-level and transuranic wastes from commercial nuclear power reactors were to be developed and implemented. This EIS will serve as the environmental input for the decision on which technology, or technologies, will be emphasized in further research and development activities in the commercial waste management program. The action proposed in this EIS is to (1) adopt a national strategy to develop mined geologic repositories for disposal of commercially generated high-level and transuranic radioactive waste (while continuing to examine subseabed and very deep hole disposal as potential backup technologies) and (2) conduct a R and D program to develop such facilities and the necessary technology to ensure the safe long-term containment and isolation of these wastes. The Department has considered in this statement: development of conventionally mined deep geologic repositories for disposal of spent fuel from nuclear power reactors and/or radioactive fuel reprocessing wastes; balanced development of several alternative disposal methods; and no waste disposal action. This volume contains appendices of supplementary data on waste management systems, geologic disposal, radiological standards, radiation dose calculation models, related health effects, baseline ecology, socio-economic conditions, hazard indices, comparison of defense and commercial wastes, design considerations, and wastes from thorium-based fuel cycle alternatives. (DMC)

Not Available

1980-10-01T23:59:59.000Z

186

Hanford Site annual dangerous waste report: Volume 2, Generator dangerous waste report, radioactive mixed waste  

SciTech Connect (OSTI)

This report contains information on radioactive mixed wastes at the Hanford Site. Information consists of shipment date, physical state, chemical nature, waste description, waste number, waste designation, weight, and waste designation.

NONE

1994-12-31T23:59:59.000Z

187

Shipping Remote Handled Transuranic Waste to the Waste Isolation Pilot Plant - An Operational Experience  

SciTech Connect (OSTI)

On January 18, 2007, the first ever shipment of Remote Handled Transuranic (RH TRU) waste left the gate at the Idaho National Laboratory (INL), headed toward the Waste Isolation Pilot Plant (WIPP) for disposal, thus concluding one of the most stressful, yet rewarding, periods the authors have ever experienced. The race began in earnest on October 16, 2006, with signature of the New Mexico Environment Department Secretary's Final Order, ruling that the '..draft permit as changed is hereby approved in its entirety.' This established the effective date of the approved permit as November 16, 2006. The permit modification was a consolidation of several Class 3 modification requests, one of which included incorporation of RH TRU requirements and another of which incorporated the requirements of Section 311 of Public Law 108-137. The obvious goal was to complete the first shipment by November 17. While many had anticipated its approval, the time had finally come to actually implement, and time seemed to be the main item lacking. At that point, even the most aggressive schedule that could be seriously documented showed a first ship date in March 2007. Even though planning for this eventuality had started in May 2005 with the arrival of the current Idaho Cleanup Project (ICP) contractor (and even before that), there were many facility and system modifications to complete, startup authorizations to fulfill, and many regulatory audits and approvals to obtain before the first drum could be loaded. Through the dedicated efforts of the ICP workers, the partnership with Department of Energy (DOE) - Idaho, the coordinated integration with the Central Characterization Project (CCP), the flexibility and understanding of the regulatory community, and the added encouragement of DOE - Carlsbad Field Office and at Headquarters, the first RH TRU canister was loaded on December 22, 2006. Following final regulatory approval on January 17, 2007, the historic event finally occurred the following day. While some of the success of this endeavor can be attributed to the sheer will and determination of the individuals involved, the fact that it was established and managed as a separate sub-project under the ICP, accounts for a majority of the success. Utilizing a structured project management approach, including development of, and management to, a performance baseline, allowed for timely decision making and the flexibility to adapt to changing conditions as the various aspects of the project matured. This paper provides some insight into how this was achieved, in a relatively short time, and provides an overview of the experience of start-up of a new retrieval, characterization, loading, and transportation operation in the midst of an aggressive cleanup project. Additionally, as one might expect, everything within the project did not go as planned, which provides a great opportunity to discuss some lessons learned. Finally, the first shipment was just the beginning. There are 224 additional shipments scheduled. In keeping with the theme of WM 2008, Phoenix Rising: Moving Forward in Waste Management, this paper will address the future opportunities and challenges of RH TRU waste management at the INL. (authors)

Anderson, S.; Bradford, J.; Clements, T.; Crisp, D.; Sherick, M. [CH2M-WG Idaho, Idaho Falls, ID (United States); D'Amico, E. [Washington TRU Solutions, Denver, CO (United States); Lattin, W. [United States Department of Energy, Idaho Operations Office, Idaho Falls, ID (United States); Watson, K. [United States Department of Energy, Carlsbad Field Office, Carlsbad, NM (United States)

2008-07-01T23:59:59.000Z

188

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

SciTech Connect (OSTI)

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

Not Available

1989-01-01T23:59:59.000Z

189

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

SciTech Connect (OSTI)

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

Not Available

1989-01-01T23:59:59.000Z

190

Portsmouth Site Delivers First Radioactive Waste Shipment to...  

Office of Environmental Management (EM)

Portsmouth Site Delivers First Radioactive Waste Shipment to Disposal Facility in Texas Portsmouth Site Delivers First Radioactive Waste Shipment to Disposal Facility in Texas...

191

2010 Annual Planning Summary for Civilian Radioactive Waste Management...  

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

Civilian Radioactive Waste Management (CRWM) 2010 Annual Planning Summary for Civilian Radioactive Waste Management (CRWM) Annual Planning Summaries briefly describe the status of...

192

Lab obtains approval to begin design on new radioactive waste...  

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

New radioactive waste staging facility Lab obtains approval to begin design on new radioactive waste staging facility The 4-acre complex will include multiple staging buildings...

193

Letter to Congress RE: Office of Civilian Radioactive Waste Management...  

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

to Congress RE: Office of Civilian Radioactive Waste Management's Annual Financial Report Letter to Congress RE: Office of Civilian Radioactive Waste Management's Annual Financial...

194

Sorting and disposal of hazardous laboratory Radioactive waste  

E-Print Network [OSTI]

Sorting and disposal of hazardous laboratory waste Radioactive waste Solid radioactive waste or in a Perspex box. Liquid radioactive waste collect in a screw-cap plastic bottle, ½ or 1 L size. Place bottles in a tray to avoid spill Final disposal of both solid and radioactive waste into the yellow barrel

Maoz, Shahar

195

Application of Field-Flow Fractionation to Radioactive Waste Disposal  

Science Journals Connector (OSTI)

Technical Paper / Argonne National Laboratory Specialists Workshop on Basic Research Needs for Nuclear Waste Management / Radioactive Waste

Marcus N. Myers; Kathy A. Graff; J. Calvin Giddings

196

WIPP TRANSURANIC WASTE How has the WIPP TRU Waste Inventory Changed  

E-Print Network [OSTI]

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

197

Waste Isolation Pilot Plant Transuranic Waste Baseline inventory report. Volume 3. Revision 1  

SciTech Connect (OSTI)

This report consists of information related to the waste forms at the WIPP facility from the waste originators. Data for retrievably stored, projected and total wastes are given.

NONE

1995-02-01T23:59:59.000Z

198

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

SciTech Connect (OSTI)

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

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

2002-01-01T23:59:59.000Z

199

Integrated Data Base for 1989: Spent fuel and radioactive waste inventories, projections, and characteristics  

SciTech Connect (OSTI)

The Integrated Data Base (IDB) Program has compiled current data on inventories and characteristics of commercial spent fuel and both commercial and US government-owned radioactive wastes through December 31, 1988. These data are based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. The current projections of future waste and spent fuel to be generated through the year 2020 and characteristics of these materials are also presented. The information forecasted is consistent with the latest US Department of Energy/Energy Information Administration (DOE/EIA) projections of US commercial nuclear power growth and the expected defense-related and private industrial and institutional (I/I) activities. The radioactive materials considered, on a chapter-by-chapter basis, are spent fuel, high-level waste, transuranic waste, low-level waste, commercial uranium mill tailings, remedial action waste, commercial reactor and fuel cycle facility decommissioning waste, and mixed (hazardous and radioactive) low-level waste. For most of these categories, current and projected inventories are given through the year 2020, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions. In addition, characteristics and current inventories are reported for miscellaneous, highly radioactive materials that may require geologic disposal. 45 figs., 119 tabs.

Not Available

1989-11-01T23:59:59.000Z

200

Integrated data base for 1990: US spent fuel and radioactive waste inventories, projections, and characteristics  

SciTech Connect (OSTI)

The Integrated Data Base (IDB) Program has compiled current data on inventories and characteristics of commercial spent fuel and both commercial and US government-owned radioactive wastes through December 31, 1989. These data are based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. The current projections of future waste and spent fuel to be generated through the year 2020 and characteristics of these materials are also presented. The information forecasted is consistent with the latest US Department of Energy/Energy Information Administration (DOE/EIA) projections of US commercial nuclear power growth and the expected DOE-related and private industrial and institutional (I/I) activities. The radioactive materials considered, on a chapter-by-chapter basis, are spent fuel, high-level waste, transuranic waste, low-level waste, commercial uranium mill tailings, environmental restoration wastes, commercial reactor and fuel cycle facility decommissioning wastes, and mixed (hazardous and radioactive) low-level waste. For most of these categories, current and projected inventories are given through the year 2020, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions. In addition, characteristics and current inventories are reported for miscellaneous radioactive materials that may require geologic disposal. 22 refs., 48 figs., 109 tabs.

Not Available

1990-10-01T23:59:59.000Z

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


201

COMPLIANCE FOR HANFORD WASTE RETRIEVAL RADIOACTIVE AIR EMISSIONS  

SciTech Connect (OSTI)

{sm_bullet} Since 1970, approximately 38,000 suspect transuranic (TRU) and TRU waste cont{approx}iners have been placed in retrievable storage on the Hanford Site in the 200Area's burial grounds. {sm_bullet} TRU waste is defined as waste containing greater than 100 nanocuries/gram of alpha emitting transuranic isotopes with half lives greater than 20 years. {sm_bullet} The United States currentl{approx}permanently disposes of TRU waste at the Waste Isolation Pilot Plant (WIPP).

FM SIMMONS

2009-06-30T23:59:59.000Z

202

Supplement Analysis for Disposal of Polychlorinated Biphenyl-Commingled Transuranic Waste at the Waste Isolation Pilot Plant (DOE/EIS-0026-SA02) (6/23/04)  

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

Disposal of Disposal of Polychlorinated Biphenyl-Commingled Transuranic Waste at the Waste Isolation Pilot Plant (DOE/EIS-0026-SA02) 1.0 Purpose and Need for Action Transuranic (TRU) waste is waste that contains alpha particle-emitting radionuclides with atomic numbers greater than uranium (92) and half-lives greater than 20 years, in concentrations greater than 100 nanocuries per gram of waste. Some TRU wastes are mixed with polychlorinated biphenyls (PCBs) (referred to as PCB-commingled TRU waste). PCBs exist in DOE's TRU waste as mixtures of synthetic organic chemicals with physical properties ranging from oily liquids to waxy solids. Exposure to PCBs can result in adverse health effects. For example, PCBs in blood or in fatty tissue as a result of inhalation, ingestion, or dermal absorption may cause reproductive effects,

203

Independent Oversight Review of the Fire Protection Program and Fire Protection Systems at the Transuranic Waste Processing Center, December 2013  

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

and Fire Protection Systems and Fire Protection Systems at the Transuranic Waste Processing Center December 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 Background ............................................................................................................................................. 1 3.0 Scope....................................................................................................................................................... 2 4.0 Methodology .......................................................................................................................................... 2

204

Integrated data base report--1996: US spent nuclear fuel and radioactive waste inventories, projections, and characteristics  

SciTech Connect (OSTI)

The Integrated Data Base Program has compiled historic data on inventories and characteristics of both commercial and U.S. Department of Energy (DOE) spent nuclear fuel (SNF) and commercial and U.S. government-owned radioactive wastes. Inventories of most of these materials are reported as of the end of fiscal year (FY) 1996, which is September 30, 1996. Commercial SNF and commercial uranium mill tailings inventories are reported on an end-of-calendar year (CY) basis. All SNF and radioactive waste data reported are based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. The information forecasted is consistent with the latest DOE/Energy Information Administration (EIA) projections of U.S. commercial nuclear power growth and the expected DOE-related and private industrial and institutional activities. The radioactive materials considered, on a chapter-by-chapter basis, are SNF, high-level waste, transuranic waste, low-level waste, uranium mill tailings, DOE Environmental Restoration Program contaminated environmental media, naturally occurring and accelerator-produced radioactive material, and mixed (hazardous and radioactive) low-level waste. For most of these categories, current and projected inventories are given through FY 2030, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions.

NONE

1997-12-01T23:59:59.000Z

205

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

SciTech Connect (OSTI)

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

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

1984-04-01T23:59:59.000Z

206

Integrated Data Base for 1992: US spent fuel and radioactive waste inventories, projections, and characteristics  

SciTech Connect (OSTI)

The Integrated Data Base (IDB) Program has compiled current data on inventories and characteristics of commercial spent fuel and both commercial and US government-owned radioactive wastes through December 31, 1991. These data are based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. The information forecasted is consistent with the latest US Department of Energy/Energy Information Administration (DOE/EIA) projections of US commercial nuclear power growth and the expected DOE-related and private industrial and institutional (I/I) activities. The radioactive materials considered, on a chapter-by-chapter basis, are spent nuclear fuel, high-level waste, transuranic waste, low-level waste, commercial uranium mill tailings, environmental restoration wastes, commercial reactor and fuel cycle facility decommissioning wastes, and mixed (hazardous and radioactive) low-level waste. For most of these categories, current and projected inventories are given through the year 2030, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions. In addition, characteristics and current inventories are reported for miscellaneous radioactive materials that may require geologic disposal.

Not Available

1992-10-01T23:59:59.000Z

207

Mobile loading transuranic waste at small quantity sites in the Department of Energy complex-10523  

SciTech Connect (OSTI)

Los Alamos National Laboratory, Carlsbad Office (LANL-CO), operates mobile loading operations for all of the large and small quantity transuranic (TRU) waste sites in the Department of Energy (DOE) complex. The mobile loading team performs loading and unloading evolutions for both contact handled (CH) and remote handled (RH) waste. For small quantity sites, many of which have yet to remove their TRU waste, the mobile loading team will load shipments that will ship to Idaho National Laboratory, a centralization site, or ship directly to the Waste Isolation Pilot Plant (WIPP). For example, Argonne National Laboratory and General Electric Vallecitos Nuclear Center have certified programs for RH waste so they will ship their RH waste directly to WIPP. Many of the other sites will ship their waste to Idaho for characterization and certification. The Mobile Loading Units (MLU) contain all of the necessary equipment needed to load CH and RH waste into the appropriate shipping vessels. Sites are required to provide additional equipment, such as cranes, fork trucks, and office space. The sites are also required to provide personnel to assist in the shipping operations. Each site requires a site visit from the mobile loading team to ensure that all of the necessary site equipment, site requirements and space for shipping can be provided. The mobile loading team works diligently with site representatives to ensure that all safety and regulatory requirements are met. Once the waste is ready and shipping needs are met, the mobile loading team can be scheduled to ship the waste. The CH MLU is designed to support TRUPACT-II and HalfPACT loading activities wherever needed within the DOE complex. The team that performs the mobile loading operation has obtained national certification under DOE for TRUPACT-II and HalfPACT loading and shipment certification. The RH MLU is designed to support removable lid canister (RLC) and RH-72B cask loading activities wherever needed within the DOE complex. The team that performs the mobile loading operation has obtained national certification under DOE for RLC and RH-72B Cask loading and shipment certification. To date, the mobile loading team has successfully made 2,131 CH and RH TRU waste shipments. The mobile loading team continues to provide each site with safe and compliant loading ofTRU waste.

Carter, Mitch [Los Alamos National Laboratory; Howard, Bryan [Los Alamos National Laboratory; Weyerman, Wade [Los Alamos National Laboratory; Mctaggart, Jerri [Los Alamos National Laboratory

2009-01-01T23:59:59.000Z

208

Review of Safety Basis Development for the Los Alamos National Laboratory Transuranic Waste Facility  

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

of6 of6 Subject: Review of Safety Basis HS: HSS CRAD 45-59 U.S. Department of Development for the Los Alamos Rev: 0 National Laboratory Transuranic Eff. Date: May 6, 2013 Energy Waste Facility - Criteria and Review Approach Document Office of Safety and ~ Emergency Management Acting Djector, Of~e of Safety and Evaluations Emergency Management Evaluations Date: May 6, 2013 firo,~ Page 1of6 Criteria and Review e;dJatnes 0. Low Approach Document Date: May 6, 2013 1.0 PURPOSE Within the Office of Health, Safety and Security (HSS), the Office of Enforcement and Oversight, Office of Safety and Emergency Management Evaluations (HS-45) mission is to assess the effectiveness of the environment, safety, health, and emergency management systems and practices used by line and

209

DOE Issues Final Request for Proposal for Oak Ridge Transuranic...  

Office of Environmental Management (EM)

Oak Ridge Transuranic Waste Processing Center Services DOE Issues Final Request for Proposal for Oak Ridge Transuranic Waste Processing Center Services October 14, 2014 - 2:16pm...

210

SRP RADIOACTIVE WASTE RELEASES S  

Office of Scientific and Technical Information (OSTI)

. . . . . . -- SRP RADIOACTIVE WASTE RELEASES S t a r t u p t h r o u g h 1 9 5 9 September 1 9 6 0 _- R E C O R D - W O R K S T E C H N I C A L D E P A R T M E N T 1 J. E. C o l e , W i l n i 1 4 W. P. 3ebbii 3 H. Worthington, Wilm 16 C. $?. P~.t-Lei-s~:; - 5 J. D. E l l e t t - 17 E. C. Morris 6 F. H. Endorf 19 3 . L. &tier 7 K. W. F r e n c h 20 bi. C . 3 e i n i g 8 J. K. Lower 2 1 2. 3 . 3 G : - x r 9 K. W. M i l l e t t 22 R . FJ . V 2 x 7 : W ~ ~ C k 1 c - 2 J. B. Tinker, W i h L-, i . c . E?-ens 4 W F i l e P. 3 . K t B U ? & J. A. Monier, Jr. 13. : . A. KcClesrer. 1 0 M. 2 . Wahl . - 23 C. Ashley C. W. J. Wende 24 T I S F i l e 11 J. W. Morris - 2s T'pC File D. E. Waters 26 P3D F i l e , 736-C R. B. Fenninger 33 V l ~ a l Records F i l e 12 W. P. Overbeck - 27 -23 P3D % x : r a Czpies P33 2e:ol.d C ~ p l *iB+ ' / - - & OF THIS DQCUMENT I S UNuMITEI) E. 1. ciu /'(I,\ 7' d

211

Solid Waste Management Plan. Revision 4  

SciTech Connect (OSTI)

The waste types discussed in this Solid Waste Management Plan are Municipal Solid Waste, Hazardous Waste, Low-Level Mixed Waste, Low-Level Radioactive Waste, and Transuranic Waste. The plan describes for each type of solid waste, the existing waste management facilities, the issues, and the assumptions used to develop the current management plan.

NONE

1995-04-26T23:59:59.000Z

212

Qualifying radioactive waste forms for geologic disposal  

SciTech Connect (OSTI)

We have developed a phased strategy that defines specific program-management activities and critical documentation for producing radioactive waste forms, from pyrochemical processing of spent nuclear fuel, that will be acceptable for geologic disposal by the US Department of Energy. The documentation of these waste forms begins with the decision to develop the pyroprocessing technology for spent fuel conditioning and ends with production of the last waste form for disposal. The need for this strategy is underscored by the fact that existing written guidance for establishing the acceptability for disposal of radioactive waste is largely limited to borosilicate glass forms generated from the treatment of aqueous reprocessing wastes. The existing guidance documents do not provide specific requirements and criteria for nonstandard waste forms such as those generated from pyrochemical processing operations.

Jardine, L.J. [Lawrence Livermore National Lab., CA (United States); Laidler, J.J.; McPheeters, C.C. [Argonne National Lab., IL (United States)

1994-09-01T23:59:59.000Z

213

Apparatus and method for radioactive waste screening  

SciTech Connect (OSTI)

An apparatus and method relating to screening radioactive waste are disclosed for ensuring that at least one calculated parameter for the measurement data of a sample falls within a range between an upper limit and a lower limit prior to the sample being packaged for disposal. The apparatus includes a radiation detector configured for detecting radioactivity and radionuclide content of the of the sample of radioactive waste and generating measurement data in response thereto, and a collimator including at least one aperture to direct a field of view of the radiation detector. The method includes measuring a radioactive content of a sample, and calculating one or more parameters from the radioactive content of the sample.

Akers, Douglas W.; Roybal, Lyle G.; Salomon, Hopi; Williams, Charles Leroy

2012-09-04T23:59:59.000Z

214

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

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

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

215

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

SciTech Connect (OSTI)

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

Not Available

1980-10-01T23:59:59.000Z

216

Integrated data base for 1988: Spent fuel and radioactive waste inventories, projections, and characteristics  

SciTech Connect (OSTI)

The Integrated Data Base (IDB) Program has compiled current data on inventories and characteristics of commercial spent fuel and both commercial and US government-owned radioactive wastes through December 31, 1987. These data are based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. The current projections of future waste and spent fuel to be generated through the year 2020 and characteristics of these materials are also presented. The information forecasted is consistent with the latest US Department of Energy/Energy Information Administration (DOE/EIA) projections of US commercial nuclear power growth and the expected defense-related and private industrial and institutional (I/I) activities. The radioactive materials considered, on a chapter-by-chapter basis are: spent fuel, high-level waste, transuranic waste, low-level waste, commercial uranium mill tailings, remedial action waste, and decommissioning waste. For each category, current and projected inventories are given through the year 2020, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions. In addition, characteristics and current inventories are reportd for miscellaneous, highly radioactive materials that may require geologic disposal. 89 refs., 46 figs., 104 tabs.

Not Available

1988-09-01T23:59:59.000Z

217

Integrated data base for 1987: Spent fuel and radioactive waste inventories, projections, and characteristics  

SciTech Connect (OSTI)

The Integrated Data Base (IDB) Program has compiled current data on inventories and characteristics of commercial spent fuel and both commercial and US government-owned radioactive wastes through December 31, 1986. These data are based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. Current projections of future waste and spent fuel to be generated through the year 2020 and characteristics of these materials are also presented. The information forecasted is consistent with the latest US Department of Energy/Energy Information Administration projections of US commercial nuclear power growth and the expected defense-related and private industrial and institutional activities. The radioactive materials considered, on a chapter-by-chapter basis, are spent fuel, high-level waste, transuranic waste, low-level waste, commercial uranium mill tailings, remedial action waste, and decommissioning waste. For each category, current and projected inventories are given through the year 2020, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions. In addition, characteristics and current inventories are reported for miscellaneous, highly radioactive materials that may require geologic disposal. 82 refs., 57 figs., 121 tabs.

Not Available

1987-09-01T23:59:59.000Z

218

Degradation of transuranic waste drums in underground storage at the Hanford Site  

SciTech Connect (OSTI)

In situ inspections were performed on tarp-covered 55-gallon drums of transuranic (TRU) waste stored underground at the Hanford Site. These inspections were part of a task to characterize TRU drums for extent of corrosion degradation and uncertainty in TRU designation (inaccuracy in earlier assay determinations may have led to drums that actually were low-level waste to be termed TRU), and to attempt to correlate accuracy of existing records with actual drum contents. Two separate storage trench sites were investigated; a total of 90 drums were inspected with ultrasonic techniques and 104 additional drums were visually inspected. A high-humidity environment in the underground storage trenches had been reported in earlier investigations and was expected to result in substantial corrosion degradation. However, corrosion was much less than expected. Only a small percentage of drums had significant corrosion (with one breach) and the maximum rate was estimated at 0.051 mm/yr (2 mils/yr). The corrosion time of underground exposure was 14 to 15 years. These inspection results should be applicable to other similar environments (this applicability should be restricted to arid climates such as the Hanford Site) where drums are stored underground but shielded from direct soil contact by a tarp or other means. Soil contact would lead to more rapid corrosion.

Duncan, D.R.

1996-05-07T23:59:59.000Z

219

Perspectives on Radioactive Waste Disposal: A Consideration of Economic Efficiency and Intergenerational Equity  

SciTech Connect (OSTI)

There are both internal and external pressures on the U.S. Department of Energy to reduce the estimated costs of isolating radioactive waste, $19 billion for transuranic waste at Waste Isolation Pilot Plant (WIPP) and $57 billion for high level waste at Yucca Mountain. The question arises whether economic analyses would add to the decision-making process to reduce costs yet maintain the same level of radiological protection. This paper examines the advantages and disadvantages of using cost-benefit analysis (CBA), a tool used to measure economic efficiency as an input for these decisions. Using a comparative research approach, we find that CBA analyses appear particularly applicable where the benefits and costs are in the near term. These findings can help policymakers become more informed on funding decisions and to develop public confidence in the merits of the program for waste disposal.

Neill, H. R.; Neill, R. H.

2003-02-25T23:59:59.000Z

220

Introduction to DOE Order 435.1 Low Level Radioactive Waste Disposal Requirements  

Broader source: Energy.gov [DOE]

Introduction to DOE Order 435.1 Low Level Radioactive Waste Disposal Requirements Christine Gelles*, U.S. Department of Energy ; Edward Regnier, U.S. Department of Energy; Andrew Wallo, U.S. Department of Energy Abstract: The Atomic Energy Act gives the U.S. Department of Energy (US DOE), the authority to regulate the management of radioactive waste generated by US DOE. This session will discuss DOE Order 435.1, which is protective of workers, public, and environment through specific requirements for the generation, treatment, storage, and disposal of US DOE radioactive waste. The Order is divided into four chapters: General Requirements, High-Level Waste, Transuranic Waste and Low-Level Waste. The requirements are consistent with existing promulgated Federal requirements but are specific to waste generated and disposed at US DOE facilities. A technical standard with requirements for documentation supporting the Disposal Authorization for a facility is also being prepared as well as a guide to accompany the Order. US DOE is in the process of updating the Order to maintain consistency with current practices and to increase efficiency in waste management. The draft Order will be available for public comment prior to being finalized.

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


221

Remote-handled transuranic system assessment appendices. Volume 2  

SciTech Connect (OSTI)

Volume 2 of this report contains six appendices to the report: Inventory and generation of remote-handled transuranic waste; Remote-handled transuranic waste site storage; Characterization of remote-handled transuranic waste; RH-TRU waste treatment alternatives system analysis; Packaging and transportation study; and Remote-handled transuranic waste disposal alternatives.

NONE

1995-11-01T23:59:59.000Z

222

Public involvement in radioactive waste management decisions  

SciTech Connect (OSTI)

Current repository siting efforts focus on Yucca Mountain, Nevada, where DOE`s Office of Civilian Radioactive Waste Management (OCRWM) is conducting exploratory studies to determine if the site is suitable. The state of Nevada has resisted these efforts: it has denied permits, brought suit against DOE, and publicly denounced the federal government`s decision to study Yucca Mountain. The state`s opposition reflects public opinion in Nevada, and has considerably slowed DOE`s progress in studying the site. The Yucca Mountain controversy demonstrates the importance of understanding public attitudes and their potential influence as DOE develops a program to manage radioactive waste. The strength and nature of Nevada`s opposition -- its ability to thwart if not outright derail DOE`s activities -- indicate a need to develop alternative methods for making decisions that affect the public. This report analyzes public participation as a key component of this openness, one that provides a means of garnering acceptance of, or reducing public opposition to, DOE`s radioactive waste management activities, including facility siting and transportation. The first section, Public Perceptions: Attitudes, Trust, and Theory, reviews the risk-perception literature to identify how the public perceives the risks associated with radioactivity. DOE and the Public discusses DOE`s low level of credibility among the general public as the product, in part, of the department`s past actions. This section looks at the three components of the radioactive waste management program -- disposal, storage, and transportation -- and the different ways DOE has approached the problem of public confidence in each case. Midwestern Radioactive Waste Management Histories focuses on selected Midwestern facility-siting and transportation activities involving radioactive materials.

NONE

1994-04-01T23:59:59.000Z

223

Radioactive waste management in the former USSR  

SciTech Connect (OSTI)

Radioactive waste materials--and the methods being used to treat, process, store, transport, and dispose of them--have come under increased scrutiny over last decade, both nationally and internationally. Nuclear waste practices in the former Soviet Union, arguably the world's largest nuclear waste management system, are of obvious interest and may affect practices in other countries. In addition, poor waste management practices are causing increasing technical, political, and economic problems for the Soviet Union, and this will undoubtedly influence future strategies. this report was prepared as part of a continuing effort to gain a better understanding of the radioactive waste management program in the former Soviet Union. the scope of this study covers all publicly known radioactive waste management activities in the former Soviet Union as of April 1992, and is based on a review of a wide variety of literature sources, including documents, meeting presentations, and data base searches of worldwide press releases. The study focuses primarily on nuclear waste management activities in the former Soviet Union, but relevant background information on nuclear reactors is also provided in appendixes.

Bradley, D.J.

1992-06-01T23:59:59.000Z

224

Geochemical aspects of radioactive waste disposal  

SciTech Connect (OSTI)

The book addresses various topics related to the geochemistry of waste disposal: natural radioactivity, kinds of radioactive waste, details of possible disposal sites, low-level waste, uranium mill tailing, natural analogs, waste forms, and engineered barriers. Emphasis throughout is on the importance of natural analogs, the behavior of elements resembling those to be put in a waste repository as they occur in natural situations where the temperature, pressure, and movement of ground water are similar to those expected near a repository. The author is convinced that conclusions drawn from the study of analog elements are directly applicable to predictions about radionuclide behavior, and that the observed near-immobility of most of these elements in comparable geologic environments is good evidence that radioactive waste can be disposed of underground with negligible effects on the biosphere. Much of his own research has been in this area, and the best parts of the book are the descriptions of his work on trace elements in the salt minerals at the Waste Isolation Pilot Plant in southeastern New Mexico, on the movement of radionuclides and their daughter elements from the famous Precambrian reactor at Oklahoma in Gabon, and on the distribution of analog elements in rocks near the contacts of igneous intrusions.

Brookins, D.G.

1984-01-01T23:59:59.000Z

225

Selected radionuclides important to low-level radioactive waste management  

SciTech Connect (OSTI)

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

NONE

1996-11-01T23:59:59.000Z

226

EVALUATION OF RISKS AND WASTE CHARACTERIZATION REQUIREMENTS FOR THE TRANSURANIC WASTE EMPLACED IN WIPP DURING 1999  

SciTech Connect (OSTI)

Specifically this report: 1. Compares requirements of the WAP that are pertinent from a technical viewpoint with the WIPP pre-Permit waste characterization program, 2. Presents the results of a risk analysis of the currently emplaced wastes. Expected and bounding risks from routine operations and possible accidents are evaluated; and 3. Provides conclusions and recommendations.

Channell, J.K.; Walker, B.A.

2000-05-01T23:59:59.000Z

227

EIS-0286: Hanford Solid (Radioactive and Hazardous) Waste Program  

Broader source: Energy.gov [DOE]

The Hanford Site Solid (Radioactive and Hazardous) Waste Program Environmental Impact Statement (HSW EIS) analyzes the proposed waste management practices at the Hanford Site.

228

Retrieval Of Final Stored Radioactive Waste Resumes | Department...  

Office of Environmental Management (EM)

Retrieval Of Final Stored Radioactive Waste Resumes Retrieval Of Final Stored Radioactive Waste Resumes April 18, 2012 - 12:00pm Addthis Media Contacts Danielle Miller, DOE-Idaho...

229

Low-Level Radioactive Waste Disposal Act (Pennsylvania) | Department of  

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

Low-Level Radioactive Waste Disposal Act (Pennsylvania) Low-Level Radioactive Waste Disposal Act (Pennsylvania) Low-Level Radioactive Waste Disposal Act (Pennsylvania) < Back Eligibility Utility Commercial Investor-Owned Utility State/Provincial Govt Municipal/Public Utility Local Government Rural Electric Cooperative Transportation Program Info State Pennsylvania Program Type Environmental Regulations Provider Pennsylvania Department of Environmental Protection This act provides a comprehensive strategy for the siting of commercial low-level waste compactors and other waste management facilities, and to ensure the proper transportation, disposal and storage of low-level radioactive waste. Commercial incineration of radioactive wastes is prohibited. Licenses are required for low-level radioactive waste disposal facilities not licensed to accept low-level radioactive waste. Disposal at

230

PUBLIC AND REGULATORY ACCEPTANCE OF BLENDING OF RADIOACTIVE WASTE VS DILUTION  

SciTech Connect (OSTI)

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

Goldston, W.

2010-11-30T23:59:59.000Z

231

High-level radioactive wastes. Supplement 1  

SciTech Connect (OSTI)

This bibliography contains information on high-level radioactive wastes included in the Department of Energy's Energy Data Base from August 1982 through December 1983. These citations are to research reports, journal articles, books, patents, theses, and conference papers from worldwide sources. Five indexes, each preceded by a brief description, are provided: Corporate Author, Personal Author, Subject, Contract Number, and Report Number. 1452 citations.

McLaren, L.H. (ed.)

1984-09-01T23:59:59.000Z

232

Annual radioactive waste tank inspection program: 1995  

SciTech Connect (OSTI)

Aqueous radioactive wastes from Savannah River Site (SRS) separations processes are contained in large underground carbon steel tanks. Inspections made during 1995 to evaluate these vessels and evaluations based on data accrued by inspections performed since the tanks were constructed are the subject of this report

McNatt, F.G. Sr.

1996-04-01T23:59:59.000Z

233

1 INSTRODUCTION In the concept of geological radioactive waste disposal,  

E-Print Network [OSTI]

1 INSTRODUCTION In the concept of geological radioactive waste disposal, argillite is being of the radioactive waste disposal, the host rock will be subjected to various thermo-hydro-mechanical loadings, thermal solicitation comes from the heat emitting from the radioactive waste packages. On one hand

Boyer, Edmond

234

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

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

HSW HSW EIS January 2004 1.6 Figure 1.2. States with Radioactive Waste Disposal Activities Final HSW EIS January 2004 1.12 Figure 1.3. Relationship of the HSW EIS to Other Hanford Cleanup Operations, Material Management Activities, and Key Environmental Reviews 2.17 Final HSW EIS January 2004 Figure 2.6. Waste Receiving and Processing Facility Figure 2.7. X-Ray Image of Transuranic Waste Drum Contents M0212-0286.11 HSW EIS 12-10-02 M0212-0286.12 HSW EIS 12-10-02 2.17 Final HSW EIS January 2004 Figure 2.6. Waste Receiving and Processing Facility Figure 2.7. X-Ray Image of Transuranic Waste Drum Contents M0212-0286.11 HSW EIS 12-10-02 M0212-0286.12 HSW EIS 12-10-02 Final HSW EIS January 2004 2.34 Figure 2.18. Typical Liner System Final HSW EIS January 2004 2.36

235

Radioactive waste shipments to Hanford Retrievable Storage from the General Electric Vallecitos Nuclear Center, Pleasanton, California  

SciTech Connect (OSTI)

During the next two decades the transuranic (TRU) wastes now stored in the burial trenches and storage facilities at the Hanford Site are to be retrieved, processed at the Waste Receiving and Processing Facility, and shipped to the Waste Isolation Pilot Plant near Carlsbad, New Mexico for final disposal. Approximately 3.8% of the TRU waste to be retrieved for shipment to WIPP was generated at the General Electric (GE) Vallecitos Nuclear Center (VNC) in Pleasanton, California and shipped to the Hanford Site for storage. The purpose of this report is to characterize these radioactive solid wastes using process knowledge, existing records, and oral history interviews. The waste was generated almost exclusively from the activities, of the Plutonium Fuels Development Laboratory and the Plutonium Analytical Laboratory. Section 2.0 provides further details of the VNC physical plant, facility operations, facility history, and current status. The solid radioactive wastes were associated with two US Atomic Energy Commission/US Department of Energy reactor programs -- the Fast Ceramic Reactor (FCR) program, and the Fast Flux Test Reactor (FFTR) program. These programs involved the fabrication and testing of fuel assemblies that utilized plutonium in an oxide form. The types and estimated quantities of waste resulting from these programs are discussed in detail in Section 3.0. A detailed discussion of the packaging and handling procedures used for the VNC radioactive wastes shipped to the Hanford Site is provided in Section 4.0. Section 5.0 provides an in-depth look at this waste including the following: weight and volume of the waste, container types and numbers, physical description of the waste, radiological components, hazardous constituents, and current storage/disposal locations.

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

1993-10-01T23:59:59.000Z

236

Underground facility area requirements for a radioactive waste repository at Yucca Mountain  

SciTech Connect (OSTI)

The Nevada Nuclear Waste Storage Investigations Project, managed by the US Department of Energy`s Nevada Operations Office, is examining the feasibility of siting a repository for high-level radioactive waste at Yucca Mountain on and adjacent to the Nevada Test Site. Preliminary waste descriptions and preliminary areal power density calculations have been completed, and the Topopah Spring Member has been recommended as the emplacement unit. Using these data, an effort has begun to determine the area needed for the underground facility. This report describes work performed to determine the area needed to emplace waste equivalent to 70,000 metric tons of uranium (MTU) initially loaded in commercial power reactors. The area needed for support functions is also described. The total area of the underground facility depends on the types of waste received, the amount of each type of waste received, the areal power density assumed, and the emplacement configuration chosen (horizontal or vertical emplacement). The areas range from about 1240 acres to about 1520 acres. For vertical emplacement of the reference inventory of spent fuel, 1520 acres are required. A significant finding of this report is the importance of low-heat-producing wastes (defense high-level waste, West Valley high-level waste, cladding hulls, transuranic waste, and spent fuel hardware) when calculating the area required for the underground facility. If other wastes are included and the spent fuel capacity is reduced consistent with a total capacity of 70,000 MTU, the area required will be smaller.

Mansure, A.J.

1985-11-01T23:59:59.000Z

237

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

SciTech Connect (OSTI)

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

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

1991-07-01T23:59:59.000Z

238

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

SciTech Connect (OSTI)

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

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

1991-07-01T23:59:59.000Z

239

Waste gas combustion in a Hanford radioactive waste tank  

SciTech Connect (OSTI)

It has been observed that a high-level radioactive waste tank generates quantities of hydrogen, ammonia, nitrous oxide, and nitrogen that are potentially well within flammability limits. These gases are produced from chemical and nuclear decay reactions in a slurry of radioactive waste materials. Significant amounts of combustible and reactant gases accumulate in the waste over a 110- to 120-d period. The slurry becomes Taylor unstable owing to the buoyancy of the gases trapped in a matrix of sodium nitrate and nitrite salts. As the contents of the tank roll over, the generated waste gases rupture through the waste material surface, allowing the gases to be transported and mixed with air in the cover-gas space in the dome of the tank. An ignition source is postulated in the dome space where the waste gases combust in the presence of air resulting in pressure and temperature loadings on the double-walled waste tank. This analysis is conducted with hydrogen mixing studies HMS, a three-dimensional, time-dependent fluid dynamics code coupled with finite-rate chemical kinetics. The waste tank has a ventilation system designed to maintain a slight negative gage pressure during normal operation. We modeled the ventilation system with the transient reactor analysis code (TRAC), and we coupled these two best-estimate accident analysis computer codes to model the ventilation system response to pressures and temperatures generated by the hydrogen and ammonia combustion.

Travis, J.R.; Fujita, R.K.; Spore, J.W.

1994-07-01T23:59:59.000Z

240

Combustible radioactive waste treatment by incineration and chemical digestion  

SciTech Connect (OSTI)

A review is given of present and planned combustible radioactive waste treatment systems in the US. Advantages and disadvantages of various systems are considered. Design waste streams are discussed in relation to waste composition, radioactive contaminants by amount and type, and special operating problems caused by the waste.

Stretz, L.A.; Crippen, M.D.; Allen, C.R.

1980-05-28T23:59:59.000Z

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


241

Integrated Data Base for 1991: US spent fuel and radioactive waste inventories, projections, and characteristics. [Contains glossary  

SciTech Connect (OSTI)

The Integrated Data Base (IDB) Program has compiled current data on inventories and characteristics of commercial spent fuel and both commercial and US government-owned radioactive wastes through December 31, 1990. These data are based on the most reliable information available form government sources, the open literature, technical reports, and direct contacts. The current projections of future waste and spent fuel to be generated generally through the year 2020 and characteristics of these materials are also presented. The information forecasted is consistent with the latest US Department of Energy/Energy Information Administration (DOE/EIA) projections of US commercial nuclear power growth and the expected DOE-related and private industrial and institutional (I/I) activities. The radioactive materials considered are spent fuel, high-level waste, transuranic waste, low-level waste, commercial uranium mill tailings, environmental restoration wastes, commercial reactor and fuel cycle facility decommissioning wastes, and mixed (hazardous and radioactive) low-level waste. For most of these categories, current and projected inventories are given through the year 2020, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions. In addition, characteristics and current inventories are reported for miscellaneous radioactive materials that may require geologic disposal. 160 refs., 61 figs., 142 tabs.

Not Available

1991-10-01T23:59:59.000Z

242

Integrated Data Base for 1991: US spent fuel and radioactive waste inventories, projections, and characteristics. Revision 7  

SciTech Connect (OSTI)

The Integrated Data Base (IDB) Program has compiled current data on inventories and characteristics of commercial spent fuel and both commercial and US government-owned radioactive wastes through December 31, 1990. These data are based on the most reliable information available form government sources, the open literature, technical reports, and direct contacts. The current projections of future waste and spent fuel to be generated generally through the year 2020 and characteristics of these materials are also presented. The information forecasted is consistent with the latest US Department of Energy/Energy Information Administration (DOE/EIA) projections of US commercial nuclear power growth and the expected DOE-related and private industrial and institutional (I/I) activities. The radioactive materials considered are spent fuel, high-level waste, transuranic waste, low-level waste, commercial uranium mill tailings, environmental restoration wastes, commercial reactor and fuel cycle facility decommissioning wastes, and mixed (hazardous and radioactive) low-level waste. For most of these categories, current and projected inventories are given through the year 2020, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions. In addition, characteristics and current inventories are reported for miscellaneous radioactive materials that may require geologic disposal. 160 refs., 61 figs., 142 tabs.

Not Available

1991-10-01T23:59:59.000Z

243

Geological problems in radioactive waste isolation  

SciTech Connect (OSTI)

The problem of isolating radioactive wastes from the biosphere presents specialists in the fields of earth sciences with some of the most complicated problems they have ever encountered. This is especially true for high level waste (HLW) which must be isolated in the underground and away from the biosphere for thousands of years. Essentially every country that is generating electricity in nuclear power plants is faced with the problem of isolating the radioactive wastes that are produced. The general consensus is that this can be accomplished by selecting an appropriate geologic setting and carefully designing the rock repository. Much new technology is being developed to solve the problems that have been raised and there is a continuing need to publish the results of new developments for the benefit of all concerned. The 28th International Geologic Congress that was held July 9--19, 1989 in Washington, DC provided an opportunity for earth scientists to gather for detailed discussions on these problems. Workshop W3B on the subject, Geological Problems in Radioactive Waste Isolation -- A World Wide Review'' was organized by Paul A Witherspoon and Ghislain de Marsily and convened July 15--16, 1989 Reports from 19 countries have been gathered for this publication. Individual papers have been cataloged separately.

Witherspoon, P.A. (ed.)

1991-01-01T23:59:59.000Z

244

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

SciTech Connect (OSTI)

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

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

1996-08-01T23:59:59.000Z

245

Southwestern Low-Level Radioactive Waste Disposal Compact (South Dakota) |  

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

Southwestern Low-Level Radioactive Waste Disposal Compact (South Southwestern Low-Level Radioactive Waste Disposal Compact (South Dakota) Southwestern Low-Level Radioactive Waste Disposal Compact (South Dakota) < Back Eligibility Utility Investor-Owned Utility Industrial Construction Municipal/Public Utility Rural Electric Cooperative Fuel Distributor Program Info State South Dakota Program Type Siting and Permitting Provider Southwestern Low-Level Radioactive Waste Commission This legislation authorizes the state's entrance into the Southwestern Low-Level Radioactive Waste Disposal Compact, which provides for the cooperative management of low-level radioactive waste. The Compact is administered by a commission, which can regulate and impose fees on in-state radioactive waste generators. The states of Arizona, California,

246

Hazardous and Radioactive Mixed Waste  

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

To establish hazardous waste management procedures for facilities operated under authority of the Atomic Energy Act of 1954, as amended (AEA). The procedures will follow. to the extent practicable, regulations issued by the Environmental Protection Agency (EPA) pursuant to the Resource Conservation and Recovery Act of 1976 (RCRA). Although Department of Energy (DOE) operations conducted under authority other than the AEA are subject to EPA or State regulations conforming with RCRA, facilities administered under the authority of the AEA are not bound by such requirements.

1982-12-31T23:59:59.000Z

247

Integrated data base for 1986: spent fuel and radioactive waste inventories, projections, and characteristics. Revision 2  

SciTech Connect (OSTI)

The Integrated Data Base (IDB) Program has compiled current data on inventories and characteristics of commercial spent fuel and both commercial and US Department of Energy (DOE) radioactive wastes through December 31, 1985, based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. Current projections of future waste and spent fuel to be generated through the year 2020 and characteristics of these materials are also presented. The information forecasted is consistent with the expected defense-related and private industrial and institutional activities and the latest DOE/Energy Information Administration (EIA) projections of US commercial nuclear power growth. The materials considered, on a chapter-by-chapter basis, are: spent fuel, high-level waste, transuranic waste, low-level waste, commercial uranium mill tailings, remedial action waste, and decommissioning waste. For each category, current and projected inventories are given through the year 2020, and the radioactivity and thermal power are calculated based on reported or calculated isotopic compositions.

Not Available

1986-09-01T23:59:59.000Z

248

E-Print Network 3.0 - activity radioactive waste Sample Search...  

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

waste Search Powered by Explorit Topic List Advanced Search Sample search results for: activity radioactive waste...

249

System for handling and storing radioactive waste  

DOE Patents [OSTI]

A system and method for handling and storing spent reactor fuel and other solid radioactive waste, including canisters to contain the elements of solid waste, storage racks to hold a plurality of such canisters, storage bays to store these racks in isolation by means of shielded doors in the bays. This system also includes means for remotely positioning the racks in the bays and an access tunnel within which the remotely operated means is located to position a rack in a selected bay. The modular type of these bays will facilitate the construction of additional bays and access tunnel extension.

Anderson, John K. (San Diego, CA); Lindemann, Paul E. (Escondido, CA)

1984-01-01T23:59:59.000Z

250

Assessment of degradation concerns for spent fuel, high-level wastes, and transuranic wastes in monitored retrievalbe storage  

SciTech Connect (OSTI)

It has been concluded that there are no significant degradation mechanisms that could prevent the design, construction, and safe operation of monitored retrievable storage (MRS) facilities. However, there are some long-term degradation mechanisms that could affect the ability to maintain or readily retrieve spent fuel (SF), high-level wastes (HLW), and transuranic wastes (TRUW) several decades after emplacement. Although catastrophic failures are not anticipated, long-term degradation mechanisms have been identified that could, under certain conditions, cause failure of the SF cladding and/or failure of TRUW storage containers. Stress rupture limits for Zircaloy-clad SF in MRS range from 300 to 440/sup 0/C, based on limited data. Additional tests on irradiated Zircaloy (3- to 5-year duration) are needed to narrow this uncertainty. Cladding defect sizes could increase in air as a result of fuel density decreases due to oxidation. Oxidation tests (3- to 5-year duration) on SF are also needed to verify oxidation rates in air and to determine temperatures below which monitoring of an inert cover gas would not be required. Few, if any, changes in the physical state of HLW glass or canisters or their performance would occur under projected MRS conditions. The major uncertainty for HLW is in the heat transfer through cracked glass and glass devitrification above 500/sup 0/C. Additional study of TRUW is required. Some fraction of present TRUW containers would probably fail within the first 100 years of MRS, and some TRUW would be highly degraded upon retrieval, even in unfailed containers. One possible solution is the design of a 100-year container. 93 references, 28 figures, 17 tables.

Guenther, R.J.; Gilbert, E.R.; Slate, S.C.; Partain, W.L.; Divine, J.R.; Kreid, D.K.

1984-01-01T23:59:59.000Z

251

1969 AUDIT OF SRP RADIOACTIVE WASTE  

Office of Scientific and Technical Information (OSTI)

969 AUDIT OF SRP RADIOACTIVE WASTE 969 AUDIT OF SRP RADIOACTIVE WASTE bY C . Ashley A p r i l 1970 Radiological Sciences Division Savannah River Laboratory E. 1. du Pont de Nemours & Co. Aiken, South Carolina 29801 DISCLAIMER Portions of this document may be illegible in electronic image products. Images are produced from the best avaiiable original document. . . . CONTENTS Page I n t r o d u c t i o n . . . . . . . . . . . . . . . . . . . . . . . . 5 Summary . . . . . . . . . . . . . . . . . . . . . . . . . . 5 Releases t o t h e Atmosphere . . . . . . . . . . . . . . . . . 6 S e p a r a t i o n s Areas . . . . . . . . . . . . . . . . . . . . 6 TNX and Building 773-A . . . . . . . . . . . . . . . . . 8 Reactor Areas . . . . . . . . . . . . . . . . . . . . . . 7 Releases t o E f f l u e n t Streams . . . . . . . . . . . . . . . . 8 S e p a r a t i o n s Areas . . . . . . . . . . . . . . . . . . . . 8 DArea . . . . . . . . . . . . . . . . . . . . . . . . . 8 R e a c t o r A r e a s . . . . . . . . . . . . . . . . . . . . . . 9

252

Office of Civilian Radioactive Waste Management  

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

RW-0583 RW-0583 QA:N/A Office of Civilian Radioactive Waste Management EVALUATION OF TECHNICAL IMPACT ON THE YUCCA MOUNTAIN PROJECT TECHNICAL BASIS RESULTING FROM ISSUES RAISED BY EMAILS OF FORMER PROJECT PARTICIPANTS February 2006 This page intentionally left blank. Table of Contents Executive Summary .............................................................................................................v 1. Introduction..............................................................................................................1 1.1 Background ....................................................................................................1 1.2 Role of the USGS in Yucca Mountain Work.................................................2

253

Integrated Data Base report--1993: U.S. spent nuclear fuel and radioactive waste inventories, projections, and characteristics. Revision 10  

SciTech Connect (OSTI)

The Integrated Data Base Program has compiled historic data on inventories and characteristics of both commercial and DOE spent nuclear fuel; also, commercial and US government-owned radioactive wastes through December 31, 1993. These data are based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. The information forecasted is consistent with the latest US Department of Energy/Energy Information Administration projections of US commercial nuclear power growth and the expected DOE-related and private industrial and institutional activities. The radioactive materials considered, on a chapter-by-chapter basis, are spent nuclear fuel, high-level waste, transuranic waste, low-level waste, commercial uranium mill tailings, DOE Environmental Restoration Program wastes, commercial reactor and fuel-cycle facility decommissioning wastes, and mixed (hazardous and radioactive) low-level waste. For most of these categories, current and projected inventories are given the calendar-year 2030, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions. In addition, characteristics and current inventories are reported for miscellaneous radioactive materials that may require geologic disposal. 256 refs., 38 figs., 141 tabs.

Not Available

1994-12-01T23:59:59.000Z

254

ANNUAL RADIOACTIVE WASTE TANK INSPECTION PROGRAM 2009  

SciTech Connect (OSTI)

Aqueous radioactive wastes from Savannah River Site (SRS) separations and vitrification processes are contained in large underground carbon steel tanks. Inspections made during 2009 to evaluate these vessels and other waste handling facilities along with evaluations based on data from previous inspections are the subject of this report. The 2009 inspection program revealed that the structural integrity and waste confinement capability of the Savannah River Site waste tanks were maintained. All inspections scheduled per LWO-LWE-2008-00423, HLW Tank Farm Inspection Plan for 2009, were completed. All Ultrasonic measurements (UT) performed in 2009 met the requirements of C-ESG-00006, In-Service Inspection Program for High Level Waste Tanks, Rev. 1, and WSRC-TR-2002-00061, Rev.4. UT inspections were performed on Tank 29 and the findings are documented in SRNL-STI-2009-00559, Tank Inspection NDE Results for Fiscal Year 2009, Waste Tank 29. Post chemical cleaning UT measurements were made in Tank 6 and the results are documented in SRNL-STI-2009-00560, Tank Inspection NDE Results Tank 6, Including Summary of Waste Removal Support Activities in Tanks 5 and 6. A total of 6669 photographs were made and 1276 visual and video inspections were performed during 2009. Twenty-Two new leaksites were identified in 2009. The locations of these leaksites are documented in C-ESR-G-00003, SRS High Level Waste Tank Leaksite Information, Rev.4. Fifteen leaksites at Tank 5 were documented during tank wall/annulus cleaning activities. Five leaksites at Tank 6 were documented during tank wall/annulus cleaning activities. Two new leaksites were identified at Tank 19 during waste removal activities. Previously documented leaksites were reactivated at Tanks 5 and 12 during waste removal activities. Also, a very small amount of additional leakage from a previously identified leaksite at Tank 14 was observed.

West, B.; Waltz, R.

2010-06-21T23:59:59.000Z

255

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

Broader source: Energy.gov [DOE]

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

256

Decontamination and Volume Reduction System for Transuranic Waste at Los Alamos National Laboratory, Los Alamos, New Mexico Environmental Assessment  

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

69 69 Decontamination and Volume Reduction System for Transuranic Waste at Los Alamos National Laboratory, Los Alamos, New Mexico Environmental Assessment Final Document Date Prepared: June 23, 1999 Prepared by: U.S. Department of Energy, Los Alamos Area Office Final document Decontamination and Volume Reduction System EA June 23, 1999 DOE/LAAO iii TABLE OF CONTENTS ACRONYMS AND TERMS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . v EXECUTIVE SUMMARY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . vii 1.0 PURPOSE AND NEED FOR AGENCY ACTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 1.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 1.2 Background . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

257

CHAPTER 5-RADIOACTIVE WASTE MANAGEMENT  

SciTech Connect (OSTI)

The ore pitchblende was discovered in the 1750's near Joachimstal in what is now the Czech Republic. Used as a colorant in glazes, uranium was identified in 1789 as the active ingredient by chemist Martin Klaproth. In 1896, French physicist Henri Becquerel studied uranium minerals as part of his investigations into the phenomenon of fluorescence. He discovered a strange energy emanating from the material which he dubbed 'rayons uranique.' Unable to explain the origins of this energy, he set the problem aside. About two years later, a young Polish graduate student was looking for a project for her dissertation. Marie Sklodowska Curie, working with her husband Pierre, picked up on Becquerel's work and, in the course of seeking out more information on uranium, discovered two new elements (polonium and radium) which exhibited the same phenomenon, but were even more powerful. The Curies recognized the energy, which they now called 'radioactivity,' as something very new, requiring a new interpretation, new science. This discovery led to what some view as the 'golden age of nuclear science' (1895-1945) when countries throughout Europe devoted large resources to understand the properties and potential of this material. By World War II, the potential to harness this energy for a destructive device had been recognized and by 1939, Otto Hahn and Fritz Strassman showed that fission not only released a lot of energy but that it also released additional neutrons which could cause fission in other uranium nuclei leading to a self-sustaining chain reaction and an enormous release of energy. This suggestion was soon confirmed experimentally by other scientists and the race to develop an atomic bomb was on. The rest of the development history which lead to the bombing of Hiroshima and Nagasaki in 1945 is well chronicled. After World War II, development of more powerful weapons systems by the United States and the Soviet Union continued to advance nuclear science. It was this defense application that formed the basis for the commercial nuclear power industry.

Marra, J.

2010-05-05T23:59:59.000Z

258

Final environmental impact statement. Management of commercially generated radioactive waste. Volume 3. Public comments hearing board report  

SciTech Connect (OSTI)

This EIS analyzes the significant environmental impacts that could occur if various technologies for management and disposal of high-level and transuranic wastes from commercial nuclear power reactors were to be developed and implemented. This EIS will serve as the environmental input for the decision on which technology, or technologies, will be emphasized in further research and development activities in the commercial waste management program. The action proposed in this EIS is to (1) adopt a national strategy to develop mined geologic repositories for disposal of commercially generated high-level and transuranic radioactive waste (while continuing to examine subseabed and very deep hole disposal as potential backup technologies) and (2) conduct a R and D program to develop such facilities and the necessary technology to ensure the safe long-term containment and isolation of these wastes. The Department has considered in this statement: development of conventionally mined deep geologic repositories for disposal of spent fuel from nuclear power reactors and/or radioactive fuel reprocessing wastes; balanced development of several alternative disposal methods; and no waste disposal action. This volume contains written public comments and hearing board responses and reports offered on the draft statement.

Not Available

1980-10-01T23:59:59.000Z

259

ANNUAL RADIOACTIVE WASTE TANK INSPECTION PROGRAM 2010  

SciTech Connect (OSTI)

Aqueous radioactive wastes from Savannah River Site (SRS) separations and vitrification processes are contained in large underground carbon steel tanks. Inspections made during 2010 to evaluate these vessels and other waste handling facilities along with evaluations based on data from previous inspections are the subject of this report. The 2010 inspection program revealed that the structural integrity and waste confinement capability of the Savannah River Site waste tanks were maintained. All inspections scheduled per SRR-LWE-2009-00138, HLW Tank Farm Inspection Plan for 2010, were completed. Ultrasonic measurements (UT) performed in 2010 met the requirements of C-ESG-00006, In-Service Inspection Program for High Level Waste Tanks, Rev. 3, and WSRC-TR-2002-00061, Rev.6. UT inspections were performed on Tanks 30, 31 and 32 and the findings are documented in SRNL-STI-2010-00533, Tank Inspection NDE Results for Fiscal Year 2010, Waste Tanks 30, 31 and 32. A total of 5824 photographs were made and 1087 visual and video inspections were performed during 2010. Ten new leaksites at Tank 5 were identified in 2010. The locations of these leaksites are documented in C-ESR-G-00003, SRS High Level Waste Tank Leaksite Information, Rev.5. Ten leaksites at Tank 5 were documented during tank wall/annulus cleaning activities. None of these new leaksites resulted in a release to the environment. The leaksites were documented during wall cleaning activities and the waste nodules associated with the leaksites were washed away. Previously documented leaksites were reactivated at Tank 12 during waste removal activities.

West, B.; Waltz, R.

2011-06-23T23:59:59.000Z

260

17 - Immobilisation of Radioactive Waste in Glass  

Science Journals Connector (OSTI)

Radionuclide immobilisation mechanisms are examined for vitreous wasteforms. Both borosilicate and phosphate glasses are described in detail, including the ability of cations to enter into the glass network structure. The role of various cations is considered, including boron, intermediates, and modifiers and elements difficult to immobilise. Selection rules for designing nuclear wasteform silicate glasses are outlined. Glass composite materials to immobilise glass-immiscible waste components are discussed. Both one- and two-stage vitrification technologies are described. An overview is given of the development of vitrification technology, including current operational data on radioactive waste vitrification facilities. Calcination processes are considered in detail, including typical properties of waste calcination products. Recent developments in vitrification are given, including descriptions of cold crucible induction-heated melters and in situ vitrification. Limitations caused by radionuclide volatility are examined. Acceptance criteria are given for vitreous wasteforms.

M.I. Ojovan; W.E. Lee

2014-01-01T23:59:59.000Z

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


261

Mission Plan for the Civilian Radioactive Waste Management Program |  

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

Mission Plan for the Civilian Radioactive Waste Management Program Mission Plan for the Civilian Radioactive Waste Management Program Mission Plan for the Civilian Radioactive Waste Management Program Summary In response to the the requirement of the Nuclear Waste Policy Act of 1982, the Office of Civilian Radioactive Waste Management in the Department of Energy (DOE) has prepared this Mission Plan for the Civilian Radioactive Waste Management Program. The Mission Plan is divided into two parts. Part I describes the overall goals, objectives, and strategy for the disposal of spent nuclear fuel and high-level waste. It explains that, to meet the directives of the Nuclear Waste Policy Act, the DOE intends to site, design, construct., and start operating a mined geologic repository by January 31, 1998. The Act specifies that the costs of these

262

A model approach to radioactive waste disposal at Sellafield  

E-Print Network [OSTI]

A model approach to radioactive waste disposal at Sellafield R. 5. Haszeldine* and C. Mc of the great environmentalproblems of our age is the safe disposal of radioactive waste for geological time periods. Britain is currently investigating a potential site for underground burial of waste, near

Haszeldine, Stuart

263

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

SciTech Connect (OSTI)

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

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

1994-03-01T23:59:59.000Z

264

Directions in low-level radioactive waste management: A brief history of commercial low-level radioactive waste disposal  

SciTech Connect (OSTI)

This report presents a history of commercial low-level radioactive waste disposal in the United States, with emphasis on the history of six commercially operated low-level radioactive waste disposal facilities. The report includes a brief description of important steps that have been taken during the last decade to ensure the safe disposal of low-level radioactive waste in the 1990s and beyond. These steps include the issuance of comprehensive State and Federal regulations governing the disposal of low-level radioactive waste, and the enactment of Federal laws making States responsible for the disposal of such waste generated within their borders.

Not Available

1994-08-01T23:59:59.000Z

265

Radioactive waste management and decommissioning of accelerator facilities  

Science Journals Connector (OSTI)

......Austria). EPAC. 2 International Atomic Energy Agency. Management of radioactive waste...Association, October 2008: Buenos Aires, Argentina. Argentina: SAR editor. 5 International Atomic Energy Agency. Classification of radioactive......

Luisa Ulrici; Matteo Magistris

2009-11-01T23:59:59.000Z

266

CIVILIAN RADIOACTIVE WASTE MANAGEMENT 2008 FEE ADEQUACY ASSESSMENT LETTER  

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

CIVILIAN RADIOACTIVE WASTE MANAGEMENT 2008 FEE ADEQUACY ASSESSMENT CIVILIAN RADIOACTIVE WASTE MANAGEMENT 2008 FEE ADEQUACY ASSESSMENT LETTER REPORT CIVILIAN RADIOACTIVE WASTE MANAGEMENT 2008 FEE ADEQUACY ASSESSMENT LETTER REPORT This Fiscal Year 2008 Civilian Radioactive Waste Management Fee Adequacy Letter Report presents an evaluation of the adequacy of the one mill per kilowatt-hour fee paid by commercial nuclear power generators for the permanent disposal of their spent nuclear fuel by the Government. This evaluation recommends no fee change. CIVILIAN RADIOACTIVE WASTE MANAGEMENT 2008 FEE ADEQUACY ASSESSMENT LETTER REPORT More Documents & Publications FY 2007 Fee Adequacy, Pub 2008 Fiscal Year 2007 Civilian Radioactive Waste Management Fee Adequacy Assessment Report January 16, 2013 Secretarial Determination of the Adequacy of the Nuclear

267

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

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

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

268

Shadow Review of the Advanced Mixed Waste Treatment Project Transuranic Storage Area Retrieval Enclosue Restrieval Restart DOE Readiness Assessment  

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

ID-2011-09-22 ID-2011-09-22 Site: Idaho Site - Idaho Cleanup Project Subject: Office of Enforcement and Oversight's Office of Safety and Emergency Management Evaluations Activity Report for the Shadow Review of the Advanced Mixed Waste Treatment Project (AMWTP) Transuranic Storage Area-Retrieval Enclosure (TSA-RE) Retrieval Restart Department of Energy Readiness Assessment Dates of Activity : 09/20/2011 - 09/22/2011 Report Preparer: Aleem Boatright Activity Description/Purpose: A review of nuclear safety implementation verification review (IVR) procedures and processes was conducted at the Idaho Site from September 12-22, 2011. The scope originally included shadowing of the Department of Energy (DOE) Idaho Operations Office (DOE-ID) Idaho Cleanup Project IVR for the Sodium Bearing Waste Treatment Project (SBWTP).

269

Shadow Review of the Advanced Mixed Waste Treatment Project Transuranic Storage Area Retrieval Enclosue Restrieval Restart DOE Readiness Assessment  

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

ID-2011-09-22 ID-2011-09-22 Site: Idaho Site - Idaho Cleanup Project Subject: Office of Enforcement and Oversight's Office of Safety and Emergency Management Evaluations Activity Report for the Shadow Review of the Advanced Mixed Waste Treatment Project (AMWTP) Transuranic Storage Area-Retrieval Enclosure (TSA-RE) Retrieval Restart Department of Energy Readiness Assessment Dates of Activity : 09/20/2011 - 09/22/2011 Report Preparer: Aleem Boatright Activity Description/Purpose: A review of nuclear safety implementation verification review (IVR) procedures and processes was conducted at the Idaho Site from September 12-22, 2011. The scope originally included shadowing of the Department of Energy (DOE) Idaho Operations Office (DOE-ID) Idaho Cleanup Project IVR for the Sodium Bearing Waste Treatment Project (SBWTP).

270

South Carolina Radioactive Waste Transportation and Disposal Act (South Carolina)  

Broader source: Energy.gov [DOE]

The Department of Health and Environmental Control is responsible for regulating the transportation of radioactive waste, with some exceptions, into or within the state for storage, disposal, or...

271

Appalachian States Low-Level Radioactive Waste Compact (Maryland)  

Broader source: Energy.gov [DOE]

This legislation authorizes Maryland's entrance into the Appalachian States Low-Level Radioactive Waste Compact, which seeks to promote interstate cooperation for the proper management and disposal...

272

RW - Radioactive Waste - Energy Conservation Plan  

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

Unconsciously Unconsciously Negative Behaviors Consciously Negative Behaviors Consciously Positive Behaviors Unconsciously Positive Behaviors Education Motivation Repetition Permanent Change Figure 1 - The Phases of Behavior Change Office of Civilian Radioactive Waste Management (OCRWM) Energy Conservation Plan Summary: Development and implementation of this plan is being treated as a project. This serves two purposes. First, it increases familiarity with the precepts of project management and DOE Order 413. Secondly, project management provides a great structure for organizing and implementing the activities that will facilitate energy savings through behavioral changes. A project structure also helps define how the effort will begin and what constitutes success at the

273

UOP, A Honewell Company CSTs Clean Radioactive Waste in  

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

UOP, A Honewell Company CSTs Clean Radioactive Waste in Fukushima and Worldwide Radiation waste cleanup was in the public eye this year following the huge earthquake and tsunami in...

274

Radioactive waste management and decommissioning of accelerator facilities  

Science Journals Connector (OSTI)

......the removed radioactive waste shall be treated and processed for either long-term storage or disposal. delayed...facility itself becomes a long-term storage that shall be...dismantling resources, waste storage space or development......

Luisa Ulrici; Matteo Magistris

2009-11-01T23:59:59.000Z

275

Radioactive Waste Management Complex performance assessment: Draft  

SciTech Connect (OSTI)

A radiological performance assessment of the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory was conducted to demonstrate compliance with appropriate radiological criteria of the US Department of Energy and the US Environmental Protection Agency for protection of the general public. The calculations involved modeling the transport of radionuclides from buried waste, to surface soil and subsurface media, and eventually to members of the general public via air, ground water, and food chain pathways. Projections of doses were made for both offsite receptors and individuals intruding onto the site after closure. In addition, uncertainty analyses were performed. Results of calculations made using nominal data indicate that the radiological doses will be below appropriate radiological criteria throughout operations and after closure of the facility. Recommendations were made for future performance assessment calculations.

Case, M.J.; Maheras, S.J.; McKenzie-Carter, M.A.; Sussman, M.E.; Voilleque, P.

1990-06-01T23:59:59.000Z

276

Standard guide for sampling radioactive tank waste  

E-Print Network [OSTI]

1.1 This guide addresses techniques used to obtain grab samples from tanks containing high-level radioactive waste created during the reprocessing of spent nuclear fuels. Guidance on selecting appropriate sampling devices for waste covered by the Resource Conservation and Recovery Act (RCRA) is also provided by the United States Environmental Protection Agency (EPA) (1). Vapor sampling of the head-space is not included in this guide because it does not significantly affect slurry retrieval, pipeline transport, plugging, or mixing. 1.2 The values stated in inch-pound units are to be regarded as standard. No other units of measurement are included in this standard. 1.3 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

American Society for Testing and Materials. Philadelphia

2011-01-01T23:59:59.000Z

277

Radioactive Material Declaration Form Exhibit to the Radioactive Waste Manual (RWM)  

E-Print Network [OSTI]

Radioactive Material Declaration Form Exhibit to the Radioactive Waste Manual (RWM) 12/5/2013 (form Declaration Form Exhibit to the Radioactive Waste Manual (RWM) 12/5/2013 (form date) SLAC-I-760-2A08Z-001 (RWM date) SLAC-I-760-2A08Z-001 (RWM number) Page 1 of 2 RADIOACTIVE MATERIAL DECLARATION FORM For RP use

Wechsler, Risa H.

278

Upgrading the Radioactive Waste Management Infrastructure in Azerbaijan  

SciTech Connect (OSTI)

Radionuclide uses in Azerbaijan are limited to peaceful applications in the industry, medicine, agriculture and research. The Baku Radioactive Waste Site (BRWS) 'IZOTOP' is the State agency for radioactive waste management and radioactive materials transport. The radioactive waste processing, storage and disposal facility is operated by IZOTOP since 1963 being significantly upgraded from 1998 to be brought into line with international requirements. The BRWS 'IZOTOP' is currently equipped with state-of-art devices and equipment contributing to the upgrade the radioactive waste management infrastructure in Azerbaijan in line with current internationally accepted practices. The IAEA supports Azerbaijan specialists in preparing syllabus and methodological materials for the Training Centre that is currently being organized on the base of the Azerbaijan BRWS 'IZOTOPE' for education of specialists in the area of safety management of radioactive waste: collection, sorting, processing, conditioning, storage and transportation. (authors)

Huseynov, A. [Baku Radioactive Waste Site IZOTOP, Baku (Azerbaijan); Batyukhnova, O. [State Unitary Enterprise Scientific and Industrial Association Radon, Moscow (Russian Federation); Ojovan, M. [Sheffield Univ., Immobilisation Science Lab. (United Kingdom); Rowat, J. [International Atomic Energy Agency, Dept. of Nuclear Safety and Security, Vienna (Austria)

2007-07-01T23:59:59.000Z

279

Savannah River Site Public and regulatory involvement in the transuranic (TRU) program and their effect on decisions to dispose of Pu-238 heat source tru waste onsite  

SciTech Connect (OSTI)

The key to successful public involvement at the Savannah River Site (SRS) has been and continues to be vigorous, up-front involvement of the public and state regulators with technical experts. The SRS Waste Management Program includes all forms of radioactive waste. All of the decisions associated with the management of these wastes are of interest to the public and successful program implementation would be impossible without including the public up-front in the program formulation. Serious problems can result if program decisions are made without public involvement, and if the public is informed after key decisions are made. This paper will describe the regulatory and public involvement program and their effects on the decisions concerning the disposal at the Savannah River Site (SRS) of heat source Pu-238 TRU waste. As can be imagined, a decision to dispose of TRU waste onsite versus shipment to the Waste Isolation Pilot Plan (WIPP) in New Mexico for disposal is of considerable interest to the stakeholders in South Carolina. The interaction between the stakeholders not only include the general public, but also the South Carolina Department of Health and Environmental Control (SCDHEC) and Region IV of the Environmental Protection Agency (EPA). The discussions, educational sessions, and negotiations include resolution of equity issues as well and moved forward to an understanding of the difficulties including risk management faced by the Ship-to- WIPP program. Once the program was better understood, the real negotiations concerning equity, safety, and risk to workers from handling Pu-238 waste could begin. This paper will also discuss the technical, regulatory, and public involvement aspects of disposal onsite that must be properly communicated if the program is to be successful. The Risk Based End State Vision Report for the Savannah River Site includes a variance that proposes on-site near surface disposal of waste from the program to produce Pu-238 heat sources for deep space probes. On-site disposal would greatly reduce the risk to workers by eliminating the need to repackage the waste in order to characterize it and ship it to the Waste Isolation Pilot Plant. Significant cost savings can also be realized. A performance assessment was completed to demonstrate that on-site disposal of this waste can be done while meeting the Department of Energy and EPA performance objectives for disposal of TRU waste in a non-WIPP location such as the SRS. This analysis provides a means of demonstrating the technical basis for this alternative to management, stakeholders and regulators. The technical analysis is required to demonstrate that the performance objectives contained in 40 CFR 191, Environmental Protection Standards for the Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes will be met over a 10,000 year period. This paper will describe the successful results of this technical, regulatory, and public involvement program, explore why and how the accomplishments occurred, and describe the future challenges along with the road map for the future. In doing this, the TRU Ship-to-WIPP program must be described to give the readers an understanding of the technical complexities that must be communicated successfully to achieve constructive stakeholder participation and regulatory approval. (authors)

Bert Crapse, H.M. [U. S. Department of Energy, Washington (United States); Sonny, W.T. [Goldston Washington Savannah River Company (United States)

2007-07-01T23:59:59.000Z

280

Radcalc: An Analytical Tool for Shippers of Radioactive Material and Waste  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE) ships radioactive materials in support of its research and development, environmental restoration, and national defense activities. The Radcalc software program assists personnel working on behalf of DOE in packaging and transportation determinations (e.g., isotopic decay, decay heat, regulatory classification, and gas generation) for shipment of radioactive materials and waste. Radcalc performs: - The U.S. Department of Transportation determinations and classifications (i.e., activity concentration for exempt material Type A or B, effective A1/A2, limited quantity, low specific activity, highway route controlled quantity, fissile quantity, fissile excepted, reportable quantity, list of isotopes required on shipping papers) - DOE calculations (i.e., transuranic waste, Pu-239 equivalent curies, fissile-gram equivalents) - The U.S. Nuclear Regulatory Commission packaging category (i.e., Category I, II, or III) - Dose-equivalent curie calculations - Radioactive decay calculations using a novel decay methodology and a decay data library of 1,867 isotopes typical of the range of materials encountered in DOE laboratory environments - Hydrogen and helium gas calculations - Pressure calculations. Radcalc is a validated and cost-effective tool to provide consistency, accuracy, reproducibility, timeliness, quality, compliance, and appropriate documentation to shippers of radioactive materials and waste at DOE facilities nationwide. Hundreds of shippers and engineers throughout the DOE Complex routinely use this software to automate various determinations and to validate compliance with the regulations. The effective use of software by DOE sites contributes toward minimizing risk involved in radioactive waste shipments and assuring the safety of workers and the public. (authors)

Kapoor, A.K. [U.S. Department of Energy, Office of Transportation, Washington, DC (United States); Stuhl, L.A. [EnergySolutions Federal Services, Inc., Richland, WA (United States)

2008-07-01T23:59:59.000Z

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


281

Composite Analysis for the Area 5 Radioactive Waste Management Site at the Nevada Test Site, Nye County, Nevada  

SciTech Connect (OSTI)

This report summarizes the results of a Composite Analysis (CA) for the Area 5 Radioactive Waste Management Site (RWMS). The Area 5 RWMS is a US Department of Energy (DOE)-operated low-level radioactive waste (LLW) management site located in northern Frenchman Flat on the Nevada Test Site (NTS). The Area 5 RWMS has disposed of low-level radioactive waste in shallow unlined pits and trenches since 1960. Transuranic waste (TRU) and high-specific activity waste was disposed in Greater Confinement Disposal (GCD) boreholes from 1983 to 1989. The purpose of this CA is to determine if continuing operation of the Area 5 RWMS poses an acceptable or unacceptable risk to the public considering the total waste inventory and all other interacting sources of radioactive material in the vicinity. Continuing operation of the Area 5 RWMS will be considered acceptable if the total effective dose equivalent (TEDE) is less than 100 mrem in a year. If the TEDE exceeds 30 mrem in a year, a cost-benefit options analysis must be performed to determine if cost-effective management options exist to reduce the dose further. If the TEDE is found to be less than 30 mrem in a year, an analysis may be performed if warranted to determine if doses are as low as reasonably achievable (ALARA).

V. Yucel

2001-09-01T23:59:59.000Z

282

Directions in low-level radioactive waste management: A brief history of commercial low-level radioactive waste disposal  

SciTech Connect (OSTI)

This report presents a history of commercial low-level radioactive waste management in the United States, with emphasis on the history of six commercially operated low-level radioactive waste disposal facilities. The report includes a brief description of important steps that have been taken during the 1980s to ensure the safe disposal of low-level waste in the 1990s and beyond. These steps include the issuance of Title 10 Code of Federal Regulations Part 61, Licensing Requirements for the Land Disposal of Radioactive Waste, the Low-Level Radioactive Waste Policy Act of 1980, the Low-Level Radioactive Waste Policy Amendments Act of 1985, and steps taken by states and regional compacts to establish additional disposal sites. 42 refs., 13 figs., 1 tab.

Not Available

1990-10-01T23:59:59.000Z

283

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

SciTech Connect (OSTI)

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

GREENWLL, R.D.

2005-01-20T23:59:59.000Z

284

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

SciTech Connect (OSTI)

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

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

2007-07-01T23:59:59.000Z

285

Atlantic Interstate Low-Level Radioactive Waste Management Compact (South  

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

Atlantic Interstate Low-Level Radioactive Waste Management Compact Atlantic Interstate Low-Level Radioactive Waste Management Compact (South Carolina) Atlantic Interstate Low-Level Radioactive Waste Management Compact (South Carolina) < Back Eligibility Utility Commercial Agricultural Investor-Owned Utility Industrial Construction Municipal/Public Utility Local Government Installer/Contractor Rural Electric Cooperative Tribal Government Program Info Start Date 1986 State South Carolina Program Type Environmental Regulations Siting and Permitting Provider Atlantic Compact Commission The Atlantic (Northeast) Interstate Low-Level Radioactive Waste Management Compact is a cooperative effort to plan, regulate, and administer the disposal of low-level radioactive waste in the region. The states of Connecticut, New Jersey, and South Carolina are party to this compact

286

1 INTRODUCTION In order to demonstrate the feasibility of a radioactive waste repository in claystone  

E-Print Network [OSTI]

1 INTRODUCTION In order to demonstrate the feasibility of a radioactive waste repository in claystone formations, the French national radioactive waste management agency (ANDRA) started in 2000

Boyer, Edmond

287

Introduction to DOE Order 435.1 Low Level Radioactive Waste Disposal...  

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

Introduction to DOE Order 435.1 Low Level Radioactive Waste Disposal Requirements Introduction to DOE Order 435.1 Low Level Radioactive Waste Disposal Requirements Christine...

288

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

SciTech Connect (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

289

2 - Radioactive waste (RAW) categories, characterization and processing route selection  

Science Journals Connector (OSTI)

Abstract: The principal approach to radioactive waste management is to transform as generated waste to a waste package suitable for safe long-term storage or ultimate disposal. A waste characterization system allows an assessment of the potential risks connected with waste handling and disposal and also allows the waste to be classified into groups (streams) according to their properties and projected processing routes. A properly selected waste classification system also enables the selection of the proper processing technology for each class of waste, tailored to waste volume, properties and available technologies in each country or waste processing organization. Long-term safe disposal of processed waste is a basic requirement of all waste classification and waste processing schemes discussed in this chapter.

R. Burcl

2013-01-01T23:59:59.000Z

290

Application of microwave solidification technology to radioactive waste  

SciTech Connect (OSTI)

The EPA has declared vitrification to be the Best Available Demonstrated Technology (BDAT) for High Level Radioactive Waste (40 CFR 268.42). Vitrification has been chosen as the method of choice for treating a number of radioactive residues and wastes in the DOE complex. Vitrification offers advantages of waste volume reduction, the ability to handle changing waste forms, and a stable, nonleachable final waste form. Microwave heating is a superior method for vitrification of radioactive wastes. Advantages of microwave heating include: (1) direct waste heating, eliminates need for electrodes, refractories and other consumables; (2) ``in-can`` processing allows for treatment of the material in its final container, (3) a mechanically simple system where the microwaves are generated away from the treatment area and transmitted to the treatment applicator by a wave guide, thus minimizing worker exposure to radiation; (4) easier equipment maintenance; and (5) a high degree of public acceptance.

Harris, M.; Sprenger, G.; Roushey, B.; Fenner, G.; Nieweg, R.

1995-09-28T23:59:59.000Z

291

EIS-0046: Management of Commercially Generated Radioactive Waste, Washington, D.C.  

Broader source: Energy.gov [DOE]

This statement analyzes the significant environmental impacts that could occur if various technologies for management and disposal of high-level and transuranic wastes from commercial nuclear power reactors were to be developed and implemented.

292

Low-Level Radioactive Waste Disposal Regional Facility Act (Pennsylvania) |  

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

Low-Level Radioactive Waste Disposal Regional Facility Act Low-Level Radioactive Waste Disposal Regional Facility Act (Pennsylvania) Low-Level Radioactive Waste Disposal Regional Facility Act (Pennsylvania) < Back Eligibility Utility Investor-Owned Utility State/Provincial Govt Industrial Construction Municipal/Public Utility Local Government Program Info State Pennsylvania Program Type Environmental Regulations Fees This act establishes a low-level radioactive waste disposal regional facility siting fund that requires nuclear power reactor constructors and operators to pay to the Department of Environmental Resources funds to be utilized for disposal facilities. This act ensures that nuclear facilities and the Department comply with the Low-Level Radioactive Disposal Act. The regional facility siting fund is used for reimbursement of expenses

293

Radioactivity, Radiation, and the Chemistry of Nuclear Waste  

Science Journals Connector (OSTI)

Radioactivity, Radiation, and the Chemistry of Nuclear Waste ... A chemistry course for nonmajors, which centers on the chemistry of nuclear waste, has as a prerequisite at least two semesters of general chemistry. ... The final section of the course is devoted to the treatment of nuclear waste by vitrification and applications based on nuclear or radiation chemistry. ...

Nick Zevos

2002-06-01T23:59:59.000Z

294

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

SciTech Connect (OSTI)

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

Birk, S.M.

1997-10-01T23:59:59.000Z

295

Portsmouth Site Delivers First Radioactive Waste Shipment to Disposal  

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

Delivers First Radioactive Waste Shipment to Delivers First Radioactive Waste Shipment to Disposal Facility in Texas Portsmouth Site Delivers First Radioactive Waste Shipment to Disposal Facility in Texas August 27, 2013 - 12:00pm Addthis Waste management and transportation personnel worked late to complete the first shipment to WCS. Through a contract with DOE, WCS will treat and accept potentially hazardous waste that has been at the Portsmouth site for decades. Pictured (from left) are Scott Fraser, Joe Hawes, Craig Herrmann, Jim Book, John Lee, John Perry, Josh Knipp, Melissa Dunsieth, Randy Barr, Rick Williams, Janet Harris, Maureen Fischels, Cecil McCoy, Trent Eckert, Anthony Howard and Chris Ashley. Waste management and transportation personnel worked late to complete the first shipment to WCS. Through a contract with DOE, WCS will treat and

296

Portsmouth Site Delivers First Radioactive Waste Shipment to Disposal  

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

Portsmouth Site Delivers First Radioactive Waste Shipment to Portsmouth Site Delivers First Radioactive Waste Shipment to Disposal Facility in Texas Portsmouth Site Delivers First Radioactive Waste Shipment to Disposal Facility in Texas August 27, 2013 - 12:00pm Addthis Waste management and transportation personnel worked late to complete the first shipment to WCS. Through a contract with DOE, WCS will treat and accept potentially hazardous waste that has been at the Portsmouth site for decades. Pictured (from left) are Scott Fraser, Joe Hawes, Craig Herrmann, Jim Book, John Lee, John Perry, Josh Knipp, Melissa Dunsieth, Randy Barr, Rick Williams, Janet Harris, Maureen Fischels, Cecil McCoy, Trent Eckert, Anthony Howard and Chris Ashley. Waste management and transportation personnel worked late to complete the

297

Record of Decision on Treating Transuranic (TRU)/Alpha Low-Level Waste at the Oak Ridge National Laboratory (DOE/EIS-0305) (8/9/00)  

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

83 83 Federal Register / Vol. 65, No. 154 / Wednesday, August 9, 2000 / Notices 1 TRU waste is waste containing alpha-emitting radionuclides with an atomic number greater than 92 and half-lives greater than 20 years, at concentrations greater than 100 nanocuries per gram of waste. 2 Alpha low-level waste is low-level waste that contains alpha-emitting isotopes. 3 Mixed waste contains radioactive waste regulated under the Atomic Energy Act of 1954, as amended, and a hazardous component subject to RCRA regulation. 4 Low-level waste is any radioactive waste that is not classified as high-level waste, spent nuclear fuel, TRU waste, byproduct material, or mixed waste. 5 Remote-handled TRU/alpha low-level waste contains alpha-, beta-, and gamma-emitting isotopes with a surface dose rate greater than 200 millirem

298

Journey to the Nevada Test Site Radioactive Waste Management Complex  

ScienceCinema (OSTI)

Journey to the Nevada Test Site Radioactive Waste Management Complex begins with a global to regional perspective regarding the location of low-level and mixed low-level waste disposal at the Nevada Test Site. For decades, the Nevada National Security Site (NNSS) has served as a vital disposal resource in the nation-wide cleanup of former nuclear research and testing facilities. State-of-the-art waste management sites at the NNSS offer a safe, permanent disposal option for U.S. Department of Energy/U.S. Department of Defense facilities generating cleanup-related radioactive waste.

None

2014-10-28T23:59:59.000Z

299

Enhancements to System for Tracking Radioactive Waste Shipments Benefit  

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

Enhancements to System for Tracking Radioactive Waste Shipments Enhancements to System for Tracking Radioactive Waste Shipments Benefit Multiple Users Enhancements to System for Tracking Radioactive Waste Shipments Benefit Multiple Users January 30, 2013 - 12:00pm Addthis Transportation Tracking and Communication System users can now track shipments of radioactive materials and access transportation information on mobile devices. Transportation Tracking and Communication System users can now track shipments of radioactive materials and access transportation information on mobile devices. CARLSBAD, N.M. - EM's Carlsbad Field Office (CBFO) recently deployed a new version of the Transportation Tracking and Communication System (TRANSCOM) that is compatible with mobile devices, including smartphones. The recent enhancement, TRANSCOM version 3.0, improves the user interface

300

Preparation of the First Shipment of Transuranic Waste by the Los Alamos National Laboratory: A Rest Stop on the Road to WIPP  

SciTech Connect (OSTI)

The Los Alamos National Laboratory (LANL) achieved a national milestone on the road to shipping transuranic (TRU) waste to the Waste Isolation Pilot Plant (WIPP) when it received certification authority on September 12, 1997. Since that time, LANL has been characterizing a non-mixed TRU waste stream and preparing shipments of this TRU waste for disposal in the WIPP. The paper describes the TRU waste identified as waste stream TA-55-43 Lot No. 01 from LANL Technical Area-55 and the process used to determine that it does not contain hazardous waste regulated by the Resource Conservation Recovery Act (RCRA) or the New Mexico Hazardous Waste Act (HWA). The non-mixed determination is based on the acceptable knowledge (AK) characterization process, which clearly shows that the waste does not exhibit any RCRA characteristics nor meet any RCRA listing descriptions. LANL has certified TRU waste from waste stream TA-55-43 Lot No. 01 and is prepared to certify additional quantities of TRU waste horn other non-mixed TRU waste streams. Assembly and preparation of AK on the processes that generated TRU waste is recognized as a necessary part of the process for having waste ready for shipment to the WIPP.

Allen, G.; Barr, A.; Betts, S.E.; Farr, J.; Foxx, J.; Gavett, M.A.; Janecky, D.R.; Kosiewicz, S.T.; Liebman, C.P.; Montoya, A.; Poths, H.; Rogers, P.S.Z.; Taggart, D.P.; Triay, I.R.; Vigil, G.I.; Vigil, J.J.; Wander, S.G.; Yeamans, D.

1999-02-01T23:59:59.000Z

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


301

Northwest Interstate Compact on Low-Level Radioactive Waste Management  

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

Northwest Interstate Compact on Low-Level Radioactive Waste Northwest Interstate Compact on Low-Level Radioactive Waste Management (Multiple States) Northwest Interstate Compact on Low-Level Radioactive Waste Management (Multiple States) < Back Eligibility Utility Fed. Government Commercial Investor-Owned Utility State/Provincial Govt Industrial Construction Municipal/Public Utility Local Government Rural Electric Cooperative Tribal Government Institutional Nonprofit Program Info Start Date 1981 State Alaska Program Type Siting and Permitting Provider Northwest Interstate Compact The Northwest Interstate Compact on Low-Level Radioactive Waste Management, enacted in 1981, was ratified by Congress in 1985. The Compact is a cooperative effort of the party states to protect their citizens, and maintain and enhance economic viability, while sharing the responsibilities

302

The High-Level Radioactive Waste Act (Manitoba, Canada)  

Broader source: Energy.gov [DOE]

Manitoba bars the storage of high-level radioactive wastes from spent nuclear fuel, not intended for research purposes, that was produced at a nuclear facility or in a nuclear reactor outside the...

303

Radioactive Waste Management in Non-Nuclear Countries - 13070  

SciTech Connect (OSTI)

This paper challenges internationally accepted concepts of dissemination of responsibilities between all stakeholders involved in national radioactive waste management infrastructure in the countries without nuclear power program. Mainly it concerns countries classified as class A and potentially B countries according to International Atomic Energy Agency. It will be shown that in such countries long term sustainability of national radioactive waste management infrastructure is very sensitive issue that can be addressed by involving regulatory body in more active way in the infrastructure. In that way countries can mitigate possible consequences on the very sensitive open market of radioactive waste management services, comprised mainly of radioactive waste generators, operators of end-life management facilities and regulatory body. (authors)

Kubelka, Dragan; Trifunovic, Dejan [SORNS, Frankopanska 11, HR-10000 Zagreb (Croatia)] [SORNS, Frankopanska 11, HR-10000 Zagreb (Croatia)

2013-07-01T23:59:59.000Z

304

CRAD, Radioactive Waste Management - June 22, 2009 | Department...  

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

22, 2009 June 22, 2009 Radioactive Waste Management, Inspection Criteria, Approach, and Lines of Inquiry (HSS CRAD 64-33, Rev. 0) This Criteria Review and Approach Document (HSS...

305

New Extraction Technologies for Management of Radioactive Wastes  

Science Journals Connector (OSTI)

Different variants reprocessing of high-level radioactive wastes are considered. The extraction of cesium, strontium, rare earth elements and actinides by various extractants is analyzed. Advantages and disadv...

V. V. Babain; A. Yu. Shadrin

1999-01-01T23:59:59.000Z

306

UNITED STATES DEPARTMENT OF ENERGY OFFICE OF CIVILIAN RADIOACTIVE WASTE  

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

UNITED STATES DEPARTMENT OF ENERGY OFFICE OF CIVILIAN RADIOACTIVE UNITED STATES DEPARTMENT OF ENERGY OFFICE OF CIVILIAN RADIOACTIVE WASTE MANAGEMENT Annual Financial Report Years Ended September 30, 2009 and 2008 UNITED STATES DEPARTMENT OF ENERGY OFFICE OF CIVILIAN RADIOACTIVE WASTE MANAGEMENT Annual Financial Report Years Ended September 30, 2009 and 2008 As required by Section 304(c) of the Nuclear Waste Policy Act (NWPA) of 1982, as amended, Public Law 97-425, the following document is the United States Department of Energy's (DOE) Office of Civilian Radioactive Waste Management's Annual Financial Report for the years ended September 30, 2009 and 2008 as required by Section 302(c)(l) ofNWPA. The information in this report is current only as of September 30, 2009, and does not reflect actions or changes that have occurred since then.

307

Coordination Meeting with National Nuclear Security Administration Los Alamos Field Office Safety Basis Review Team Leader for Transuranic Waste Facility Preiminary Documented Safety Analysis Report  

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

HIAR-LANL-2013-04-08 HIAR-LANL-2013-04-08 Site: Los Alamos National Laboratory Subject: Office of Enforcement and Oversight's Office of Safety and Emergency Management Evaluations Activity Report for Coordination Meeting with National Nuclear Security Administration Los Alamos Field Office Safety Basis Review Team Leader for Transuranic Waste Facility Preliminary Documented Safety Analysis Report Dates of Activity : 04/08/13 Report Preparer: James O. Low Activity Description/Purpose: The Office of Health, Safety and Security (HSS) staff visited the Los Alamos National Laboratory (LANL) to coordinate with the National Nuclear Security Administration (NNSA) Los Alamos Field Office (NA-00-LA) Safety Basis Review Team (SBRT) Leader for review of the revised preliminary documented safety analysis (PDSA) for the Transuranic Waste

308

Coordination Meeting with National Nuclear Security Administration Los Alamos Field Office Safety Basis Review Team Leader for Transuranic Waste Facility Preiminary Documented Safety Analysis Report  

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

HIAR-LANL-2013-04-08 HIAR-LANL-2013-04-08 Site: Los Alamos National Laboratory Subject: Office of Enforcement and Oversight's Office of Safety and Emergency Management Evaluations Activity Report for Coordination Meeting with National Nuclear Security Administration Los Alamos Field Office Safety Basis Review Team Leader for Transuranic Waste Facility Preliminary Documented Safety Analysis Report Dates of Activity : 04/08/13 Report Preparer: James O. Low Activity Description/Purpose: The Office of Health, Safety and Security (HSS) staff visited the Los Alamos National Laboratory (LANL) to coordinate with the National Nuclear Security Administration (NNSA) Los Alamos Field Office (NA-00-LA) Safety Basis Review Team (SBRT) Leader for review of the revised preliminary documented safety analysis (PDSA) for the Transuranic Waste

309

Transuranic Waste Retrieval from the 218-W-4B and 218-W-4C Low-Level Burial Grounds, Hanford Site, Richland, Washington  

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

05 05 Environmental Assessment Transuranic Waste Retrieval from the 218-W-4B and 218-W-4C Low-Level Burial Grounds, Hanford Site, Richland, Washington U.S. Department of Energy Washington, D.C. March 2002 DOE/EA-1405 U.S. Department of Energy Contents Environmental Assessment C-1 March 2002 CONTENTS PREFACE ....................................................................................................................................P-1 GLOSSARY ................................................................................................................................ G-1 SCIENTIFIC NOTATION CONVERSION CHART .................................................................... G-2 METRIC CONVERSION CHART...............................................................................................

310

Independent Oversight Review of Management of Safety Systems at the Oak Ridge Transuranic Waste Processing Center and Associated Feedback and Improvement Processes, September 2013  

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

Management of Safety Systems at the Oak Ridge Transuranic Waste Processing Center and Associated Feedback and Improvement Processes May 2011 February 2013 September 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 Background ............................................................................................................................................. 1 3.0 Scope....................................................................................................................................................... 2

311

Independent Oversight Review of Management of Safety Systems at the Oak Ridge Transuranic Waste Processing Center and Associated Feedback and Improvement Processes, September 2013  

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

Management of Safety Systems at the Oak Ridge Transuranic Waste Processing Center and Associated Feedback and Improvement Processes May 2011 February 2013 September 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 Background ............................................................................................................................................. 1 3.0 Scope....................................................................................................................................................... 2

312

Neutron and gamma-ray nondestructive examination of contact-handled transuranic waste at the ORNL TRU Waste Drum Assay Facility  

SciTech Connect (OSTI)

A nondestructive assay system, which includes the Neutron Assay System (NAS) and the Segmented Gamma Scanner (SGS), for the quantification of contact-handled (<200 mrem/h total radiation dose rate at contact with container) transuranic elements (CH-TRU) in bulk solid waste contained in 208-L and 114-L drums has been in operation at the Oak Ridge National Laboratory since April 1982. The NAS has been developed and demonstrated by Los Alamos National Laboratory (LANL) and the Oak Ridge National Laboratory (ORNL) for use by most US Department of Energy Defense Plant (DOE-DP) sites. More research and development is required, however, before the NAS can provide complete assay results for other than routine defense waste. To date, 525 ORNL waste drums have been assayed, with varying degrees of success. The isotopic complexity of the ORNL waste creates a correspondingly complex assay problem. The NAS and SGS assay data are presented and discussed. Neutron matrix effects, the destructive examination facility, and enriched uranium fuel-element assays are also discussed.

Schultz, F.J.; Coffey, D.E.; Norris, L.B.; Haff, K.W.

1985-03-01T23:59:59.000Z

313

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

SciTech Connect (OSTI)

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

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

1997-09-01T23:59:59.000Z

314

Characterisation of radioactive waste products associated with plant decommissioning  

Science Journals Connector (OSTI)

......the results integrated over selected...deposited on the system and equipment...operating plant data and...residual waste activities...coolant pH controls. Shut-down...Surface treatments (e.g...Component-system decontamination...varies from plant to plant...radioactive waste due to activation...internals and control rod drive......

J. Sejvar; A. H. Fero; C. Gil; R. J. Hagler; J. L. Santiago; A. Holgado; R. Swenson

2005-12-20T23:59:59.000Z

315

Molten salt extraction of transuranic and reactive fission products from used uranium oxide fuel  

DOE Patents [OSTI]

Used uranium oxide fuel is detoxified by extracting transuranic and reactive fission products into molten salt. By contacting declad and crushed used uranium oxide fuel with a molten halide salt containing a minor fraction of the respective uranium trihalide, transuranic and reactive fission products partition from the fuel to the molten salt phase, while uranium oxide and non-reactive, or noble metal, fission products remain in an insoluble solid phase. The salt is then separated from the fuel via draining and distillation. By this method, the bulk of the decay heat, fission poisoning capacity, and radiotoxicity are removed from the used fuel. The remaining radioactivity from the noble metal fission products in the detoxified fuel is primarily limited to soft beta emitters. The extracted transuranic and reactive fission products are amenable to existing technologies for group uranium/transuranic product recovery and fission product immobilization in engineered waste forms.

Herrmann, Steven Douglas

2014-05-27T23:59:59.000Z

316

System for chemically digesting low level radioactive, solid waste material  

DOE Patents [OSTI]

An improved method and system for chemically digesting low level radioactive, solid waste material having a high through-put. The solid waste material is added to an annular vessel (10) substantially filled with concentrated sulfuric acid. Concentrated nitric acid or nitrogen dioxide is added to the sulfuric acid within the annular vessel while the sulfuric acid is reacting with the solid waste. The solid waste is mixed within the sulfuric acid so that the solid waste is substantilly fully immersed during the reaction. The off gas from the reaction and the products slurry residue is removed from the vessel during the reaction.

Cowan, Richard G. (Kennewick, WA); Blasewitz, Albert G. (Richland, WA)

1982-01-01T23:59:59.000Z

317

Synergistic Inhibitors for Dilute High-Level Radioactive Waste  

SciTech Connect (OSTI)

Cyclic potentiodynamic polarization scans were conducted to determine the effectiveness of various combinations of anodic inhibitors in the prevention of pitting in carbon steel exposed to dilute radioactive waste. Chromate, molybdate, and phosphate were investigated as replacements for nitrite, whose effective concentrations are incompatible with the waste vitrification process. The polarization scans were performed in non-radioactive waste simulants. Their results showed that acceptable combinations of phosphate with chromate and phosphate with molybdate effectively prevented pitting corrosion. Chromate with molybdate could not replace nitrite.

Wiersma, B.J.; Zapp, P.E.

1995-11-01T23:59:59.000Z

318

Removal of radioactive and other hazardous material from fluid waste  

DOE Patents [OSTI]

Hollow glass microspheres obtained from fly ash (cenospheres) are impregnated with extractants/ion-exchangers and used to remove hazardous material from fluid waste. In a preferred embodiment the microsphere material is loaded with ammonium molybdophosphonate (AMP) and used to remove radioactive ions, such as cesium-137, from acidic liquid wastes. In another preferred embodiment, the microsphere material is loaded with octyl(phenyl)-N-N-diisobutyl-carbamoylmethylphosphine oxide (CMPO) and used to remove americium and plutonium from acidic liquid wastes.

Tranter, Troy J. (Idaho Falls, ID); Knecht, Dieter A. (Idaho Falls, ID); Todd, Terry A. (Aberdeen, ID); Burchfield, Larry A. (W. Richland, WA); Anshits, Alexander G. (Krasnoyarsk, RU); Vereshchagina, Tatiana (Krasnoyarsk, RU); Tretyakov, Alexander A. (Zheleznogorsk, RU); Aloy, Albert S. (St. Petersburg, RU); Sapozhnikova, Natalia V. (St. Petersburg, RU)

2006-10-03T23:59:59.000Z

319

Commercial low-level radioactive waste disposal in the US  

SciTech Connect (OSTI)

Why are 11 states attempting to develop new low-level radioactive waste disposal facilities? Why is only on disposal facility accepting waste nationally? What is the future of waste disposal? These questions are representative of those being asked throughout the country. This paper attempts to answer these questions in terms of where we are, how we got there, and where we might be going.

Smith, P.

1995-10-01T23:59:59.000Z

320

Low-level radioactive waste disposal facility closure  

SciTech Connect (OSTI)

Part I of this report describes and evaluates potential impacts associated with changes in environmental conditions on a low-level radioactive waste disposal site over a long period of time. Ecological processes are discussed and baselines are established consistent with their potential for causing a significant impact to low-level radioactive waste facility. A variety of factors that might disrupt or act on long-term predictions are evaluated including biological, chemical, and physical phenomena of both natural and anthropogenic origin. These factors are then applied to six existing, yet very different, low-level radioactive waste sites. A summary and recommendations for future site characterization and monitoring activities is given for application to potential and existing sites. Part II of this report contains guidance on the design and implementation of a performance monitoring program for low-level radioactive waste disposal facilities. A monitoring programs is described that will assess whether engineered barriers surrounding the waste are effectively isolating the waste and will continue to isolate the waste by remaining structurally stable. Monitoring techniques and instruments are discussed relative to their ability to measure (a) parameters directly related to water movement though engineered barriers, (b) parameters directly related to the structural stability of engineered barriers, and (c) parameters that characterize external or internal conditions that may cause physical changes leading to enhanced water movement or compromises in stability. Data interpretation leading to decisions concerning facility closure is discussed. 120 refs., 12 figs., 17 tabs.

White, G.J.; Ferns, T.W.; Otis, M.D.; Marts, S.T.; DeHaan, M.S.; Schwaller, R.G.; White, G.J. (EG and G Idaho, Inc., Idaho Falls, ID (USA))

1990-11-01T23:59:59.000Z

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


321

Geologic processes in the RWMC area, Idaho National Engineering Laboratory: Implications for long term stability and soil erosion at the radioactive waste management complex  

SciTech Connect (OSTI)

The Radioactive Waste Management Complex (RWMC) is the disposal and storage facility for low-level radioactive waste at the Idaho National Engineering Laboratory (INEL). Transuranic waste and mixed wastes were also disposed at the RWMC until 1970. It is located in the southwestern part of the INEL about 80 km west of Idaho Falls, Idaho. The INEL occupies a portion of the Eastern Snake River Plain (ESRP), a low-relief, basalt, and sediment-floored basin within the northern Rocky Mountains and northeastern Basin and Range Province. It is a cool and semiarid, sagebrush steppe desert characterized by irregular, rolling terrain. The RWMC began disposal of INEL-generated wastes in 1952, and since 1954, wastes have been accepted from other Federal facilities. Much of the waste is buried in shallow trenches, pits, and soil vaults. Until about 1970, trenches and pits were excavated to the basalt surface, leaving no sediments between the waste and the top of the basalt. Since 1970, a layer of sediment (about 1 m) has been left between the waste and the basalt. The United States Department of Energy (DOE) has developed regulations specific to radioactive-waste disposal, including environmental standards and performance objectives. The regulation applicable to all DOE facilities is DOE Order 5820.2A (Radioactive Waste Management). An important consideration for the performance assessment of the RWMC is the long-term geomorphic stability of the site. Several investigators have identified geologic processes and events that could disrupt a radioactive waste disposal facility. Examples of these {open_quotes}geomorphic hazards{close_quotes} include changes in stream discharge, sediment load, and base level, which may result from climate change, tectonic processes, or magmatic processes. In the performance assessment, these hazards are incorporated into scenarios that may affect the future performance of the RWMC.

Hackett, W.R.; Tullis, J.A.; Smith, R.P. [and others

1995-09-01T23:59:59.000Z

322

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

SciTech Connect (OSTI)

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

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

2000-05-19T23:59:59.000Z

323

Functions and requirements document for interim store solidified high-level and transuranic waste  

SciTech Connect (OSTI)

The functions, requirements, interfaces, and architectures contained within the Functions and Requirements (F{ampersand}R) Document are based on the information currently contained within the TWRS Functions and Requirements database. The database also documents the set of technically defensible functions and requirements associated with the solidified waste interim storage mission.The F{ampersand}R Document provides a snapshot in time of the technical baseline for the project. The F{ampersand}R document is the product of functional analysis, requirements allocation and architectural structure definition. The technical baseline described in this document is traceable to the TWRS function 4.2.4.1, Interim Store Solidified Waste, and its related requirements, architecture, and interfaces.

Smith-Fewell, M.A., Westinghouse Hanford

1996-05-17T23:59:59.000Z

324

Method for aqueous radioactive waste treatment  

DOE Patents [OSTI]

Plutonium, strontium, and cesium found in aqueous waste solutions resulting from nuclear fuel processing are removed by contacting the waste solutions with synthetic zeolite incorporating up to about 5 wt % titanium as sodium titanate in an ion exchange system. More than 99.9% of the plutonium, strontium, and cesium are removed from the waste solutions.

Bray, Lane A. (Richland, WA); Burger, Leland L. (Richland, WA)

1994-01-01T23:59:59.000Z

325

Civilian Radioactive Waste Management System Requirements Document  

SciTech Connect (OSTI)

The CRD addresses the requirements of Department of Energy (DOE) Order 413.3-Change 1, ''Program and Project Management for the Acquisition of Capital Assets'', by providing the Secretarial Acquisition Executive (Level 0) scope baseline and the Program-level (Level 1) technical baseline. The Secretarial Acquisition Executive approves the Office of Civilian Radioactive Waste Management's (OCRWM) critical decisions and changes against the Level 0 baseline; and in turn, the OCRWM Director approves all changes against the Level 1 baseline. This baseline establishes the top-level technical scope of the CRMWS and its three system elements, as described in section 1.3.2. The organizations responsible for design, development, and operation of system elements described in this document must therefore prepare subordinate project-level documents that are consistent with the CRD. Changes to requirements will be managed in accordance with established change and configuration control procedures. The CRD establishes requirements for the design, development, and operation of the CRWMS. It specifically addresses the top-level governing laws and regulations (e.g., ''Nuclear Waste Policy Act'' (NWPA), 10 Code of Federal Regulations (CFR) Part 63, 10 CFR Part 71, etc.) along with specific policy, performance requirements, interface requirements, and system architecture. The CRD shall be used as a vehicle to incorporate specific changes in technical scope or performance requirements that may have significant program implications. Such may include changes to the program mission, changes to operational capability, and high visibility stakeholder issues. The CRD uses a systems approach to: (1) identify key functions that the CRWMS must perform, (2) allocate top-level requirements derived from statutory, regulatory, and programmatic sources, and (3) define the basic elements of the system architecture and operational concept. Project-level documents address CRD requirements by further defining system element functions, decomposing requirements into significantly greater detail, and developing designs of system components, facilities, and equipment. The CRD addresses the identification and control of functional, physical, and operational boundaries between and within CRWMS elements. The CRD establishes requirements regarding key interfaces between the CRWMS and elements external to the CRWMS. Project elements define interfaces between CRWMS program elements. The Program has developed a change management process consistent with DOE Order 413.3-Change 1. Changes to the Secretarial Acquisition Executive and Program-level baselines must be approved by a Program Baseline Change Control Board. Specific thresholds have been established for identifying technical, cost, and schedule changes that require approval. The CRWMS continually evaluates system design and operational concepts to optimize performance and/or cost. The Program has developed systems analysis tools to assess potential enhancements to the physical system and to determine the impacts from cost saving initiatives, scientific and technological improvements, and engineering developments. The results of systems analyses, if appropriate, are factored into revisions to the CRD as revised Programmatic Requirements.

C.A. Kouts

2006-05-10T23:59:59.000Z

326

ANALYSES AND PRELIMINARY RESULTS OF AN UPDATED ITER RADIOACTIVE WASTE ASSESSMENT  

E-Print Network [OSTI]

ANALYSES AND PRELIMINARY RESULTS OF AN UPDATED ITER RADIOACTIVE WASTE ASSESSMENT S. ZHENG,a * R aimed at updating the ITER radioactive inventory assessment and assisting the waste manage- ment operations, and waste management processes and services. KEYWORDS: ITER, radioactive waste management

327

Modeling of transport and reaction in an engineered barrier for radioactive waste confinement  

E-Print Network [OSTI]

Modeling of transport and reaction in an engineered barrier for radioactive waste confinement G bentonite; Radioactive waste; Modelling; KIRMAT code; Chemical transformations; Mass transport 0169;1. Introduction A particular radioactive waste disposal design proposes to store waste in deep geological layers

Montes-Hernandez, German

328

Record of Decision for the Department of Energy's Waste Management Program; Treatment and Storage of Transuranic Waste  

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

3630 3630 Federal Register / Vol. 63, No. 15 / Friday, January 23, 1998 / Notices to agreements DOE has entered into, such as those with States, relating to the treatment and storage of TRU waste. Future NEPA review could include, but would not necessarily be limited to, analysis of the need to supplement existing environmental reviews. DOE would conduct all such TRU waste shipments between sites in accordance with applicable transportation requirements and would coordinate these shipments with appropriate State, Tribal and local authorities. This Record of Decision was prepared in coordination with the Record of Decision issued on January 16, 1998, on disposal of DOE's TRU waste, which is based on the Waste Isolation Pilot Plant Disposal Phase Final Supplemental Environmental Impact Statement (WIPP

329

DOE/EIS-0200-SA-01: Supplement Analysis and Determination for the Proposed Characterization for Disposal of Contact-Handled Transuranic Waste at the Waste Isolation Pilot Plant (WIPP) (12/00)  

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

CH-TRU waste may be shipped to WIPP in drums, standard waste boxes, or drum overpacks; 1,250 cubic meters is the CH-TRU waste may be shipped to WIPP in drums, standard waste boxes, or drum overpacks; 1,250 cubic meters is the equivalent of about 6,000 drums (4.8 drums/cubic meter). 1 Supplement Analysis and Determination for the Proposed Characterization for Disposal of Contact-Handled Transuranic Waste at the Waste Isolation Pilot Plant (WIPP) (DOE/EIS- 0200-SA-01) 1.0 Introduction In the Record of Decision for the Department of Energy's Waste Isolation Pilot Plant Disposal Phase Supplemental Environmental Impact Statement (63 Fed. Reg. 3623, January 23, 1998), the Department of Energy (DOE) decided to dispose of transuranic (TRU) waste at WIPP after preparing it to meet WIPP's Waste Acceptance Criteria (WAC). In the Record of Decision for the Department of Energy's Waste Management Program: Treatment and Storage of

330

DOE/EIS-0200-SA-01: Supplement Analysis and Determination for the Proposed Characterization for Disposal of Contact-Handled Transuranic Waste at the Waste Isolation Pilot Plant (WIPP) (12/00)  

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

CH-TRU waste may be shipped to WIPP in drums, standard waste boxes, or drum overpacks; 1,250 cubic meters is the CH-TRU waste may be shipped to WIPP in drums, standard waste boxes, or drum overpacks; 1,250 cubic meters is the equivalent of about 6,000 drums (4.8 drums/cubic meter). 1 Supplement Analysis and Determination for the Proposed Characterization for Disposal of Contact-Handled Transuranic Waste at the Waste Isolation Pilot Plant (WIPP) (DOE/EIS- 0200-SA-01) 1.0 Introduction In the Record of Decision for the Department of Energy's Waste Isolation Pilot Plant Disposal Phase Supplemental Environmental Impact Statement (63 Fed. Reg. 3623, January 23, 1998), the Department of Energy (DOE) decided to dispose of transuranic (TRU) waste at WIPP after preparing it to meet WIPP's Waste Acceptance Criteria (WAC). In the Record of Decision for the Department of Energy's Waste Management Program: Treatment and Storage of

331

The basics in transportation of low-level radioactive waste  

SciTech Connect (OSTI)

This bulletin gives a basic understanding about issues and safety standards that are built into the transportation system for radioactive material and waste in the US. An excellent safety record has been established for the transport of commercial low-level radioactive waste, or for that matter, all radioactive materials. This excellent safety record is primarily because of people adhering to strict regulations governing the transportation of radioactive materials. This bulletin discusses the regulatory framework as well as the regulations that set the standards for packaging, hazard communications (communicating the potential hazard to workers and the public), training, inspections, routing, and emergency response. The excellent safety record is discussed in the last section of the bulletin.

Allred, W.E.

1998-06-01T23:59:59.000Z

332

Savannah River Site Celebrates Historic Closure of Radioactive Waste Tanks:  

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

Savannah River Site Celebrates Historic Closure of Radioactive Savannah River Site Celebrates Historic Closure of Radioactive Waste Tanks: Senior DOE Officials and South Carolina Congressional Leadership Gather to Commemorate Historic Cleanup Milestone Savannah River Site Celebrates Historic Closure of Radioactive Waste Tanks: Senior DOE Officials and South Carolina Congressional Leadership Gather to Commemorate Historic Cleanup Milestone October 1, 2012 - 12:00pm Addthis U.S. Energy Under Secretary for Nuclear Security Thomas D'Agostino, left, South Carolina Department of Health and Environmental Control Director Catherine Templeton and U.S. Sen. Lindsey Graham (R-SC) unveil a marker to commemorate the closing of waste tanks at the Savannah River Site in South Carolina. U.S. Energy Under Secretary for Nuclear Security Thomas D'Agostino, left,

333

Savannah River Site Celebrates Historic Closure of Radioactive Waste Tanks:  

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

Savannah River Site Celebrates Historic Closure of Radioactive Savannah River Site Celebrates Historic Closure of Radioactive Waste Tanks: Senior DOE Officials and South Carolina Congressional Leadership Gather to Commemorate Historic Cleanup Milestone Savannah River Site Celebrates Historic Closure of Radioactive Waste Tanks: Senior DOE Officials and South Carolina Congressional Leadership Gather to Commemorate Historic Cleanup Milestone October 1, 2012 - 12:00pm Addthis U.S. Energy Under Secretary for Nuclear Security Thomas D'Agostino, left, South Carolina Department of Health and Environmental Control Director Catherine Templeton and U.S. Sen. Lindsey Graham (R-SC) unveil a marker to commemorate the closing of waste tanks at the Savannah River Site in South Carolina. U.S. Energy Under Secretary for Nuclear Security Thomas D'Agostino, left,

334

Sandia National Laboratories: radioactive waste solution cleanup  

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

in Fukushima and Worldwide On February 14, 2013, in Energy, Materials Science, Nuclear Energy, Partnership, Research & Capabilities Radiation waste cleanup was in the public eye...

335

Roadmapping the Resolution of Gas Generation Issues in Packages Containing Radioactive Waste/Materials  

SciTech Connect (OSTI)

Gas generation issues, particularly hydrogen, have been an area of concern for the transport and storage of radioactive materials and waste in the Department of Energy (DOE) complex. Potentially combustible gases can be generated through a variety of reactions, including chemical reactions and radiolytic decomposition of hydrogen-containing materials. Transportation regulations prohibit shipment of explosives and radioactive materials together. This paper discusses the major gas generation issues within the DOE Complex and the research that has been and is being conducted by the transuranic (TRU) waste, nuclear materials (NM), and spent nuclear fuels (SNF) programs within DOEs Environmental Management (EM) organization to address gas generation concerns. This paper presents a "program level" roadmap that links technology development to program needs and identifies the probability of success in an effort to understand the programmatic risk associated with the issue of gas generation. This "program level" roadmapping involves linking technology development (and deployment) efforts to the programs needs and requirements for dispositioning the material/waste that generates combustible gas through radiolysis and chemical decomposition. The roadmapping effort focused on needed technical & programmatic support to the baselines (and to alternatives to the baselines) where the probability of success is low (i.e., high uncertainty) and the consequences of failure are relatively high (i.e., high programmatic risk). A second purpose for roadmapping was to provide the basis for coordinating sharing of "lessons learned" from research and development (R&D) efforts across DOE programs to increase efficiency and effectiveness in addressing gas generation issues.

Luke, Dale Elden; Rogers, Adam Zachary; Hamp, S.

2001-03-01T23:59:59.000Z

336

Radioactive waste management in the former USSR. Volume 3  

SciTech Connect (OSTI)

Radioactive waste materials--and the methods being used to treat, process, store, transport, and dispose of them--have come under increased scrutiny over last decade, both nationally and internationally. Nuclear waste practices in the former Soviet Union, arguably the world`s largest nuclear waste management system, are of obvious interest and may affect practices in other countries. In addition, poor waste management practices are causing increasing technical, political, and economic problems for the Soviet Union, and this will undoubtedly influence future strategies. this report was prepared as part of a continuing effort to gain a better understanding of the radioactive waste management program in the former Soviet Union. the scope of this study covers all publicly known radioactive waste management activities in the former Soviet Union as of April 1992, and is based on a review of a wide variety of literature sources, including documents, meeting presentations, and data base searches of worldwide press releases. The study focuses primarily on nuclear waste management activities in the former Soviet Union, but relevant background information on nuclear reactors is also provided in appendixes.

Bradley, D.J.

1992-06-01T23:59:59.000Z

337

SPRU Removes High-Risk Radioactive Waste  

Broader source: Energy.gov [DOE]

NISKAYUNA, N.Y. EMs Separations Process Research Unit (SPRU) Disposition Project completed a significant waste-treatment campaign in February that involved the solidification of approximately 9,700 gallons of contaminated sludge and 14 shipments of the waste off-site for permanent disposal.

338

s.haszeldine@ed.ac.uk Radioactive waste Cumbria 6, 7 Sept 2012 1 Geological disposal of radioactive  

E-Print Network [OSTI]

of Edinburgh Professor of Geology Nuclear waste ­ exists and has to be solved Nuclear power ­ is likely_and_Copeland.html #12;Nuclear power s.haszeldine@ed.ac.uk Radioactive waste Cumbria 6, 7 Sept 2012 2 First civil nuclear waste Cumbria 6, 7 Sept 2012 15 Thus, the nuclear industry has calculated that the escape of radioactive

339

CONCEPTUAL DATA MODELING OF THE INTEGRATED DATABASE FOR THE RADIOACTIVE WASTE MANAGEMENT  

SciTech Connect (OSTI)

A study of a database system that can manage radioactive waste collectively on a network has been carried out. A conceptual data modeling that is based on the theory of information engineering (IE), which is the first step of the whole database development, has been studied to manage effectively information and data related to radioactive waste. In order to establish the scope of the database, user requirements and system configuration for radioactive waste management were analyzed. The major information extracted from user requirements are solid waste, liquid waste, gaseous waste, and waste related to spent fuel. The radioactive waste management system is planning to share information with associated companies.

Park, H.S; Shon, J.S; Kim, K.J; Park, J.H; Hong, K.P; Park, S.H

2003-02-27T23:59:59.000Z

340

Low-level radioactive waste technology: a selected, annotated bibliography  

SciTech Connect (OSTI)

This annotated bibliography of 447 references contains scientific, technical, economic, and regulatory information relevant to low-level radioactive waste technology. The bibliography focuses on environmental transport, disposal site, and waste treatment studies. The publication covers both domestic and foreign literature for the period 1952 to 1979. Major chapters selected are Chemical and Physical Aspects; Container Design and Performance; Disposal Site; Environmental Transport; General Studies and Reviews; Geology, Hydrology and Site Resources; Regulatory and Economic Aspects; Transportation Technology; Waste Production; and Waste Treatment. Specialized data fields have been incorporated into the data file to improve the ease and accuracy of locating pertinent references. Specific radionuclides for which data are presented are listed in the Measured Radionuclides field, and specific parameters which affect the migration of these radionuclides are presented in the Measured Parameters field. In addition, each document referenced in this bibliography has been assigned a relevance number to facilitate sorting the documents according to their pertinence to low-level radioactive waste technology. The documents are rated 1, 2, 3, or 4, with 1 indicating direct applicability to low-level radioactive waste technology and 4 indicating that a considerable amount of interpretation is required for the information presented to be applied. The references within each chapter are arranged alphabetically by leading author, corporate affiliation, or title of the document. Indexes are provide for (1) author(s), (2) keywords, (3) subject category, (4) title, (5) geographic location, (6) measured parameters, (7) measured radionuclides, and (8) publication description.

Fore, C.S.; Vaughan, N.D.; Hyder, L.K.

1980-10-01T23:59:59.000Z

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


341

Method for solidification of radioactive and other hazardous waste  

DOE Patents [OSTI]

Solidification of liquid radioactive waste, and other hazardous wastes, is accomplished by the method of the invention by incorporating the waste into a porous glass crystalline molded block. The porous block is first loaded with the liquid waste and then dehydrated and exposed to thermal treatment at 50-1,000.degree. C. The porous glass crystalline molded block consists of glass crystalline hollow microspheres separated from fly ash (cenospheres), resulting from incineration of fossil plant coals. In a preferred embodiment, the porous glass crystalline blocks are formed from perforated cenospheres of grain size -400+50, wherein the selected cenospheres are consolidated into the porous molded block with a binder, such as liquid silicate glass. The porous blocks are then subjected to repeated cycles of saturating with liquid waste, and drying, and after the last cycle the blocks are subjected to calcination to transform the dried salts to more stable oxides. Radioactive liquid waste can be further stabilized in the porous blocks by coating the internal surface of the block with metal oxides prior to adding the liquid waste, and by coating the outside of the block with a low-melting glass or a ceramic after the waste is loaded into the block.

Anshits, Alexander G. (Krasnoyarsk, RU); Vereshchagina, Tatiana A. (Krasnoyarsk, RU); Voskresenskaya, Elena N. (Krasnoyarsk, RU); Kostin, Eduard M. (Zheleznogorsk, RU); Pavlov, Vyacheslav F. (Krasnoyarsk, RU); Revenko, Yurii A. (Zheleznogorsk, RU); Tretyakov, Alexander A. (Zheleznogorsk, RU); Sharonova, Olga M. (Krasnoyarsk, RU); Aloy, Albert S. (Saint-Petersburg, RU); Sapozhnikova, Natalia V. (Saint-Petersburg, RU); Knecht, Dieter A. (Idaho Falls, ID); Tranter, Troy J. (Idaho Falls, ID); Macheret, Yevgeny (Idaho Falls, ID)

2002-01-01T23:59:59.000Z

342

U.S. Department of Energy to Host Press Call on Radioactive Waste...  

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

Department of Energy to Host Press Call on Radioactive Waste Shipment and Disposal U.S. Department of Energy to Host Press Call on Radioactive Waste Shipment and Disposal November...

343

Locations of Spent Nuclear Fuel and High-Level Radioactive Waste...  

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

Locations of Spent Nuclear Fuel and High-Level Radioactive Waste Locations of Spent Nuclear Fuel and High-Level Radioactive Waste Map of the United States of America showing the...

344

Long-term management of high-level radioactive waste (HLW) and...  

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

Long-term management of high-level radioactive waste (HLW) and spent nuclear fuel (SNF) Long-term management of high-level radioactive waste (HLW) and spent nuclear fuel (SNF)...

345

Radioactive Waste Management Complex Wide Review  

Office of Environmental Management (EM)

explain Generation-04.02 Volume, including the waste and any stabilization or absorbent media; No, Yes Generation-04.02.01 If No, please explain Generation-04.03 Weight of the...

346

Radioactive and mixed waste - risk as a basis for waste classification. Symposium proceedings No. 2  

SciTech Connect (OSTI)

The management of risks from radioactive and chemical materials has been a major environmental concern in the United states for the past two or three decades. Risk management of these materials encompasses the remediation of past disposal practices as well as development of appropriate strategies and controls for current and future operations. This symposium is concerned primarily with low-level radioactive wastes and mixed wastes. Individual reports were processed separately for the Department of Energy databases.

NONE

1995-06-21T23:59:59.000Z

347

Memorandum of Understanding between the US Department of Energy and the National Radioactive Waste Management Agency of France  

Broader source: Energy.gov [DOE]

Memorandum of Understanding between the US Department of Energy and the National Radioactive Waste Management Agency of France concerning cooperation in the field of radioactive waste management.

348

Materials and Security Consolidation Complex Facilities Radioactive Waste Management Basis and DOE Manual 435.1-1 Compliance Tables  

SciTech Connect (OSTI)

Department of Energy Order 435.1, 'Radioactive Waste Management,' along with its associated manual and guidance, requires development and maintenance of a radioactive waste management basis for each radioactive waste management facility, operation, and activity. This document presents a radioactive waste management basis for Idaho National Laboratory's Materials and Security Consolidation Center facilities that manage radioactive waste. The radioactive waste management basis for a facility comprises existing laboratory-wide and facility-specific documents. Department of Energy Manual 435.1-1, 'Radioactive Waste Management Manual,' facility compliance tables also are presented for the facilities. The tables serve as a tool for developing the radioactive waste management basis.

Not Listed

2011-09-01T23:59:59.000Z

349

Materials and Fuels Complex Facilities Radioactive Waste Management Basis and DOE Manual 435.1-1 Compliance Tables  

SciTech Connect (OSTI)

Department of Energy Order 435.1, 'Radioactive Waste Management,' along with its associated manual and guidance, requires development and maintenance of a radioactive waste management basis for each radioactive waste management facility, operation, and activity. This document presents a radioactive waste management basis for Idaho National Laboratory's Materials and Fuels Complex facilities that manage radioactive waste. The radioactive waste management basis for a facility comprises existing laboratory-wide and facility-specific documents. Department of Energy Manual 435.1-1, 'Radioactive Waste Management Manual,' facility compliance tables also are presented for the facilities. The tables serve as a tool for developing the radioactive waste management basis.

Lisa Harvego; Brion Bennett

2011-09-01T23:59:59.000Z

350

Commercial low-level radioactive waste transportation liability and radiological risk  

SciTech Connect (OSTI)

This report was prepared for States, compact regions, and other interested parties to address two subjects related to transporting low-level radioactive waste to disposal facilities. One is the potential liabilities associated with low-level radioactive waste transportation from the perspective of States as hosts to low-level radioactive waste disposal facilities. The other is the radiological risks of low-level radioactive waste transportation for drivers, the public, and disposal facility workers.

Quinn, G.J.; Brown, O.F. II; Garcia, R.S.

1992-08-01T23:59:59.000Z

351

Cesium removal from Savannah River Site radioactive waste using crystalline silicotitanate (IONSIV(R) IE-911)  

SciTech Connect (OSTI)

This study measured the ability of crystalline silicotitanate to remove cesium from Savannah River Site radioactive waste.

Walker, D.D.

1999-12-15T23:59:59.000Z

352

Plutonium Equivalent Inventory for Belowground Radioactive Waste at the Los Alamos National Laboratory Technical Area 54, Area G Disposal Facility - Fiscal Year 2011  

SciTech Connect (OSTI)

The Los Alamos National Laboratory (LANL) generates radioactive waste as a result of various activities. Many aspects of the management of this waste are conducted at Technical Area 54 (TA-54); Area G plays a key role in these management activities as the Laboratory's only disposal facility for low-level radioactive waste (LLW). Furthermore, Area G serves as a staging area for transuranic (TRU) waste that will be shipped to the Waste Isolation Pilot Plant for disposal. A portion of this TRU waste is retrievably stored in pits, trenches, and shafts. The radioactive waste disposed of or stored at Area G poses potential short- and long-term risks to workers at the disposal facility and to members of the public. These risks are directly proportional to the radionuclide inventories in the waste. The Area G performance assessment and composite analysis (LANL, 2008a) project long-term risks to members of the public; short-term risks to workers and members of the public, such as those posed by accidents, are addressed by the Area G Documented Safety Analysis (LANL, 2011a). The Documented Safety Analysis uses an inventory expressed in terms of plutonium-equivalent curies, referred to as the PE-Ci inventory, to estimate these risks. The Technical Safety Requirements for Technical Area 54, Area G (LANL, 2011b) establishes a belowground radioactive material limit that ensures the cumulative projected inventory authorized for the Area G site is not exceeded. The total belowground radioactive waste inventory limit established for Area G is 110,000 PE-Ci. The PE-Ci inventory is updated annually; this report presents the inventory prepared for 2011. The approach used to estimate the inventory is described in Section 2. The results of the analysis are presented in Section 3.

French, Sean B. [Los Alamos National Laboratory; Shuman, Rob [WPS: WASTE PROJECTS AND SERVICES

2012-04-18T23:59:59.000Z

353

Ion-exchange material and method of storing radioactive wastes  

DOE Patents [OSTI]

A new cation exchanger is a modified tobermorite containing aluminum isomorphously substituted for silicon and containing sodium or potassium. The exchanger is selective for lead, rubidium, cobalt, and cadmium and is selective for cesium over calcium or sodium. The tobermorites are compatible with cement and are useful for the long-term fixation and storage of radioactive nuclear wastes.

Komarneni, S.; Roy, D.M.

1983-10-31T23:59:59.000Z

354

Method of storing radioactive wastes using modified tobermorite  

DOE Patents [OSTI]

A new cation exchanger is a modified tobermorite containing aluminum isomorphously substituted for silicon and containing sodium or potassium. The exchanger is selective for lead, rubidium, cobalt and cadmium and is selective for cesium over calcium or sodium. The tobermorites are compatable with cement and are useful for the long-term fixation and storage of radioactive nuclear wastes.

Komarneni, Sridhar (State College, PA); Roy, Della M. (State College, PA)

1985-01-01T23:59:59.000Z

355

Migration of Radioactive Wastes: Radionuclide Mobilization by Complexing Agents  

Science Journals Connector (OSTI)

...the Hanford, West Valley, and Maxey Flats facilities, respectively (29-31...Chalk River, West Valley, and Maxey Flats (31, 32). The use of EDTA and...transport at many radio-active waste disposal sites in this coun-try, and migration...

JEFFREY L. MEANS; DAVID A. CRERAR; JAMES O. DUGUID

1978-06-30T23:59:59.000Z

356

Field test of the Rapid Transuranic Monitoring Laboratory  

SciTech Connect (OSTI)

A field test of the Rapid Transuranic Monitoring Laboratory (RTML) developed at the Idaho National Engineering Laboratory (INEL) was conducted as part of a demonstration sponsored by the Buried Waste Integrated Demonstration (BWID). The RTML is a mobile, field- deployable laboratory developed for use at buried radioactive waste remediation sites to allow onsite preparation and analysis of soil, smear, and air filter samples for alpha and gamma-emitting contaminants. Analytical instruments installed in the RTML include an extended range, germanium photon analysis spectrometer with an automatic sample changer, two large-area ionization chamber alpha spectrometers, and four alpha continuous air monitors. The performance of the RTML was tested at the Test Reactor Area and Cold Test Pit near the Radioactive Waste Management Complex at the INEL. Objectives, experimental procedures, and an evaluation of the performance of the RTML are presented.

McIsaac, C.V.; Sill, C.W.; Gehrke, R.J.; Killian, E.W.; Watts, K.D.; Amaro, C.R.

1993-12-01T23:59:59.000Z

357

MONTE CARLO SIMULATION OF RADIONUCLIDE MIGRATION IN FRACTURED ROCK FOR THE PERFORMANCE ASSESSMENT OF RADIOACTIVE WASTE  

E-Print Network [OSTI]

OF RADIOACTIVE WASTE REPOSITORIES F. Cadini1 , J. De Sanctis1 , I. Bertoli1 , E. Zio1,2 1 Dipartimento di Energia is a fundamental task in any performance assessment aimed at verifying the protection offered by radioactive waste for chemical or low-level radioactive wastes, or the Performance Assessment (PA) of geological repositories

Paris-Sud XI, Université de

358

Modelling of long-term diffusionreaction in a bentonite barrier for radioactive waste confinement  

E-Print Network [OSTI]

Modelling of long-term diffusion­reaction in a bentonite barrier for radioactive waste confinement in geological disposal facilities for radioactive waste. This material is expected to fill up by swelling transformations; Solute diffusion 1. Introduction The radioactive waste confinement in deep geolo- gical laye

Montes-Hernandez, German

359

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

E-Print Network [OSTI]

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

360

Sequential Thermo-Hydraulic Modeling of Variably Saturated Flow in High-Level Radioactive Waste Repository  

E-Print Network [OSTI]

Sequential Thermo-Hydraulic Modeling of Variably Saturated Flow in High-Level Radioactive Waste long-lived radioactive wastes must be managed in a safe way for human health and for the environment. That is the raison why the French agency for the management of radioactive waste (ANDRA) is engaged to study

Boyer, Edmond

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


361

Radiological protection from radioactive waste management in existing exposure situations resulting from a nuclear accident  

Science Journals Connector (OSTI)

......people living in long-term-contaminated...Radioactive waste management in...longer-term storage and appropriate...appropriate for the long-term assessment...long-lived radioactive wastes in planned exposure...People Living in Long-term Contaminated...from Radioactive Waste Management in......

Daisuke Sugiyama; Takatoshi Hattori

2013-01-01T23:59:59.000Z

362

Applications Where Snap is BPM for Radioactive Waste Assay  

SciTech Connect (OSTI)

Historically, the Atomic Weapons Establishment (AWE) at Aldermaston in the United Kingdom (UK), has used a variety of assay techniques to measure the radioactive content of a diverse range of waste packages from decommissioning, operational and legacy sources. The regulator, the Environment Agency in the UK, places conditions and limits on AWE through an authorisation within the Radioactive Substances Act (RSA93). The conditions and limits require Best Practical Means (BPM) measurements to be used to demonstrate compliance with the authorisation. Hence, the assay technique employed needs to achieve a balance between risk of exposure, environmental considerations, technological considerations, health and safety considerations and cost effectiveness, without being grossly disproportionate in terms of money, time or trouble. Recently published work has concluded that the Spectral Non-destructive Assay Platform (SNAP) assay system is BPM for Depleted Uranium (DU) waste assay at AWE (1) and low level plutonium in soft drummed waste, HEPA filters and soils (2-4). The purpose of this paper is to highlight other applications where SNAP represents BPM for radioactive waste assay. This has been done by intercomparison studies of SNAP with other assay techniques, such as Segmented Gamma Scanner (SGS) and Passive Neutron Coincidence Counter (PNCC). It has been concluded that, for a large range of waste packages encountered at AWE, SNAP is BPM. (author)

Miller, T.J. [AWE, Aldermaston, Reading, Berkshire (United Kingdom)

2008-07-01T23:59:59.000Z

363

Disposal of radioactive waste from nuclear research facilities  

E-Print Network [OSTI]

Swiss radioactive wastes originate from nuclear power plants (NPP) and from medicine (e.g. radiation sources), industry (e.g. fire detectors) and research (e.g. CERN, PSI). Their conditioning, characterisation and documentation has to meet the demands given by the Swiss regulatory authorities including all information needed for a safe disposal in future repositories. For NPP wastes, arisings as well as the processes responsible for the buildup of short and long lived radionuclides are well known, and the conditioning procedures are established. The radiological inventories are determined on a routinely basis using a combined system of measurements and calculational programs. For waste from research, the situation is more complicated. The wide spectrum of different installations combined with a poorly known history of primary and secondary radiation results in heterogeneous waste sorts with radiological inventories quite different from NPP waste and difficult to measure long lived radionuclides. In order to c...

Maxeiner, H; Kolbe, E

2003-01-01T23:59:59.000Z

364

Management of radioactive waste from nuclear power plants: An overview  

SciTech Connect (OSTI)

The nuclear power industry, which accounts for about 20% of the total electricity supply, is a vital part of the nation`s energy resource. While it generates approximately one-third of the commercial low-level radioactive waste produced in the country, it has achieved one of the most successful examples in waste minimization. On the other hand, progress on development of new disposal facilities by the state compacts is currently stalled. The milestones have been repeatedly postponed, and the various Acts passed by Congress on nuclear waste disposal have not accomplished what they were intended to do. With dwindling access to waste disposal sites and with escalating disposal costs, the power plant utilities are forced to store wastes onsite as an interim measure. However, such temporary measures are not a permanent solution. A national will is sorely needed to break out of the current impasse.

Devgun, J.S.

1994-07-01T23:59:59.000Z

365

RETENTION OF SULFATE IN HIGH LEVEL RADIOACTIVE WASTE GLASS  

SciTech Connect (OSTI)

High level radioactive wastes are being vitrified at the Savannah River Site for long term disposal. Many of the wastes contain sulfate at concentrations that can be difficult to retain in borosilicate glass. This study involves efforts to optimize the composition of a glass frit for combination with the waste to improve sulfate retention while meeting other process and product performance constraints. The fabrication and characterization of several series of simulated waste glasses are described. The experiments are detailed chronologically, to provide insight into part of the engineering studies used in developing frit compositions for an operating high level waste vitrification facility. The results lead to the recommendation of a specific frit composition and a concentration limit for sulfate in the glass for the next batch of sludge to be processed at Savannah River.

Fox, K.

2010-09-07T23:59:59.000Z

366

The importance of zeolites in the potential high-level radioactive waste repository at Yucca Mountain, Nevada  

SciTech Connect (OSTI)

Zeolitic rocks play an important role in retarding the migration of radionuclides that occur in solution as simple cations (Cs, Sr, Ba). However, the interaction of zeolites with complex transuranic species in solution provides little if any advantage over other common silicate minerals. The most important consequences of zeolite occurrences near a high-level radioactive waste repository environment are likely to be their response to thermal loading and their impact on site hydrology. Partial zeolite dehydration during the early thermal pulse from the repository and rehydration as the repository slowly cools can have an important impact on the water budget of a repository in unsaturated rocks, provided that the long-term heating does not result in zeolite destabilization.

Vaniman, D.T.; Bish, D.L.

1993-07-01T23:59:59.000Z

367

Guidelines for generators of hazardous chemical waste at LBL and guidelines for generators of radioactive and mixed waste at LBL  

SciTech Connect (OSTI)

In part one of this document the Governing Documents and Definitions sections provide general guidelines and regulations applying to the handling of hazardous chemical wastes. The remaining sections provide details on how you can prepare your waste properly for transport and disposal. They are correlated with the steps you must take to properly prepare your waste for pickup. The purpose of the second part of this document is to provide the acceptance criteria for the transfer of radioactive and mixed waste to LBL's Hazardous Waste Handling Facility (HWHF). These guidelines describe how you, as a generator of radioactive or mixed waste, can meet LBL's acceptance criteria for radioactive and mixed waste.

Not Available

1991-09-01T23:59:59.000Z

368

Waste Disposal Site and Radioactive Waste Management (Iowa)  

Broader source: Energy.gov [DOE]

This section describes the considerations of the Commission in determining whether to approve the establishment and operation of a disposal site for nuclear waste. If a permit is issued, the...

369

Enclosure 3 DOE Response to EPA Question Regarding "High-Level Liquid Radioactive Waste"  

E-Print Network [OSTI]

to date, which is from the definitions in the Nuclear Waste Policy Act: The term "high-level radioactive of waste streams as from the applicable definition of HLW in the Nuclear Waste Policy Act. 5/11/20051 #12 defining High Level Waste: For the purpose of this statement of policy, "high-level liquid radioactive

370

COMPLETION OF THE TRANSURANIC GREATER CONFINEMENT DISPOSAL BOREHOLE PERFORMANCE ASSESSMENT FOR THE NEVADA TEST SITE  

SciTech Connect (OSTI)

Classified transuranic material that cannot be shipped to the Waste Isolation Pilot Plant in New Mexico is stored in Greater Confinement Disposal boreholes in the Area 5 Radioactive Waste Management Site on the Nevada Test Site. A performance assessment was completed for the transuranic inventory in the boreholes and submitted to the Transuranic Waste Disposal Federal Review Group. The performance assessment was prepared by Sandia National Laboratories on behalf of the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office using an iterative methodology that assessed radiological releases from the intermediate depth disposal configuration against the regulatory requirements of the 1985 version of 40 CFR 191 of the U.S. Environmental Protection Agency. The transuranic materials are stored at 21 to 37 m depth (70 to 120 ft) in large diameter boreholes constructed in the unsaturated alluvial deposits of Frenchman Flat. Hydrologic processes that affect long- term isolation of the radionuclides are dominated by extremely slow upward rates of liquid/vapor advection and diffusion; there is no downward pathway under current climatic conditions and there is no recharge to groundwater under future ''glacial'' climatic conditions. A Federal Review Team appointed by the Transuranic Waste Disposal Federal Review Group reviewed the Greater Confinement Disposal performance assessment and found that the site met the majority of the regulatory criteria of the 1985 and portions of the 1993 versions of 40 CFR 191. A number of technical and procedural issues required development of supplemental information that was incorporated into a final revision of the performance assessment. These issues include inclusion of radiological releases into the complementary cumulative distribution function for the containment requirements associated with drill cuttings from inadvertent human intrusion, verification of mathematical models used in the performance assessment, inclusion of dose calculations from collocated low-level waste in the boreholes for the individual protection requirements, further assessments of engineered barriers and conditions associated with the assurance requirements, and expansion of documentation provided for assessing the groundwater protection requirements. The Transuranic Waste Disposal Federal Review Group approved the performance assessment for Greater Confinement Disposal boreholes in 2001 and did not approve the Application of the Assurance Requirements. Remaining issues concerned with engineered barriers and the multiple aspects of the Assurance Requirements will be resolved at the time of closure of the Area 5 Radioactive Waste Management Site. This is the first completion and acceptance of a performance assessment for transuranic materials under the U.S. Department of Energy self-regulation. The Greater Confinement Disposal boreholes are only the second waste disposal configuration to meet the safety regulatory requirements of 40 CFR 191.

Colarusso, Angela; Crowe, Bruce; Cochran, John R.

2003-02-27T23:59:59.000Z

371

EIS-0200: Managing Treatment, Storage, and Disposal of Radioactive and  

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

00: Managing Treatment, Storage, and Disposal of Radioactive 00: Managing Treatment, Storage, and Disposal of Radioactive and Hazardous Waste EIS-0200: Managing Treatment, Storage, and Disposal of Radioactive and Hazardous Waste SUMMARY This EIS evaluates the potential environmental and cost impacts of strategic managment alternatives for managing five types of radioactive and hazardous wastes that have resulted and will continue to result from nuclear defense and research activities at a variety of sites around the United States. PUBLIC COMMENT OPPORTUNITIES None available at this time. DOCUMENTS AVAILABLE FOR DOWNLOAD July 7, 2011 EIS-0200-SA-03: Supplement Analysis Treatment of Transuranic Waste at the Idaho National Laboratory, Carlsbad Field Office March 7, 2008 EIS-0200: Amendment to the Record of Decision Treatment and Storage of Transuranic Waste

372

Determination of Iodine-129 in Low Level Radioactive Wastes - 13334  

SciTech Connect (OSTI)

For the radioactivity determination of {sup 129}I in the radioactive wastes, alkali fusion and anion-exchange resin separation methods, which are sample pretreatment methods, have been investigated in this study. To separate and quantify the {sup 129}I radionuclide in an evaporator bottom and spent resin, the radionuclide was chemically leached from the wastes and adsorbed on an anion exchange resin at pH 4, 7, 9. In the case of dry active waste and another solid type, the alkali fusion method was applied. KNO{sub 3} was added as a KOH and oxidizer to the wastes. It was then fused at 450 deg. C for 1 hour. The radioactivity of the separated iodine was measured with a low energy gamma spectrometer after the sample pretreatment. Finally, it was confirmed that the recovery rate of the iodine for the alkali fusion method was 83.63.8%, and 86.41.6% for the anionic exchange separation method. (authors)

Choi, K.C.; Ahn, J.H.; Park, Y.J.; Song, K.S. [Nuclear Chemistry Research Division, Korea Atomic Energy Research Institute, Daejeon, 305-600 (Korea, Republic of)] [Nuclear Chemistry Research Division, Korea Atomic Energy Research Institute, Daejeon, 305-600 (Korea, Republic of)

2013-07-01T23:59:59.000Z

373

Classification and disposal of radioactive wastes: History and legal and regulatory requirements  

SciTech Connect (OSTI)

This document discusses the laws and regulations in the United States addressing classification of radioactive wastes and the requirements for disposal of different waste classes. This review emphasizes the relationship between waste classification and the requirements for permanent disposal.

Kocher, D.C.

1990-01-01T23:59:59.000Z

374

A robotic inspector for low-level radioactive waste  

SciTech Connect (OSTI)

The Department of Energy has low-level radioactive waste stored in warehouses at several facilities. Weekly visual inspections are required. A mobile robot inspection system, ARIES (Autonomous Robotic Inspection Experimental System), has been developed to survey and inspect the stored drums. The robot will travel through the three- foot wide aisles of drums stacked four high and perform a visual inspection, normally performed by a human operator, making decisions about the condition of the drums and maintaining a database of pertinent information about each drum. This mobile robot system will improve the quality of inspection, generate required reports, and relieve human operators from low-level radioactive exposure.

Byrd, J.S.; Pettus, R.O. [South Carolina Univ., Columbia, SC (United States). Dept. of Electrical and Computer Engineering

1996-06-01T23:59:59.000Z

375

Reportable Nuclide Criteria for ORNL Radioactive Waste Management Activities - 13005  

SciTech Connect (OSTI)

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 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 these 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. (authors)

McDowell, Kip; Forrester, Tim [Oak Ridge National Laboratory, PO Box 2008 MS-6322, Oak Ridge, TN 37831 (United States)] [Oak Ridge National Laboratory, PO Box 2008 MS-6322, Oak Ridge, TN 37831 (United States); Saunders, Mark [Fairfield Services Group, PO Box 31468, KNOxville, TN 37930 (United States)] [Fairfield Services Group, PO Box 31468, KNOxville, TN 37930 (United States)

2013-07-01T23:59:59.000Z

376

Order Module--DOE O 435.1 RADIOACTIVE WASTE MANAGEMENT | Department of  

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

35.1 RADIOACTIVE WASTE MANAGEMENT 35.1 RADIOACTIVE WASTE MANAGEMENT Order Module--DOE O 435.1 RADIOACTIVE WASTE MANAGEMENT DOE Order 5820.2A, Radioactive Waste Management, was issued by DOE in September 1988. As early as 1990, DOE began analyzing, assessing, and reviewing the process of implementing the Order. DOE revised the Order on radioactive waste management for several reasons: - After thorough technical reviews and analyses, DOE and the Defense Nuclear Facilities Safety Board concluded that DOE Order 5820.2A did not adequately address the Department's radioactive waste management and disposal practices. -There had been significant advances in radioactive waste management practices and changes in DOE since the Order was issued in 1988. - Risk-based and performance-based requirements were determined to be

377

Order Module--DOE O 435.1 RADIOACTIVE WASTE MANAGEMENT | Department of  

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

O 435.1 RADIOACTIVE WASTE MANAGEMENT O 435.1 RADIOACTIVE WASTE MANAGEMENT Order Module--DOE O 435.1 RADIOACTIVE WASTE MANAGEMENT DOE Order 5820.2A, Radioactive Waste Management, was issued by DOE in September 1988. As early as 1990, DOE began analyzing, assessing, and reviewing the process of implementing the Order. DOE revised the Order on radioactive waste management for several reasons: - After thorough technical reviews and analyses, DOE and the Defense Nuclear Facilities Safety Board concluded that DOE Order 5820.2A did not adequately address the Department's radioactive waste management and disposal practices. -There had been significant advances in radioactive waste management practices and changes in DOE since the Order was issued in 1988. - Risk-based and performance-based requirements were determined to be

378

No Time Wasted. 25 years COVRA: Radioactive Waste Management in the Netherlands  

SciTech Connect (OSTI)

Time will render radioactive waste harmless. How can we manage the time radioactive substances remain harmful? Just 'wait and see' or 'marking time' is not an option. We need to isolate the waste from our living environment and control it as long as necessary. December 2007 was a time to commemorate, as the national waste management organisation of the Netherlands, COVRA, celebrated its 12. anniversary. During this period of 25 years a stable policy has been formulated and implemented. For the situation in the Netherlands, it was obvious that a period of long term storage was needed. Both the small volume of waste and the limited financial possibilities are determining factors. Time is needed to let the volume of waste grow and to let the money, needed for disposal, grow in a capital growth fund. A historical overview of the activities of COVRA is presented and lessons learned over a period of 25 years are given. (authors)

Codee, H.D.K.; Verhoef, E.V. [COVRA N.V., Vlissingen (Netherlands)

2008-07-01T23:59:59.000Z

379

Summary of radioactive solid waste received in the 200 Areas during calendar year 1992  

SciTech Connect (OSTI)

Westinghouse Hanford Company manages and operates the Hanford Site 200 Area radioactive solid waste storage and disposal facilities for the US Department of Energy, Richland Field Office, under contract DE-AC06-87RL10930. These facilities include radioactive solid waste disposal sites and radioactive solid waste storage areas. This document summarizes the amount of radioactive materials that have been buried and stored in the 200 Area radioactive solid waste storage and disposal facilities since startup in 1944 through calendar year 1991. This report does not include solid radioactive wastes in storage or disposed of in other areas or facilities such as the underground tank farms, or backlog wastes. Unless packaged within the scope of WHC-EP-0063, Hanford Site Solid Waste Acceptance Criteria, (WHC 1988), liquid waste data are not included in this document.

Anderson, J.D.; Hagel, D.L.

1992-05-01T23:59:59.000Z

380

Summary of radioactive solid waste received in the 200 Areas during calendar year 1994  

SciTech Connect (OSTI)

Westinghouse Hanford Company manages and operates the Hanford Site 200 Area radioactive solid waste storage and disposal facilities for the US Department of Energy, Richland Field Office, under contract DE-AC06-87RL10930. These facilities include radioactive solid waste disposal sites and radioactive solid waste storage areas. This document summarizes the amount of radioactive material that has been buried and stored in the 200 Area radioactive solid waste storage and disposal facilities from startup in 1944 through calendar year 1994. This report does not include backlog waste: solid radioactive wastes in storage or disposed of in other areas or facilities such as the underground tank farms. Unless packaged within the scope of WHC-EP-0063, Hanford Site Solid Waste Acceptance Criteria (WHC 1988), liquid waste data are not included in this document.

Anderson, J.D.; Hagel, D.L.

1995-08-01T23:59:59.000Z

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


381

Summary of radioactive solid waste received in the 200 Areas during calendar year 1993  

SciTech Connect (OSTI)

Westinghouse Hanford Company manages and operates the Hanford Site 200 Areas radioactive solid waste storage and disposal facilities for the US Department of Energy, Richland Operations Office. These facilities include radioactive solid waste disposal sites and radioactive solid waste storage areas. This document summarizes the amount of radioactive materials that have been buried and stored in the 200 Areas radioactive solid waste storage and disposal facilities since startup in 1944 through calendar year 1993. This report does not include backlog waste, solid radioactive waste in storage or disposed of in other areas, or facilities such as the underground tank farms. Unless packaged within the scope of WHC-EP-0063, ``Hanford Site Solid Waste Acceptance Criteria,`` (WHC 1988), liquid waste data are not included in this document.

Anderson, J.D.; Hagel, D.L.

1994-09-01T23:59:59.000Z

382

Processing of solid mixed waste containing radioactive and hazardous materials  

DOE Patents [OSTI]

Apparatus for the continuous heating and melting of a solid mixed waste bearing radioactive and hazardous materials to form separate metallic, slag and gaseous phases for producing compact forms of the waste material to facilitate disposal includes a copper split water-cooled (cold) crucible as a reaction vessel for receiving the waste material. The waste material is heated by means of the combination of a plasma torch directed into the open upper portion of the cold crucible and an electromagnetic flux produced by induction coils disposed about the crucible which is transparent to electromagnetic fields. A metallic phase of the waste material is formed in a lower portion of the crucible and is removed in the form of a compact ingot suitable for recycling and further processing. A glass-like, non-metallic slag phase containing radioactive elements is also formed in the crucible and flows out of the open upper portion of the crucible into a slag ingot mold for disposal. The decomposition products of the organic and toxic materials are incinerated and converted to environmentally safe gases in the melter. 6 figs.

Gotovchikov, V.T.; Ivanov, A.V.; Filippov, E.A.

1998-05-12T23:59:59.000Z

383

DEVELOPMENT OF GLASS MATRICES FOR HLW RADIOACTIVE WASTES  

SciTech Connect (OSTI)

Vitrification is currently the most widely used technology for the treatment of high level radioactive wastes (HLW) throughout the world. Most of the nations that have generated HLW are immobilizing in either borosilicate glass or phosphate glass. One of the primary reasons that glass has become the most widely used immobilization media is the relative simplicity of the vitrification process, e.g. melt waste plus glass forming frit additives and cast. A second reason that glass has become widely used for HLW is that the short range order (SRO) and medium range order (MRO) found in glass atomistically bonds the radionuclides and governs the melt properties such as viscosity, resistivity, sulphate solubility. The molecular structure of glass controls contaminant/radionuclide release by establishing the distribution of ion exchange sites, hydrolysis sites, and the access of water to those sites. The molecular structure is flexible and hence accounts for the flexibility of glass formulations to waste variability. Nuclear waste glasses melt between 1050-1150 C which minimizes the volatility of radioactive components such as Tc{sup 99}, Cs{sup 137}, and I{sup 129}. Nuclear waste glasses have good long term stability including irradiation resistance. Process control models based on the molecular structure of glass have been mechanistically derived and have been demonstrated to be accurate enough to control the world's largest HLW Joule heated ceramic melter in the US since 1996 at 95% confidence.

Jantzen, C.

2010-03-18T23:59:59.000Z

384

Microbial effects on radioactive wastes at SLB sites  

SciTech Connect (OSTI)

The objectives of this study are to determine the significance of microbial degradation of organic wastes on radionuclide migration on shallow land burial for humid and arid sites, establish which mechanisms predominate and ascertain the conditions under which these mechanisms operate. Factors contolling gaseous eminations from low-level radioactive waste disposal sites are assessed. Importance of gaseous fluxes of methane, carbon dioxide and possibly hydrogen from the site stems from the inclusion of tritium and/or /sup 14/C into the elemental composition of these compounds. In that the primary source of these gases is the biodegradation of organic components of the waste materials, primary emphasis of the study involved on examination of the biochemical pathways producing methane, carbon dioxide and hydrogen, and the environmental parameters controlling the activity of the microbial community involved. Although the methane and carbon dioxide production rate indicates the degradation rate of the organic substances in the waste, it does not predict the methane evolution rate from the trench site. Methane fluxes from the soil surface are equivalent to the net synthesis minus the quantity oxidized by the microbial community as the gas passes through the soil profile. Gas studies were performed at three commercial low-level radioactive waste disposal sites (West Valley, New York; Beatty, Nevada; Maxey Flats, Kentucky) during the period 1976 to 1978. The results of these studies are presented. 3 tables.

Colombo, P.

1982-01-01T23:59:59.000Z

385

Office of Civilian Radioactive Waste Management annual report to Congress  

SciTech Connect (OSTI)

This sixth Annual Report to Congress by the Office of Civilian Radioactive Waste Management (OCRWM) describes activities and expenditures of the Office during fiscal year 1988. An epilogue chapter reports significant events from the end of the fiscal year on September 30, 1988 through March 1989. The Nuclear Waste Policy Amendments Act (NWPA) of 1987 made significant changes to the NWPA relating to repository siting and monitored retrievable storage and added new provisions for the establishment of several institutional entities with which OCRWM will interact. Therefore, a dominant theme throughout this report is the implementation of the policy focus and specific provisions of the Amendments Act. 50 refs., 8 figs., 4 tabs.

NONE

1989-12-01T23:59:59.000Z

386

Regulation of geological disposal of high-level radioactive waste  

SciTech Connect (OSTI)

The Nuclear Regulatory Commission has been actively developing needed regulations over the last two years for the geological disposal of high-level radioactive waste. Technical criteria are about to be published in the form of a proposed regulation. The waste packages, underground facility, and geologic setting form the major elements of any geologic repository and the basis of a multibarrier system. Performance objectives and supporting technical criteria have been developed for each of these repository elements to provide benchmarks for scientists and engineers working in each of these major areas. 9 refs.

White, L.A.

1981-11-01T23:59:59.000Z

387

Northeast High-Level Radioactive Waste Transportation Task Force Agenda  

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

Northeast High-Level Radioactive Waste Transportation Task Force Northeast High-Level Radioactive Waste Transportation Task Force Spring Meeting - May 15, 2012 Hilton Knoxville 501 West Church Avenue, Knoxville, TN 37902-2591 Agenda (Draft #1 - 4/18/12) ______________________________________________________________________________ Tuesday, May 15 - 9:00 AM - 3:30 PM / (need meeting room name) 8:00 a.m. Continental Breakfast - served in meeting room 9:00 a.m. Task Force Business Meeting - John Giarrusso, MEMA and Rich Pinney, NJDEP Co-chairs presiding  Welcome: Introductions; Agenda Review; Announcements  2012 funding  Co-Chair Election  Rules of Procedure  Membership: members & alternates appointment status  Legislative Liaisons  Staff Regional Meeting Attendance

388

THE USE OF POLYMERS IN RADIOACTIVE WASTE PROCESSING SYSTEMS  

SciTech Connect (OSTI)

The Savannah River Site (SRS), one of the largest U.S. Department of Energy (DOE) sites, has operated since the early 1950s. The early mission of the site was to produce critical nuclear materials for national defense. Many facilities have been constructed at the SRS over the years to process, stabilize and/or store radioactive waste and related materials. The primary materials of construction used in such facilities are inorganic (metals, concrete), but polymeric materials are inevitably used in various applications. The effects of aging, radiation, chemicals, heat and other environmental variables must therefore be understood to maximize service life of polymeric components. In particular, the potential for dose rate effects and synergistic effects on polymeric materials in multivariable environments can complicate compatibility reviews and life predictions. The selection and performance of polymeric materials in radioactive waste processing systems at the SRS are discussed.

Skidmore, E.; Fondeur, F.

2013-04-15T23:59:59.000Z

389

Research trends in radioactive waste management: a global perspective  

Science Journals Connector (OSTI)

The present study is aimed at analysing the growth of literature on radioactive waste management. International Nuclear Information System (INIS) database is used as a data source to analyse the focused areas of this field for the period 1970-2011. Journal Citation Report-2010 is used for eliciting information related to journal impact factors. The database contained a total of 101,419 publications covered by all the channels of communication during the period. The study analyses the broad features focusing on its publication growth characteristics, country-wise distribution of publications, domain-wise publications and activity index, various methods of radioactive waste disposal, institutions active in the field, communication channels, and journals preferred for publication by the scientists and the highly cited publications.

B.S. Kademani; Ganesh Surwase; Anil Sagar; Lalit Mohan; K. Bhanumurthy

2013-01-01T23:59:59.000Z

390

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

SciTech Connect (OSTI)

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

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

2003-02-27T23:59:59.000Z

391

Court blocks testing of nuclear waste site  

Science Journals Connector (OSTI)

Court blocks testing of nuclear waste site ... WIPP was authorized by Congress in 1979 to provide an R&D facility to demonstrate safe handling, transport, and disposal of "mixed" transuranic wastes (contaminated with radioactive plutonium-239 and hazardous chemicals), which are now stored temporarily at DOE nuclear-weapons-making facilities. ...

RICHARD SELTZER

1992-02-10T23:59:59.000Z

392

Teaching Radioactive Waste Management in an Undergraduate Engineering Program - 13269  

SciTech Connect (OSTI)

The University of Ontario Institute of Technology is Ontario's newest university and the only one in Canada that offers an accredited Bachelor of Nuclear Engineering (Honours) degree. The nuclear engineering program consists of 48 full-semester courses, including one on radioactive waste management. This is a design course that challenges young engineers to develop a fundamental understanding of how to manage the storage and disposal of various types and forms of radioactive waste, and to recognize the social consequences of their practices and decisions. Students are tasked with developing a major project based on an environmental assessment of a simple conceptual design for a waste disposal facility. They use collaborative learning and self-directed exploration to gain the requisite knowledge of the waste management system. The project constitutes 70% of their mark, but is broken down into several small components that include, an environmental assessment comprehensive study report, a technical review, a facility design, and a public defense of their proposal. Many aspects of the project mirror industry team project situations, including the various levels of participation. The success of the students is correlated with their engagement in the project, the highest final examination scores achieved by students with the strongest effort in the project. (authors)

Ikeda, Brian M. [Faculty of Energy Systems and Nuclear Science, University of Ontario Institute of Technology, 2000 Simcoe Street North, Oshawa, Ontario L1H 7K4 (Canada)] [Faculty of Energy Systems and Nuclear Science, University of Ontario Institute of Technology, 2000 Simcoe Street North, Oshawa, Ontario L1H 7K4 (Canada)

2013-07-01T23:59:59.000Z

393

Microbial transformation of low-level radioactive waste  

SciTech Connect (OSTI)

Microorganisms play a significant role in the transformation of the radioactive waste and waste forms disposed of at shallow-land burial sites. Microbial degradation products of organic wastes may influence the transport of buried radionuclides by leaching, solubilization, and formation of organoradionuclide complexes. The ability of indigenous microflora of the radioactive waste to degrade the organic compounds under aerobic and anaerobic conditions was examined. Leachate samples were extracted with methylene chloried and analyzed for organic compounds by gas chromatography and mass spectrometry. In general, several of the organic compounds in the leachates were degraded under aerobic conditions. Under anaerobic conditions, the degradation of the organics was very slow, and changes in concentrations of several acidic compounds were observed. Several low-molecular-weight organic acids are formed by breakdown of complex organic materials and are further metabolized by microorganisms; hence these compounds are in a dynamic state, being both synthesized and destroyed. Tributyl phosphate, a compound used in the extraction of metal ions from solutions of reactor products, was not degraded under anaerobic conditions.

Francis, A.J.

1980-06-01T23:59:59.000Z

394

Radioactive Liquid Waste Treatment Facility Discharges in 2011  

SciTech Connect (OSTI)

This report documents radioactive discharges from the TA50 Radioactive Liquid Waste Treatment Facilities (RLWTF) during calendar 2011. During 2011, three pathways were available for the discharge of treated water to the environment: discharge as water through NPDES Outfall 051 into Mortandad Canyon, evaporation via the TA50 cooling towers, and evaporation using the newly-installed natural-gas effluent evaporator at TA50. Only one of these pathways was used; all treated water (3,352,890 liters) was fed to the effluent evaporator. The quality of treated water was established by collecting a weekly grab sample of water being fed to the effluent evaporator. Forty weekly samples were collected; each was analyzed for gross alpha, gross beta, and tritium. Weekly samples were also composited at the end of each month. These flow-weighted composite samples were then analyzed for 37 radioisotopes: nine alpha-emitting isotopes, 27 beta emitters, and tritium. These monthly analyses were used to estimate the radioactive content of treated water fed to the effluent evaporator. Table 1 summarizes this information. The concentrations and quantities of radioactivity in Table 1 are for treated water fed to the evaporator. Amounts of radioactivity discharged to the environment through the evaporator stack were likely smaller since only entrained materials would exit via the evaporator stack.

Del Signore, John C. [Los Alamos National Laboratory

2012-05-16T23:59:59.000Z

395

DOE/EIS-0305-D; Draft Environmental Impact Statement for Treating Transuranic/Alpha Low-Level Waste at the Oak Ridge National Laboratory Oak Ridge, Tennessee (February 2000)  

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

05-D 05-D DRAFT ENVIRONMENTAL IMPACT STATEMENT (DEIS) FOR TREATING TRANSURANIC (TRU)/ALPHA LOW-LEVEL WASTE AT THE OAK RIDGE NATIONAL LABORATORY OAK RIDGE, TENNESSEE February 2000 TRU Waste Treatment Project, DRAFT Environmental Impact Statement COVER SHEET RESPONSIBLE AGENCY: U.S. Department of Energy (DOE) TITLE: Draft Environmental Impact Statement (EIS) for Treating Transuranic (TRU)/Alpha Low-Level Waste at the Oak Ridge National Laboratory, Oak Ridge, Tennessee CONTACT: For further information on this document, write or call: Dr. Clayton Gist, Waste Management Integration Team Leader U.S. Department of Energy Oak Ridge Operations 55 Jefferson Avenue P. O. Box 2001 Oak Ridge, TN 37831 Telephone: (865) 241-3498 * Facsimile: (865) 576-5333 * E-Mail: gistcs@oro.doe.gov

396

Gamma monitor for assay of radioactive solid-waste shipments  

SciTech Connect (OSTI)

A gamma waste monitor has been developed and evaluated at the Savannah River Plant (SRP). The purpose of the monitor is to improve estimates of the radionuclides in solid wastes arriving at the plant's burial ground. This monitor, a computer-based spectrometer, quantitatively measures many radionuclides in SRP waste, including waste in heavily shielded shipping casks. Radionuclides emitting gamma rays of sufficient energy to penetrate the shipping container walls can be measured directly. Other radionuclides that are beta emitters or which emit gamma photons too weak to penetrate the walls of the waste containers can often be estimated by their association with measurable gamma photons. Development of the monitor was initiated to find a more accurate method of estimating the quantities of radioactive materials accumulated in the burial ground and to ensure compliance with burial limits imposed by SRP technical standards. Another benefit from the monitor is that it provides specific radionuclide data which are essential to environmental impact evaluations and decommissioning planning. The gamma waste monitor is described. (WHK)

Crawford, J H

1982-06-01T23:59:59.000Z

397

EIS-0375: Disposal of Greater-than-Class-C Low-Level Radioactive Waste and  

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

5: Disposal of Greater-than-Class-C Low-Level Radioactive 5: Disposal of Greater-than-Class-C Low-Level Radioactive Waste and Department of Energy GTCC-like Waste EIS-0375: Disposal of Greater-than-Class-C Low-Level Radioactive Waste and Department of Energy GTCC-like Waste EIS-0375: Disposal of Greater-than-Class-C Low-Level Radioactive Waste and Department of Energy GTCC-like Waste Summary This EIS evaluates the reasonably foreseeable environmental impacts associated with the proposed development, operation, and long-term management of a disposal facility or facilities for Greater-Than-Class C (GTCC) low-level radioactive waste and GTCC-like waste. The Environmental Protection Agency is a cooperating agency in the preparation of this EIS. The EIS evaluates potential impacts from the construction and operation of

398

Life-Cycle Cost Study for a Low-Level Radioactive Waste Disposal Facility in Texas  

SciTech Connect (OSTI)

This report documents the life-cycle cost estimates for a proposed low-level radioactive waste disposal facility near Sierra Blanca, Texas. The work was requested by the Texas Low-Level Radioactive Waste Disposal Authority and performed by the National Low-Level Waste Management Program with the assistance of Rogers and Associates Engineering Corporation.

B. C. Rogers; P. L. Walter (Rogers and Associates Engineering Corporation); R. D. Baird

1999-08-01T23:59:59.000Z

399

Solid Waste Program Fiscal Year 1996 Multi-Year Program Plan WBS 1.2.1, Revision 1  

SciTech Connect (OSTI)

This document contains the Fiscal Year 1996 Multi-Year Program Plan for the Solid Waste Program at the Hanford Reservation in Richland, Washington. The Solid Waste Program treats, stores, and disposes of a wide variety of solid wastes consisting of radioactive, nonradioactive and hazardous material types. Solid waste types are typically classified as transuranic waste, low-level radioactive waste, low-level mixed waste, and non-radioactive hazardous waste. This report describes the mission, goals and program strategies for the Solid Waste Program for fiscal year 1996 and beyond.

NONE

1995-09-01T23:59:59.000Z

400

Deep borehole disposal of high-level radioactive waste.  

SciTech Connect (OSTI)

Preliminary evaluation of deep borehole disposal of high-level radioactive waste and spent nuclear fuel indicates the potential for excellent long-term safety performance at costs competitive with mined repositories. Significant fluid flow through basement rock is prevented, in part, by low permeabilities, poorly connected transport pathways, and overburden self-sealing. Deep fluids also resist vertical movement because they are density stratified. Thermal hydrologic calculations estimate the thermal pulse from emplaced waste to be small (less than 20 C at 10 meters from the borehole, for less than a few hundred years), and to result in maximum total vertical fluid movement of {approx}100 m. Reducing conditions will sharply limit solubilities of most dose-critical radionuclides at depth, and high ionic strengths of deep fluids will prevent colloidal transport. For the bounding analysis of this report, waste is envisioned to be emplaced as fuel assemblies stacked inside drill casing that are lowered, and emplaced using off-the-shelf oilfield and geothermal drilling techniques, into the lower 1-2 km portion of a vertical borehole {approx}45 cm in diameter and 3-5 km deep, followed by borehole sealing. Deep borehole disposal of radioactive waste in the United States would require modifications to the Nuclear Waste Policy Act and to applicable regulatory standards for long-term performance set by the US Environmental Protection Agency (40 CFR part 191) and US Nuclear Regulatory Commission (10 CFR part 60). The performance analysis described here is based on the assumption that long-term standards for deep borehole disposal would be identical in the key regards to those prescribed for existing repositories (40 CFR part 197 and 10 CFR part 63).

Stein, Joshua S.; Freeze, Geoffrey A.; Brady, Patrick Vane; Swift, Peter N.; Rechard, Robert Paul; Arnold, Bill Walter; Kanney, Joseph F.; Bauer, Stephen J.

2009-07-01T23:59:59.000Z

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


401

RSP WASTE UNIVERSITY OF HAWAII RADIOACTIVE WASTE PICKUP REQUEST FORM Revision 06/07 (WASTE WHICH CONTAINS RADIOISOTOPES BUT NO HAZARDOUS CHEMICALS)  

E-Print Network [OSTI]

RSP WASTE UNIVERSITY OF HAWAII RADIOACTIVE WASTE PICKUP REQUEST FORM Revision 06/07 (WASTE WHICH CONTAINS RADIOISOTOPES BUT NO HAZARDOUS CHEMICALS) INSTRUCTIONS : 1. *NO ISOTOPES MAY BE MIXED IN THE WASTE BOX! One type of isotope per waste box - Except C-14 AND H-3 WHICH MAY BE DISPOSED OF TOGETHER. 2

Browder, Tom

402

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

SciTech Connect (OSTI)

This report presents supplemental information to support the human health risk assessment conducted for the transportation of transuranic waste (TRUW) in support of the US Department of Energy Waste Management Programmatic Environmental Impact Statement (WM PEIS). Detailed descriptions of the transportation health risk assessment method and results of the assessment are presented in Appendix E of the WM PEIS and are not repeated in this report. This report presents additional information that is not presented in Appendix E but is necessary to conduct the transportation risk assessment for Waste Management (WM) contact- and remote-handed (CH and RH) TRUW. Included are definitions of the TRUW alternatives considered in the WM PEIS, data related to the inventory and to the physical and radiological characteristics of CH and RH TRUW, and detailed results of the assessment for each WM TRUW case considered.

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

1996-12-01T23:59:59.000Z

403

Disposing of nuclear waste in a salt bed  

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

Disposing of nuclear waste in a salt bed Disposing of nuclear waste in a salt bed 1663 Los Alamos science and technology magazine Latest Issue:November 2013 All Issues » submit Disposing of nuclear waste in a salt bed Decades' worth of transuranic waste from Los Alamos is being laid to rest at the Waste Isolation Pilot Plant in southeastern New Mexico March 25, 2013 Disposing of nuclear waste in a salt bed Depending on the impurities embedded within it, the salt from WIPP can be anything from a reddish, relatively opaque rock to a clear crystal like the one shown here. Ordinary salt effectively seals transuranic waste in a long-term repository Transuranic waste, made of items such as lab coats and equipment that have been contaminated by radioactive elements heavier than uranium, is being shipped from the Los Alamos National Laboratory to a long-term storage

404

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

Office of Legacy Management (LM)

Waste Isolation Pilot Plant - 019 Waste Isolation Pilot Plant - 019 FUSRAP Considered Sites Site: Waste Isolation Pilot Plant (019) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status: The Waste Isolation Pilot Plant, or WIPP, is the world¿s first underground repository licensed to safely and permanently dispose of transuranic radioactive waste left from the research and production of nuclear weapons. Transuranic waste consists primarily of clothing, tools, rags, and other disposable items contaminated with small amounts of radioactive elements, mostly plutonium. After more than 20 years of scientific study and public input, WIPP began operations on March 26, 1999. Located in the remote

405

REVISED INDEPENDENT VERIFICATION SURVEY OF A AND B RADIOACTIVE WASTE TRANSFER LINES TRENCH BROOKHAVEN NATIONAL LABORATORY  

SciTech Connect (OSTI)

REVISED INDEPENDENT VERIFICATION SURVEY OF THE A AND B RADIOACTIVE WASTE TRANSFER LINES TRENCH, BROOKHAVEN NATIONAL LABORATORY 5062-SR-01-1

P.C. Weaver

2010-02-10T23:59:59.000Z

406

Rules and Regulations for the Disposal of Low-Level Radioactive Waste (Nebraska)  

Broader source: Energy.gov [DOE]

These regulations, promulgated by the Department of Environmental Quality, contain provisions pertaining to the disposal of low-level radioactive waste, disposal facilities, and applicable fees.

407

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

E-Print Network [OSTI]

??The radioactive waste classification system currently used in the United States primarily relies on a source-based framework. This has lead to numerous issues, such as (more)

Djokic, Denia

2013-01-01T23:59:59.000Z

408

Southeast Interstate Low-Level Radioactive Waste Management Compact (multi-state)  

Broader source: Energy.gov [DOE]

The Southeast Interstate Low-Level Radioactive Waste Management Compact is administered by the Compact Commission. The Compact provides for rotating responsibility for the region's low-level...

409

Report to Congress: 1995 Annual report on low-level radioactive waste management progress  

SciTech Connect (OSTI)

This report is prepared in response to the Low-Level Radioactive Waste Policy Act, Public Law 96-573, 1980, as amended by the Low-Level Radioactive Waste Policy Amendments Act of 1985, Public Law 99-240. The report summarizes the progress of states and compact regions during calendar year 1995 in establishing new disposal facilities for commercially-generated low-level radioactive waste. The report emphasizes significant issues and events that have affected progress, and also includes an introduction that provides background information and perspective on United States policy for low-level radioactive waste disposal.

NONE

1996-06-01T23:59:59.000Z

410

1996 annual report on low-level radioactive waste management progress. Report to Congress  

SciTech Connect (OSTI)

This report is prepared in response to the Low-Level Radioactive Waste Policy Act (the Act), Public Law 96-573, 1980, as amended by the Low-Level Radioactive Waste Policy Amendments Act of 1985, Public Law 99-240. The report summarizes the activities during calendar year 1996 related to the establishment of new disposal facilities for commercially-generated low-level radioactive waste. The report emphasizes significant issues and events that have affected progress in developing new disposal facilities, and also includes an introduction that provides background information and perspective on US policy for low-level radioactive waste disposal.

NONE

1997-11-01T23:59:59.000Z

411

Office of Civilian Radioactive Waste Management Transportation Program: Tribal Initiatives  

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

COMMUNICATIONS BREAKOUT COMMUNICATIONS BREAKOUT SESSION Jay Jones Office of Civilian Radioactive Waste Management April 22, 2004 Albuquerque, New Mexico 2 Session Overview * Meeting objectives and expectations * Topic Group Background and History * Transportation information products - Information Product Survey results - Alliance for Transportation Research Institute Assessments * Discussion on future DOE communications * Information Display 3 Objectives and Expectations * OCRWM communications approach - Transportation Strategic Plan Collaborative effort with stakeholders Two-way interactions with program participants and public - provide information and receive feedback * Implement communications strategy - Identify stakeholders and issues - Engage nationally, regionally and with States - Participate through discussion and issue resolution

412

Naturally occurring crystalline phases: analogues for radioactive waste forms  

SciTech Connect (OSTI)

Naturally occurring mineral analogues to crystalline phases that are constituents of crystalline radioactive waste forms provide a basis for comparison by which the long-term stability of these phases may be estimated. The crystal structures and the crystal chemistry of the following natural analogues are presented: baddeleyite, hematite, nepheline; pollucite, scheelite;sodalite, spinel, apatite, monazite, uraninite, hollandite-priderite, perovskite, and zirconolite. For each phase in geochemistry, occurrence, alteration and radiation effects are described. A selected bibliography for each phase is included.

Haaker, R.F.; Ewing, R.C.

1981-01-01T23:59:59.000Z

413

Evaluation of Incident Risks in a Repository for Radioactive Waste  

SciTech Connect (OSTI)

A probabilistic safety assessment of the operation phase of a repository for radioactive waste requires the knowledge of incident risks. These are evaluated from generic observations. The present method accounts for the uncertainty (1) of whether an incident occurs, (2) of the incident rate, (3) of the duration of generic observation, and (4) of the duration of operation phase of the repository. It yields a mean risk and its standard deviation from a minimum of generic data, comprising only the number of observed incidents and the duration of the observation, as more comprehensive generic data are seldom available. It was shown that incidents sharing a common generic observation must be either merged together to a total incident or the generic observation must be split up in sub-observations, one for each such incident. The method was tested on the example of the German Konrad repository for low-level waste in a deep geological formation. (authors)

Grundler, D.; Mariae, D.; Muller, W.; Boetsch, W. [Institut fur Sicherheitstechnologie (ISTec), Koln (Germany); Thiel, J. [Bundesamt fur Strahlenschutz (BfS), Salzgitter (Germany)

2008-07-01T23:59:59.000Z

414

Midwestern High-Level Radioactive Waste Transportation Project  

SciTech Connect (OSTI)

For more than half a century, the Council of State Governments has served as a common ground for the states of the nation. The Council is a nonprofit, state-supported and -directed service organization that provides research and resources, identifies trends, supplies answers and creates a network for legislative, executive and judicial branch representatives. This List of Available Resources was prepared with the support of the US Department of Energy, Cooperative Agreement No. DE-FC02-89CH10402. However, any opinions, findings, conclusions, or recommendations expressed herein are those of the author(s) and do not necessarily reflect the views of DOE. The purpose of the agreement, and reports issued pursuant to it, is to identify and analyze regional issues pertaining to the transportation of high-level radioactive waste and to inform Midwestern state officials with respect to technical issues and regulatory concerns related to waste transportation.

Dantoin, T.S.

1990-12-01T23:59:59.000Z

415

Finding of no significant impact for the interim action for cleanup of Pit 9 at the Radioactive Waste Management Complex, Idaho National Engineering Laboratory  

SciTech Connect (OSTI)

The Department of Energy (DOE) has prepared an environmental assessment (EA), DOE/EA-0854, for an interim action under the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA). The proposed action would be conducted at Pit 9, Operable Unit 7--10, located at the Subsurface Disposal Area (SDA) of the Radioactive Waste Management Complex (RWMC) at the Idaho National Engineering Laboratory (INEL). The proposed action consists of construction of retrieval and processing buildings, excavation and retrieval of wastes from Pit 9, selective physical separation and chemical extraction, and stabilization of wastes either through thermal processing or by forming a stabilized concentrate. The proposed action would involve limited waste treatment process testing and full-scale waste treatment processing for cleaning up pre-1970 Transuranic (TRU) wastes in Pit 9. The purpose of this interim action is to expedite the overall cleanup at the RWMC and to reduce the risks associated with potential migration of Pit 9 wastes to the Snake River Plain Aquifer.

Not Available

1993-10-01T23:59:59.000Z

416

EA-1061: The Off-site Volume Reduction of Low-level Radioactive Waste From  

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

1: The Off-site Volume Reduction of Low-level Radioactive 1: The Off-site Volume Reduction of Low-level Radioactive Waste From the Savannah River Site, Aiken, South Carolina EA-1061: The Off-site Volume Reduction of Low-level Radioactive Waste From the Savannah River Site, Aiken, South Carolina SUMMARY This EA evaluates the environmental impacts of the proposal for off-site volume reduction of low-level radioactive wastes generated at the U.S. Department of Energy's Savannah River Site located near Aiken, South Carolina. PUBLIC COMMENT OPPORTUNITIES None available at this time. DOCUMENTS AVAILABLE FOR DOWNLOAD July 28, 1995 EA-1061: Finding of No Significant Impact The Off-site Volume Reduction of Low-level Radioactive Waste From the Savannah River Site July 28, 1995 EA-1061: Final Environmental Assessment The Off-site Volume Reduction of Low-level Radioactive Waste From the

417

1989 Annual report on low-level radioactive waste management progress  

SciTech Connect (OSTI)

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

418

Transuranic waste inventory, characteristics, generation, and facility assessment for treatment, storage, and disposal alternatives considered in the U.S. Department of Energy Waste Management Programmatic Environmental Impact Statement  

SciTech Connect (OSTI)

Transuranic waste (TRUW) loads and potential contaminant releases at and en route to treatment, storage, and disposal sites in the US Department of Energy (DOE) complex are important considerations in DOE`s Waste Management Programmatic Environmental Impact Statement (WM PEIS). Waste loads are determined in part by the level of treatment the waste has undergone and the complex-wide configuration of origination, treatment, storage, and disposal sites selected for TRUW management. Other elements that impact waste loads are treatment volumes, waste characteristics, and the unit operation parameters of the treatment technologies. Treatment levels and site configurations have been combined into six TRUW management alternatives for study in the WM PEIS. This supplemental report to the WM PEIS gives the projected waste loads and contaminant release profiles for DOE treatment sites under each of the six TRUW management alternatives. It gives TRUW characteristics and inventories for current DOE generation and storage sites, describes the treatment technologies for three proposed levels of TRUW treatment, and presents the representative unit operation parameters of the treatment technologies. The data presented are primary inputs to developing the costs, health risks, and socioeconomic and environmental impacts of treating, packaging, and shipping TRUW for disposal.

Hong, K.; Kotek, T.; Folga, S.; Koebnick, B.; Wang, Y.; Kaicher, C.

1996-12-01T23:59:59.000Z

419

Management of low-level radioactive wastes around the world  

SciTech Connect (OSTI)

This paper reviews the status of various practices used throughout the world for managing low-level radioactive wastes. Most of the information in this review was obtained through the DOE-sponsored International Program Support Office (IPSO) activities at Pacific Northwest Laboratory (PNL) at Richland, Washington. The objective of IPSO is to collect, evaluate, and disseminate information on international waste management and nuclear fuel cycle activities. The center's sources of information vary widely and include the proceedings of international symposia, papers presented at technical society meetings, published topical reports, foreign trip reports, and the news media. Periodically, the information is published in topical reports. Much of the information contained in this report was presented at the Fifth Annual Participants' Information Meeting sponsored by DOE's Low-Level Waste Management Program Office at Denver, Colorado, in September of 1983. Subsequent to that presentation, the information has been updated, particularly with information provided by Dr. P. Colombo of Brookhaven National Laboratory who corresponded with low-level waste management specialists in many countries. The practices reviewed in this paper generally represent actual operations. However, major R and D activities, along with future plans, are also discussed. 98 refs., 6 tabls.

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

1985-04-01T23:59:59.000Z

420

Office of Civilian Radioactive Waste Management annual report to Congress  

SciTech Connect (OSTI)

This is the fifth Annual Report to Congress by the Office of Civilian Radioactive Waste Management (OCRWM). The report covers the activities and expenditures of OCRWM during fiscal year 1987, which ended on September 30, 1987. The activities and accomplishments of OCRWM during fiscal year 1987 are discussed in chapters 1 through 9 of this report. The audited financial statements of the Nuclear Waste Fund are provided in chapter 10. Since the close of the fiscal year, a number of significant events have occurred. Foremost among them was the passage of the Nuclear Waste Policy Amendments Act of 1987 (Amendments Act) on December 21, 1987, nearly 3 months after the end of the fiscal year covered by this report. As a result, some of the plans and activities discussed in chapters 1 through 9 are currently undergoing significant change or are being discontinued. Most prominent among the provisions of the Amendments Act is the designation of Yucca Mountain, Nevada, as the only candidate first repository site to be characterized. Therefore, the site characterization plans for Deaf Smith, Texas, and Hanford, Washington, discussed in chapter 3, will not be issued. The refocusing of the waste management program under the Amendments Act is highlighted in the epilogue, chapter 11. 68 refs., 7 figs., 7 tabs.

NONE

1988-08-01T23:59:59.000Z

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


421

Microbial degradation of low-level radioactive waste. Final report  

SciTech Connect (OSTI)

The Nuclear Regulatory Commission stipulates in 10 CFR 61 that disposed low-level radioactive waste (LLW) be stabilized. To provide guidance to disposal vendors and nuclear station waste generators for implementing those requirements, the NRC developed the Technical Position on Waste Form, Revision 1. That document details a specified set of recommended testing procedures and criteria, including several tests for determining the biodegradation properties of waste forms. Information has been presented by a number of researchers, which indicated that those tests may be inappropriate for examining microbial degradation of cement-solidified LLW. Cement has been widely used to solidify LLW; however, the resulting waste forms are sometimes susceptible to failure due to the actions of waste constituents, stress, and environment. The purpose of this research program was to develop modified microbial degradation test procedures that would be more appropriate than the existing procedures for evaluation of the effects of microbiologically influenced chemical attack on cement-solidified LLW. The procedures that have been developed in this work are presented and discussed. Groups of microorganisms indigenous to LLW disposal sites were employed that can metabolically convert organic and inorganic substrates into organic and mineral acids. Such acids aggressively react with cement and can ultimately lead to structural failure. Results on the application of mechanisms inherent in microbially influenced degradation of cement-based material are the focus of this final report. Data-validated evidence of the potential for microbially influenced deterioration of cement-solidified LLW and subsequent release of radionuclides developed during this study are presented.

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

1996-06-01T23:59:59.000Z

422

Revision 08 (08/10) Form G Radioactive Waste Disposal Form  

E-Print Network [OSTI]

Revision 08 (08/10) Form G Radioactive Waste Disposal Form RS - 19g Proc. 9290, 9501 General Instructions: 1. Do not mix different waste forms together. Keep dry, liquid, and scintillation vials separate. 2. Do not mix waste of different isotopes. 3. Entries are to be made on this form each time waste

Nair, Sankar

423

Geological problems in radioactive waste isolation - A world wide review  

SciTech Connect (OSTI)

The problem of isolating radioactive wastes from the biosphere presents specialists in the earth sciences with some of the most complicated problems they have ever encountered. This is especially true for high-level waste (HLW), which must be isolated in the underground and away from the biosphere for thousands of years. The most widely accepted method of doing this is to seal the radioactive materials in metal canisters that are enclosed by a protective sheath and placed underground in a repository that has been carefully constructed in an appropriate rock formation. Much new technology is being developed to solve the problems that have been raised, and there is a continuing need to publish the results of new developments for the benefit of all concerned. Table 1 presents a summary of the various formations under investigation according to the reports submitted for this world wide review. It can be seen that in those countries that are searching for repository sites, granitic and metamorphic rocks are the prevalent rock type under investigation. Six countries have developed underground research facilities that are currently in use. All of these investigations are in saturated systems below the water table, except the United States project, which is in the unsaturated zone of a fractured tuff.

Witherspoon, P.A. [Lawrence Berkeley Lab., CA (United States)

1991-06-01T23:59:59.000Z

424

Program integration on the Civilian Radioactive Waste Management System  

SciTech Connect (OSTI)

The recent development and implementation of a revised Program Approach for the Civilian Radioactive Waste Management System (CRWMS) was accomplished in response to significant changes in the environment in which the program was being executed. The lack of an interim storage site, growing costs and schedule delays to accomplish the full Yucca Mountain site characterization plan, and the development and incorporation of a multi-purpose (storage, transport, and disposal) canister (MPC) into the CRWMS required a reexamination of Program plans and priorities. Dr. Daniel A. Dreyfus, the Director of the Office of Civilian Radioactive Waste Management (OCRWM), established top-level schedule, targets and cost goals and commissioned a Program-wide task force of DOE and contractor personnel to identify and evaluate alternatives to meet them. The evaluation of the suitability of Yucca Mountain site by 1998 and the repository license application data of 2001 were maintained and a target date of January 1998 for MPC availability was established. An increased multi-year funding profile was baselined and agreed to by Congress. A $1.3 billion reduction in Yucca Mountain site characterization costs was mandated to hold the cost to $5 billion. The replanning process superseded all previous budget allocations and focused on program requirements and their relative priorities within the cost profiles. This paper discusses the process for defining alternative scenarios to achieve the top-level program goals in an integrated fashion.

Trebules, V.B. [USDOE Office of Civilian Radioactive Waste Management, Washington, DC (United States). Program Management Div.; King, M.H. [TRW Environmental Safety Systems Inc., Vienna, VA (United States)

1995-09-01T23:59:59.000Z

425

LANL sets TRU waste hauling record  

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

sets TRU waste hauling record sets TRU waste hauling record LANL sets TRU waste hauling record TRU waste consists of clothing, tools, rags, debris, soil, and other items contaminated with radioactive elements, mostly plutonium. October 4, 2011 TRU waste from LANL to WIPP TRU waste from LANL to WIPP Contact Colleen Curran Communications Office (505) 664-0344 Email LOS ALAMOS, New Mexico, October 4, 2011-Los Alamos National Laboratory has set a new LANL record for the amount of transuranic (TRU) waste from past nuclearoperations shipped in a single year to the U.S. Department of Energy's Waste Isolation Pilot Plant (WIPP) near Carlsbad, NM. In fact, the Laboratory has shipped record numbers of transuranic waste each of the past three years. The Laboratory's TRU Waste Program completed 171 shipments in the past

426

Directions in low-level radioactive waste management. Low-level radioactive waste disposal: commercial facilities no longer operating  

SciTech Connect (OSTI)

This publication discusses three commercial facilities-no longer operating-that have received and now contain low-level radioactive waste. The facilities are located at West Valley, New York; Maxey Flats, Kentucky; and Sheffield, Illinois. All three of the facilities were selected and developed in the 1960s. The onset of water management problems caused the closure of the sites at West Valley and Maxey Flats in 1975 and 1977, respectively. Closure of the Sheffield site occurred in 1978, after the operator experienced site problems and consequent lengthy delays in its license renewal procedures. The document provides detailed explanation of the history, basis for closure, and current status of each facility. This information is intended, primarily, to assist state officials-executive, legislative, and agency-in planning for, establishing, and managing low-level waste disposal facilities.

Berlin, R.E.; Tuite, P.T.

1982-10-01T23:59:59.000Z

427

Nevada Waste Leaves Idaho Facility  

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

Media Contacts: Media Contacts: Danielle Miller, 208-526-5709 Brad Bugger, 208-526-0833 For Immediate Release: Date: March 02, 2010 Nevada Waste Leaves Idaho Facility (Note: This is a reissue of a press release originally sent last week to ensure all intended recipients receive a copy after technical glitch may have kept it from reaching some of them) It may have looked like just another shipment of transuranic radioactive waste leaving Idaho, but the shipment heading south on U.S. Interstate 15 the afternoon of January 26 actually contained waste from another DOE site in Nevada. The shipment demonstrated the capacity of the U.S. Department of Energy�s Advanced Mixed Waste Treatment Project to be a hub where the Department�s transuranic radioactive waste can be safely and compliantly