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Sample records for legacy tru waste

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

    SciTech Connect (OSTI)

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

    2003-02-25

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

  2. Legacy Waste | Department of Energy

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

    Services » Legacy Waste Legacy Waste Legacy Waste The Environmental Management Los Alamos Field Office's (EM-LA) Solid Waste Stabilization and Disposition Project Team is dedicated to packaging, shipping and disposing legacy waste - low-level, mixed low-level, and transuranic (TRU) waste - from Los Alamos National Laboratory (LANL). The most challenging legacy waste at LANL is TRU, which is currently stored at Area G, located on a mesa 1.3 miles north of the residential community of White Rock

  3. DOE Achieves Second TRU Waste Cleanup

    Broader source: Energy.gov [DOE]

    CARLSBAD, N.M. –The U.S. Department of Energy has successfully removed all legacy contact-handled transuranic (TRU) waste from the Argonne National Laboratory (ANL), near Chicago, Illinois. In September, all legacy TRU waste was removed from the Bettis Atomic Power Laboratory (BAPL), near Pittsburgh, Pennsylvania.

  4. 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.

  5. DOE Completes TRU Waste Cleanup at Bettis

    Broader source: Energy.gov [DOE]

    CARLSBAD, N.M.– The U.S. Department of Energy (DOE) has successfully completed cleanup of all Cold War legacy transuranic (TRU) waste at the Bettis Atomic Power Laboratory (BAPL) near Pittsburgh, Pa., permanently disposing of it at the Waste Isolation Pilot Plant (WIPP).

  6. Progress Update: TRU Waste Shipping

    ScienceCinema (OSTI)

    Cody, Tom

    2012-06-14

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

  7. LANL sets TRU waste hauling record

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

    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

  8. On Going TRU Waste Disposition

    ScienceCinema (OSTI)

    Cody, Tom

    2012-06-14

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

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

    Broader source: Energy.gov [DOE]

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

  10. Transuranic (TRU) Waste | Department of Energy

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

    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 transuranic isotopes per gram of waste with half-lives greater than 20 years, except for (A) high-level radioactive waste, (B) waste that the Secretary of Energy has determined, with concurrence of the Administrator of the Environmental Protection Agency, does not need the degree of isolation required by the disposal

  11. Contents TRU Waste Celebration

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

    waste drums stored at the NTS for 30 years." , assistant general manager for ... achieved in experiments conducted three years ago at Los Alamos National Laboratory ...

  12. Los Alamos National Laboratory TRU Waste Update | Department of Energy

    Office of Environmental Management (EM)

    TRU Waste Update Los Alamos National Laboratory TRU Waste Update Topic: David Nickless presented the members with information on the status of the remaining transuranic waste at Los Alamos National Laboratory. PDF icon TRU Waste Update - July 29, 2015

  13. Hanford Site Transuranic (TRU) Waste Certification Plan

    SciTech Connect (OSTI)

    GREAGER, T.M.

    2000-12-06

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

  14. Hanford Site Transuranic (TRU) Waste Certification Plan

    SciTech Connect (OSTI)

    GREAGER, T.M.

    2000-12-01

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

  15. CALORIMETRY OF TRU WASTE MATERIALS

    SciTech Connect (OSTI)

    C. RUDY; ET AL

    2000-08-01

    Calorimetry has been used for accountability measurements of nuclear material in the US. Its high accuracy, insensitivity to matrix effects, and measurement traceability to National Institute of Standards and Technology have made it the primary accountability assay technique for plutonium (Pu) and tritium in the Department of Energy complex. A measurement of Pu isotopic composition by gamma-ray spectroscopy is required to transform the calorimeter measurement into grams Pu. The favorable calorimetry attributes allow it to be used for verification measurements, for production of secondary standards, for bias correction of other faster nondestructive (NDA) methods, or to resolve anomalous measurement results. Presented in this paper are (1) a brief overview of calorimeter advantages and disadvantages, (2) a description of projected large volume calorimeters suitable for waste measurements, and (3) a new technique, direct measurement of transuranic TRU waste alpha-decay activity through calorimetry alone.

  16. Hanford Site Transuranic (TRU) Waste Certification Plan

    SciTech Connect (OSTI)

    GREAGER, T.M.

    1999-12-14

    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.

  17. Hanford Site Transuranic (TRU) Waste Certification Plan

    SciTech Connect (OSTI)

    GREAGER, T.M.

    1999-09-09

    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.

  18. TRU waste from the Superblock

    SciTech Connect (OSTI)

    Coburn, T.T.

    1997-05-27

    This data analysis is to show that weapons grade plutonium is of uniform composition to the standards set by the Waste-Isolation Pilot Plant (WIPP) Transuranic Waste Characterization Quality Assurance Program Plan (TRUW Characterization QAPP, Rev. 2, DOE, Carlsbad Area Office, November 15, 1996). The major portion of Superblock transuranic (TRU) waste is glove-box trash contaminated with weapons grade plutonium. This waste originates in the Building 332 (B332) radioactive-materials area (RMA). Because each plutonium batch brought into the B332 RMA is well characterized with regard to nature and quantity of transuranic nuclides present, waste also will be well characterized without further analytical work, provided the batches are quite similar. A sample data set was created by examining the 41 incoming samples analyzed by Ken Raschke (using a {gamma}-ray spectrometer) for isotopic distribution and by Ted Midtaune (using a calorimeter) for mass of radionuclides. The 41 samples were from separate batches analyzed May 1993 through January 1997. All available weapons grade plutonium data in Midtaune's files were used. Alloys having greater than 50% transuranic material were included. The intention of this study is to use this sample data set to judge ''similarity.''

  19. RH-TRU Waste Content Codes

    SciTech Connect (OSTI)

    Washington TRU Solutions

    2007-07-01

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

  20. Transuranic (TRU) Waste Phase I Retrieval Plan

    SciTech Connect (OSTI)

    MCDONALD, K.M.

    2000-09-28

    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.

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

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

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

  2. Repackaging Rocky Flats Legacy Transuranic Waste

    SciTech Connect (OSTI)

    McTaggart, Jerri Lynne

    2008-01-15

    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.

  3. Transuranic (TRU) Waste Phase I Retrieval Plan

    SciTech Connect (OSTI)

    MCDONALD, K.M.

    1999-08-27

    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.

  4. Neutron multiplication error in TRU waste measurements

    SciTech Connect (OSTI)

    Veilleux, John [Los Alamos National Laboratory; Stanfield, Sean B [CCP; Wachter, Joe [CCP; Ceo, Bob [CCP

    2009-01-01

    Total Measurement Uncertainty (TMU) in neutron assays of transuranic waste (TRU) are comprised of several components including counting statistics, matrix and source distribution, calibration inaccuracy, background effects, and neutron multiplication error. While a minor component for low plutonium masses, neutron multiplication error is often the major contributor to the TMU for items containing more than 140 g of weapons grade plutonium. Neutron multiplication arises when neutrons from spontaneous fission and other nuclear events induce fissions in other fissile isotopes in the waste, thereby multiplying the overall coincidence neutron response in passive neutron measurements. Since passive neutron counters cannot differentiate between spontaneous and induced fission neutrons, multiplication can lead to positive bias in the measurements. Although neutron multiplication can only result in a positive bias, it has, for the purpose of mathematical simplicity, generally been treated as an error that can lead to either a positive or negative result in the TMU. While the factors that contribute to neutron multiplication include the total mass of fissile nuclides, the presence of moderating material in the matrix, the concentration and geometry of the fissile sources, and other factors; measurement uncertainty is generally determined as a function of the fissile mass in most TMU software calculations because this is the only quantity determined by the passive neutron measurement. Neutron multiplication error has a particularly pernicious consequence for TRU waste analysis because the measured Fissile Gram Equivalent (FGE) plus twice the TMU error must be less than 200 for TRU waste packaged in 55-gal drums and less than 325 for boxed waste. For this reason, large errors due to neutron multiplication can lead to increased rejections of TRU waste containers. This report will attempt to better define the error term due to neutron multiplication and arrive at values that are more realistic and accurate. To do so, measurements of standards and waste drums were performed with High Efficiency Neutron Counters (HENC) located at Los Alamos National Laboratory (LANL). The data were analyzed for multiplication effects and new estimates of the multiplication error were computed. A concluding section will present alternatives for reducing the number of rejections of TRU waste containers due to neutron multiplication error.

  5. CH-TRU Waste Content Codes

    SciTech Connect (OSTI)

    Washington TRU Solutions LLC

    2008-01-16

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

  6. Retrieval and Repackaging of RH-TRU Waste - General Presentation...

    Office of Environmental Management (EM)

    Retrieval and Repackaging of RH-TRU Waste- GENERAL PRESENTATION MODULAR HOT CELL TECHNOLOGY AREVA FEDERAL SERVICES - OAK RIDGE, TN - GENERAL PRESENTATION OF MODULAR HOT CELL ...

  7. TRU waste transportation -- The flammable gas generation problem

    SciTech Connect (OSTI)

    Connolly, M.J.; Kosiewicz, S.T.

    1997-11-01

    The Nuclear Regulatory Commission (NRC) has imposed a flammable gas (i.e., hydrogen) concentration limit of 5% by volume on transuranic (TRU) waste containers to be shipped using the TRUPACT-II transporter. This concentration is the lower explosive limit (LEL) in air. This was done to minimize the potential for loss of containment during a hypothetical 60 day period. The amount of transuranic radionuclide that is permissible for shipment in TRU waste containers has been tabulated in the TRUPACT-II Safety Analysis Report for Packaging (SARP, 1) to conservatively prevent accumulation of hydrogen above this 5% limit. Based on the SARP limitations, approximately 35% of the TRU waste stored at the Idaho National Engineering and Environmental Lab (INEEL), Los Alamos National Lab (LANL), and Rocky Flats Environmental Technology Site (RFETS) cannot be shipped in the TRUPACT-II. An even larger percentage of the TRU waste drums at the Savannah River Site (SRS) cannot be shipped because of the much higher wattage loadings of TRU waste drums in that site`s inventory. This paper presents an overview of an integrated, experimental program that has been initiated to increase the shippable portion of the Department of Energy (DOE) TRU waste inventory. In addition, the authors will estimate the anticipated expansion of the shippable portion of the inventory and associated cost savings. Such projection should provide the TRU waste generating sites a basis for developing their TRU waste workoff strategies within their Ten Year Plan budget horizons.

  8. DOE Reaches Recovery Act Goal With Cleanup of All Legacy Transuranic Waste at Sandia National Laboratories

    Broader source: Energy.gov [DOE]

    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.

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

    SciTech Connect (OSTI)

    GREAGER, T.M.

    2000-12-06

    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.

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

    SciTech Connect (OSTI)

    Hayes, Timothy; Nelson, Roger

    2012-07-01

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

  11. Transuranic (TRU) Waste Repackaging at the Nevada Test Site

    SciTech Connect (OSTI)

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

    2009-03-01

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

  12. Los Alamos National Laboratory TRU waste sampling projects

    SciTech Connect (OSTI)

    Yeamans, D.; Rogers, P.; Mroz, E.

    1997-02-01

    The Los Alamos National Laboratory (LANL) has begun characterizing transuranic (TRU) waste in order to comply with New Mexico regulations, and to prepare the waste for shipment and disposal at the Waste Isolation Pilot Plant (WIPP), near Carlsbad, New Mexico. Sampling consists of removing some head space gas from each drum, removing a core from a few drums of each homogeneous waste stream, and visually characterizing a few drums from each heterogeneous waste stream. The gases are analyzed by GC/MS, and the cores are analyzed for VOC`s and SVOC`s by GC/MS and for metals by AA or AE spectroscopy. The sampling and examination projects are conducted in accordance with the ``DOE TRU Waste Quality Assurance Program Plan`` (QAPP) and the ``LANL TRU Waste Quality Assurance Project Plan,`` (QAPjP), guaranteeing that the data meet the needs of both the Carlsbad Area Office (CAO) of DOE and the ``WIPP Waste Acceptance Criteria, Rev. 5,`` (WAC).

  13. Preparation of Safety Basis Documents for Transuranic (TRU) Waste...

    Office of Environmental Management (EM)

    ... and Fire C-1 D Criteria for TRU Waste Drums Requiring Venting... ranging from very low radioactive levels to ... These topics are addressed in a level of detail that ...

  14. Oak Ridge National Laboratory TRU Waste Processing Center Tank...

    Office of Environmental Management (EM)

    ... BVEST W-Tank System Control Trailer Off-Gas Skid Pipe bridge Jet Pump Skid Charge Vessels W-21 W-22 W-23 Valve Skid SL Mobilization ORNL TRU Waste Processing Center Questions 242 A ...

  15. Occurrence Reporting and Processing System (ORPS) - PISA: TRU Waste Drums

    Energy Savers [EERE]

    Containing Treated Nitrate Salts May Challenge the Safety Analysis | Department of Energy Occurrence Reporting and Processing System (ORPS) - PISA: TRU Waste Drums Containing Treated Nitrate Salts May Challenge the Safety Analysis Occurrence Reporting and Processing System (ORPS) - PISA: TRU Waste Drums Containing Treated Nitrate Salts May Challenge the Safety Analysis The documents included in this listing are additional references not included in the Phase 2 Radiological Release at the

  16. DOE ACHIEVES MAJOR COLD WAR LEGACY WASTE CLEANUP MILESTONE: Waste Isolation Pilot Plant Receives 10,000th Shipment

    Broader source: Energy.gov [DOE]

    CARLSBAD, N.M. – The Waste Isolation Pilot Plant (WIPP) received its 10,000th shipment of transuranic (TRU) waste on Sept. 24, 2011. This marked an important milestone in the DOE Office of Environmental Management mission to clean up the country’s Cold War legacy.

  17. Characterizing cemented TRU waste for RCRA hazardous constituents

    SciTech Connect (OSTI)

    Yeamans, D.R.; Betts, S.E.; Bodenstein, S.A. [and others

    1996-06-01

    Los Alamos National Laboratory (LANL) has characterized drums of solidified transuranic (TRU) waste from four major waste streams. The data will help the State of New Mexico determine whether or not to issue a no-migration variance of the Waste Isolation Pilot Plant (WIPP) so that WIPP can receive and dispose of waste. The need to characterize TRU waste stored at LANL is driven by two additional factors: (1) the LANL RCRA Waste Analysis Plan for EPA compliant safe storage of hazardous waste; (2) the WIPP Waste Acceptance Criteria (WAC) The LANL characterization program includes headspace gas analysis, radioassay and radiography for all drums and solids sampling on a random selection of drums from each waste stream. Data are presented showing that the only identified non-metal RCRA hazardous component of the waste is methanol.

  18. The Advantages of Fixed Facilities in Characterizing TRU Wastes

    SciTech Connect (OSTI)

    FRENCH, M.S.

    2000-02-08

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

  19. RH-TRU Waste Content Codes (RH-TRUCON)

    SciTech Connect (OSTI)

    Washington TRU Solutions LLC

    2007-08-01

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

  20. RH-TRU Waste Content Codes (RH TRUCON)

    SciTech Connect (OSTI)

    Washington TRU Solutions

    2007-05-01

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

  1. The Department of Energy Announces Major Cold War Legacy Waste Cleanup

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

    Milestone | Department of Energy The Department of Energy Announces Major Cold War Legacy Waste Cleanup Milestone The Department of Energy Announces Major Cold War Legacy Waste Cleanup Milestone September 28, 2011 - 8:54am Addthis CARLSBAD, NM - The U.S. Department of Energy today announced that the Waste Isolation Pilot Plant (WIPP) received its 10,000th shipment of transuranic (TRU) waste over the weekend. This marks an important milestone in DOE's mission to clean up the country's Cold

  2. 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.

  3. Test Plan: WIPP bin-scale CH TRU waste tests

    SciTech Connect (OSTI)

    Molecke, M.A.

    1990-08-01

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

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

    SciTech Connect (OSTI)

    Oakley, Brian; Heacker, Fred; McMillan, Bill

    2013-07-01

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

  5. Transuranic (TRU) Waste | Department of Energy

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

    Defined by the WIPP Land Withdrawal Act as "waste containing more than 100 nanocuries of alpha-emitting transuranic isotopes per gram of waste with half-lives greater than 20 ...

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

    SciTech Connect (OSTI)

    Mctaggert, Jerri Lynne; Lott, Sheila; Gadbury, Casey

    2009-01-01

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

  7. IPP RH-TRU Waste Study - Summary

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

    Summary This study was prepared by the Department in fulfillment of a congressional mandate specified in Public Law 102-579, referred to as the Waste Isolation Pilot Plant Land Withdrawal Act. In addition, the Department considers the preparation of the study to be a prudent element in the compliance certification process for the Waste Isolation Pilot Plant (WIPP). The study includes an analysis of the impact of remote-handled Transuranic waste on the performance assessment of the WIPP and a

  8. Los Alamos National Laboratory TRU Waste Status

    Broader source: Energy.gov [DOE]

    At the July 9, 2014 Committee meeting Lee Bishop DOE, Provided Information on the 3706 Campaign and Nitrate Salt Waste Storage at LANL. Information on the Administrative Order Issued by the New Mexico Environment Department was also Discussed.

  9. TRU Waste Management Program. Cost/schedule optimization analysis

    SciTech Connect (OSTI)

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

    1985-10-01

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

  10. Expert System for Building TRU Waste Payloads - 13554

    SciTech Connect (OSTI)

    Bruemmer, Heather; Slater, Bryant

    2013-07-01

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

  11. Environmental and Waste Management (WMO) Legacy TRU Waste Pause |

    Office of Environmental Management (EM)

    Environmental Risk Assessment Environmental Risk Assessment PPPO subject-matter experts analyze possible environmental hazards and provide risk assessment information to help inform various environmental decision-making processes. In doing so, the office consistently tracks its ongoing and projected Environmental Assessments and Environmental Impact Statements. To address CERCLA requirements, numerous risk-related activities include (but are not limited to) input to and quality assurance of

  12. CH-TRU Waste Content Codes (CH-TRUCON)

    SciTech Connect (OSTI)

    Washington TRU Solutions LLC

    2004-10-01

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

  13. CH-TRU Waste Content Codes (CH TRUCON)

    SciTech Connect (OSTI)

    Washington TRU Solutions LLC

    2004-12-01

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

  14. CH-TRU Waste Content Codes (CH-TRUCON)

    SciTech Connect (OSTI)

    Washington TRU Solutions LLC

    2006-12-20

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

  15. CH-TRU Waste Content Codes (CH-TRUCON)

    SciTech Connect (OSTI)

    Washington TRU Solutions LLC

    2006-06-20

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

  16. CH-TRU Waste Content Codes (CH-TRUCON)

    SciTech Connect (OSTI)

    Washington TRU Solutions LLC

    2006-08-15

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

  17. CH-TRU Waste Content Codes (CH-TRUCON)

    SciTech Connect (OSTI)

    Washington TRU Solutions LLC

    2006-01-18

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

  18. CH-TRU Waste Content Codes (CH-TRUCON)

    SciTech Connect (OSTI)

    Washington TRU Solutions LLC

    2007-02-15

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

  19. CH-TRU Waste Content Codes (CH-TRUCON)

    SciTech Connect (OSTI)

    Washington TRU Solutions LLC

    2007-06-15

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

  20. CH-TRU Waste Content Codes (CH-TRUCON)

    SciTech Connect (OSTI)

    Washington TRU Solutions LLC

    2007-08-15

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

  1. CH-TRU Waste Content Codes (CH-TRUCON)

    SciTech Connect (OSTI)

    Washington TRU Solutions LLC

    2007-09-20

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

  2. CH-TRU Waste Content Codes (CH-TRUCON)

    SciTech Connect (OSTI)

    Washington TRU Solutions LLC

    2005-05-01

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

  3. CH-TRU Waste Content Codes (CH-TRUCON)

    SciTech Connect (OSTI)

    Washington TRU Solutions LLC

    2005-03-15

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

  4. CH-TRU Waste Content Codes (CH-TRUCON)

    SciTech Connect (OSTI)

    Washington TRU Solutions LLC

    2005-08-15

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

  5. CH-TRU Waste Content Codes (CH-TRUCON)

    SciTech Connect (OSTI)

    Washington TRU Solutions LLC

    2005-01-15

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

  6. CH-TRU Waste Content Codes (CH-TRUCON)

    SciTech Connect (OSTI)

    Washington TRU Solutions LLC

    2005-12-15

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

  7. CH-TRU Waste Content Codes (CH-TRUCON)

    SciTech Connect (OSTI)

    Washington TRU Solutions LLC

    2005-06-20

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

  8. CH-TRU Waste Content Codes (CH-TRUCON)

    SciTech Connect (OSTI)

    Washington TRU Solutions LLC

    2005-01-30

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

  9. CH-TRU Waste Content Codes (CH-TRUCON)

    SciTech Connect (OSTI)

    Washington TRU Solutions LLC

    2006-09-15

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

  10. CH-TRU Waste Content Codes (CH-TRUCON)

    SciTech Connect (OSTI)

    Washington TRU Solutions LLC

    2005-11-20

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

  11. Impact of TRU waste storage on a stand-alone MRS facility

    SciTech Connect (OSTI)

    Griffin, R.E.; Ganley, J.T.

    1983-11-01

    A study was made of the impact of transuranic (TRU) waste storage on the conceptual design of a stand-alone Monitored Retrievable Storage (MRS) facility. The amount of TRU waste requiring storage is related to the startup dates of the reprocessing plant and the final repository. Current technology is available to store TRU waste from lightwater reactor (LWR) fuel reprocessing and mixed oxide (MOX) fuel refabrication safely and economically. Unit capital costs for TRU waste storage are in the range 7 to 10 $/kg of heavy metal. 7 references, 13 figures, 16 tables.

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

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

    provides oversight for WIPP and the National TRU Program, Manager Joe Franco. "The LANL Framework Agreement with New U.S. Department of Energy Carlsbad Field Office Waste...

  13. Final environmental assessment: TRU waste drum staging building, Technical Area 55, Los Alamos National Laboratory

    SciTech Connect (OSTI)

    1996-02-09

    Much of the US Department of Energy`s (DOE`s) research on plutonium metallurgy and plutonium processing is performed at Los Alamos National Laboratory (LANL), in Los Alamos, New Mexico. LANL`s main facility for plutonium research is the Plutonium Facility, also referred to as Technical Area 55 (TA-55). The main laboratory building for plutonium work within the Plutonium Facility (TA-55) is the Plutonium Facility Building 4, or PF-4. This Environmental Assessment (EA) analyzes the potential environmental effects that would be expected to occur if DOE were to stage sealed containers of transuranic (TRU) and TRU mixed waste in a support building at the Plutonium Facility (TA-55) that is adjacent to PF-4. At present, the waste containers are staged in the basement of PF-4. The proposed project is to convert an existing support structure (Building 185), a prefabricated metal building on a concrete foundation, and operate it as a temporary staging facility for sealed containers of solid TRU and TRU mixed waste. The TRU and TRU mixed wastes would be contained in sealed 55-gallon drums and standard waste boxes as they await approval to be transported to TA-54. The containers would then be transported to a longer term TRU waste storage area at TA-54. The TRU wastes are generated from plutonium operations carried out in PF-4. The drum staging building would also be used to store and prepare for use new, empty TRU waste containers.

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

    SciTech Connect (OSTI)

    Gilles, Michael L.; Gilmour, John C.

    2013-07-01

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

  15. Hydrogen Gas Generation Model for Fuel Based Remote Handled TRU Waste Stored at INEEL

    SciTech Connect (OSTI)

    Soli T. Khericha; Rajiv N. Bhatt; Kevin Liekhus

    2003-02-01

    The Idaho National Environmental and Engineering Laboratory (INEEL) initiated efforts to calculate the hydrogen gas generation in remote-handled transuranic (RH-TRU) containers in order to evaluate continued storage of unvented RH-TRU containers in vaults and to identify any potential problems during retrieval and aboveground storage. A computer code is developed to calculate the hydrogen concentration in the stored RH-TRU waste drums for known configuration, waste matrix, and radionuclide inventories as a function of time.

  16. The Department of Energy Announces Major Cold War Legacy Waste Cleanup

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

    Milestone Media Contact: (208) 586-4940 For Immediate Release: September 28, 2011 The Department of Energy Announces Major Cold War Legacy Waste Cleanup Milestone Waste Isolation Pilot Plant Receives 10,000th Shipment CARLSBAD, NM - The U.S. Department of Energy today announced that the Waste Isolation Pilot Plant (WIPP) received its 10,000th shipment of transuranic (TRU) waste over the weekend. This marks an important milestone in DOE�s mission to clean up the country�s Cold War

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

    SciTech Connect (OSTI)

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

    1993-04-01

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

  18. The NUMO Strategy for HLW and TRU Waste Disposal

    SciTech Connect (OSTI)

    Kitayama, K.; Oda, Y. [Nuclear Waste Management Organization of Japan (NUMO), Tokyo (Japan)

    2008-07-01

    Shortly after the Nuclear Waste Management Organization of Japan (NUMO) was established, we initiated an open call to all municipalities, requesting volunteers to host a repository for vitrified HLW. The first volunteer applied for a preliminary literature survey phase last January but, unfortunately, it withdrew the application in April. This failure provided an invaluable lesson for both the relevant authorities and NUMO; subsequently the Atomic Energy Commission of Japan and associated organizations are examining a support plan to back up NUMO's open solicitation. On another front, a recent amendment of 'The Specified Radioactive Waste Final Disposal Act' also allocates specific 'TRU' waste for deep geological disposal, requiring a demonstration of safety to a similar level as that for HLW. To implement the radioactive waste disposal project, NUMO has developed a methodology appropriate to our specific boundary conditions - the NUMO Structured Approach. This takes into account, in particular, our need to balance competing goals, such as operational safety, post-closure safety and cost, during repository tailoring to specific sites. The most important challenge for NUMO is, however, to attract volunteers. We believe that our open and structured R and D program is critical to demonstrate technical competence which, in turn, enhances the credibility of our various public relations activities. (authors)

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

    SciTech Connect (OSTI)

    Cournoyer, Michael E; Nixon, Archie E; Dodge, Robert L; Fife, Keith W; Sandoval, Arnold M; Garcia, Vincent E

    2010-01-01

    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.

  20. LANL Shatters Records in First Year of Accelerated TRU Waste Shipping

    Energy Savers [EERE]

    Effort | Department of Energy Shatters Records in First Year of Accelerated TRU Waste Shipping Effort LANL Shatters Records in First Year of Accelerated TRU Waste Shipping Effort December 27, 2012 - 12:00pm Addthis From left, EM Deputy Assistant Secretary for Waste Management Frank Marcinowski, San Ildefonso Pueblo Governor Terry Aguilar, Los Alamos County Council Chair Sharon Stover, New Mexico Governor Susana Martinez, Los Alamos Site Office Manager Kevin Smith, and Laboratory Director

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

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

    June 4, 2013 Bill Taylor, DOE-SR, (803) 952-8564 bill.taylor@srs.gov DT Townsend, SRNS, (803) 952-7566 Dt-lawrence.townsend@srs.gov Savannah River Site Exceeds Waste Shipment Goals AIKEN, S.C. - During the month of April, the Savannah River Site met two new milestone records towards analyzing, preparing, packaging and shipping radioactive transuranic (TRU) waste bound for a disposal site in New Mexico. The Savannah River Nuclear Solutions Solid Waste organization completed thirty-two TRU waste

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

    SciTech Connect (OSTI)

    Rodriguez, M.

    2010-12-17

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

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

    SciTech Connect (OSTI)

    Carlsbad Field Office

    2005-08-03

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

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

    SciTech Connect (OSTI)

    N /A

    2009-04-01

    Each testing and analytical facility performing waste characterization activities for the Waste Isolation Pilot Plant (WIPP) participates in the Performance Demonstration Program (PDP) to comply with the Transuranic Waste Acceptance Criteria for the Waste Isolation Pilot Plant (WAC) (DOE/WIPP-02-3122) and the Quality Assurance Program Document (QAPD) (CBFO-94-1012). The PDP serves as a quality control check for data generated in the characterization of waste destined for WIPP. Single blind audit samples are prepared and distributed to each of the facilities participating in the PDP. The PDP evaluates analyses of simulated headspace gases, constituents of the Resource Conservation and Recovery Act (RCRA), and transuranic (TRU) radionuclides using nondestructive assay (NDA) techniques.

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

    SciTech Connect (OSTI)

    None, None

    2009-10-01

    Each testing and analytical facility performing waste characterization activities for the Waste Isolation Pilot Plant (WIPP) participates in the Performance Demonstration Program (PDP) to comply with the Transuranic Waste Acceptance Criteria for the Waste Isolation Pilot Plant (WAC) (DOE/WIPP-02-3122) and the Quality Assurance Program Document (QAPD) (CBFO-94-1012). The PDP serves as a quality control check for data generated in the characterization of waste destined for WIPP. Single-blind audit samples are prepared and distributed to each of the facilities participating in the PDP. Different PDPs evaluate the analyses of simulated headspace gases (HSGs), constituents of the Resource Conservation and Recovery Act (RCRA), and transuranic (TRU) radionuclides using nondestructive assay (NDA) techniques.

  6. MWIR-1995 DOE national mixed and TRU waste database users guide

    SciTech Connect (OSTI)

    1995-11-01

    The Department of Energy (DOE) National 1995 Mixed Waste Inventory Report (MWIR-1995) Database Users Guide provides information on computer system requirements and describes installation, operation, and navigation through the database. The MWIR-1995 database contains a detailed, nationwide compilation of information on DOE mixed waste streams and treatment systems. In addition, the 1995 version includes data on non- mixed, transuranic (TRU) waste streams. These were added to the data set as a result of coordination of the 1995 update with the National Transuranic Program Office`s (NTPO`s) data needs to support the Waste Isolation Pilot Plant (WIPP) TRU Waste Baseline Inventory Report (WTWBIR). However, the information on the TRU waste streams is limited to that associated with the core mixed waste data requirements. The additional, non-core data on TRU streams collected specifically to support the WTWBIR is not included in the MWIR-1995 database. With respect to both the mixed and TRU waste stream data, the data set addresses {open_quotes}stored{close_quotes} streams. In this instance, {open_quotes}stored{close_quotes} streams are defined as (a) streams currently in storage at both EM-30 and EM-40 sites and (b) streams that have yet to be generated but are anticipated within the next five years from sources other than environmental restoration and decontamination and decommissioning (ER/D&D) activities. Information on future ER/D&D streams is maintained in the EM-40 core database. The MWIR-1995 database also contains limited information for both waste streams and treatment systems that have been removed or deleted since the 1994 MWIR. Data on these is maintained only through Section 2, Waste Stream Identification/Tracking/Source, to document the reason for removal from the data set.

  7. The WIPP RCRA Part B permit application for TRU mixed waste disposal

    SciTech Connect (OSTI)

    Johnson, J.E. [Westinghouse Electric Corp., Carlsbad, NM (United States). Waste Isolation Div.; Snider, C.A. [USDOE Carlsbad Area Office, NM (United States)

    1995-12-31

    In August 1993, the New Mexico Environment Department (NMED) issued a draft permit for the Waste Isolation Pilot Plant (WIPP) to begin experiments with transuranic (TRU) mixed waste. Subsequently, the Department of Energy (DOE) decided to cancel the on-site test program, opting instead for laboratory testing. The Secretary of the NMED withdrew the draft permit in 1994, ordering the State`s Hazardous and Radioactive Waste Bureau to work with the DOE on submittal of a revised permit application. Revision 5 of the WIPP`s Resource Conservation and Recovery Act (RCRA) Part B Permit Application was submitted to the NMED in May 1995, focusing on disposal of 175,600 m{sup 3} of TRU mixed waste over a 25 year span plus ten years for closure. A key portion of the application, the Waste Analysis Plan, shifted from requirements to characterize a relatively small volume of TRU mixed waste for on-site experiments, to describing a complete program that would apply to all DOE TRU waste generating facilities and meet the appropriate RCRA regulations. Waste characterization will be conducted on a waste stream basis, fitting into three broad categories: (1) homogeneous solids, (2) soil/gravel, and (3) debris wastes. Techniques used include radiography, visually examining waste from opened containers, radioassay, headspace gas sampling, physical sampling and analysis of homogeneous wastes, and review of documented acceptable knowledge. Acceptable knowledge of the original organics and metals used, and the operations that generated these waste streams is sufficient in most cases to determine if the waste has toxicity characteristics, hazardous constituents, polychlorinated biphenyls (PBCs), or RCRA regulated metals.

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

    SciTech Connect (OSTI)

    Carlsbad Field Office

    2001-01-31

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

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

    SciTech Connect (OSTI)

    GREAGER, T.M.

    1999-09-09

    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.

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

    SciTech Connect (OSTI)

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

    1982-01-01

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

  11. Statistical analysis of radiochemical measurements of TRU radionuclides in REDC waste

    SciTech Connect (OSTI)

    Beauchamp, J.; Downing, D.; Chapman, J.; Fedorov, V.; Nguyen, L.; Parks, C.; Schultz, F.; Yong, L.

    1996-10-01

    This report summarizes results of the study on the isotopic ratios of transuranium elements in waste from the Radiochemical Engineering Development Center actinide-processing streams. The knowledge of the isotopic ratios when combined with results of nondestructive assays, in particular with results of Active-Passive Neutron Examination Assay and Gamma Active Segmented Passive Assay, may lead to significant increase in precision of the determination of TRU elements contained in ORNL generated waste streams.

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

    SciTech Connect (OSTI)

    Halada, Gary P

    2008-04-10

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

  13. Hydrogen venting characteristics of commercial carbon-composite filters and applications to TRU waste

    SciTech Connect (OSTI)

    Callis, E.L.; Marshall, R.S.; Cappis, J.H.

    1997-04-01

    The generation of hydrogen (by radiolysis) and of other potentially flammable gases in radioactive wastes which are in contact with hydrogenous materials is a source of concern, both from transportation and on-site storage considerations. Because very little experimental data on the generation and accumulation of hydrogen was available in actual waste materials, work was initiated to experimentally determine factors affecting the concentration of hydrogen in the waste containers, such as the hydrogen generation rate, (G-values) and the rate of loss of hydrogen through packaging and commercial filter-vents, including a new design suitable for plastic bags. This report deals only with the venting aspect of the problem. Hydrogen venting characteristics of two types of commercial carbon-composite filter-vents, and two types of PVC bag closures (heat-sealed and twist-and-tape) were measured. Techniques and equipment were developed to permit measurement of the hydrogen concentration in various layers of actual transuranic (TRU) waste packages, both with and without filter-vents. A test barrel was assembled containing known configuration and amounts of TRU wastes. Measurements of the hydrogen in the headspace verified a hydrogen release model developed by Benchmark Environmental Corporation. These data were used to calculate revised wattage Emits for TRU waste packages incorporating the new bag filter-vent.

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

    SciTech Connect (OSTI)

    GREAGER, T.M.

    1999-12-14

    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).

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

    Office of Environmental Management (EM)

    Mercury-Contaminated Soil | Department of Energy Site Completes Canyon-Side Cleanup of Mercury-Contaminated Soil EM's Los Alamos Site Completes Canyon-Side Cleanup of Mercury-Contaminated Soil July 28, 2015 - 12:00pm Addthis A spider excavator extracts mercury-contaminated soil. A spider excavator extracts mercury-contaminated soil. Workers position a crane above the project site. Workers position a crane above the project site. A waste container is loaded for off-site disposal. A waste

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

    SciTech Connect (OSTI)

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

    1997-09-01

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

  17. System to control contamination during retrieval of buried TRU waste

    DOE Patents [OSTI]

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

    1993-01-01

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

  18. System to control contamination during retrieval of buried TRU waste

    DOE Patents [OSTI]

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

    1993-04-20

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

  19. WIPP RH-TRU Waste Study - Notice To Users

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

    Notice To Users The NTP World Wide Web (WWW) server is provided as a service of the Department of Energy for distribution of publicly available information and is maintained by the Waste Isolation Pilot Plant (WIPP). NTP is an agency of the Federal Government of the United States of America. Use of NTP WWW server is intended only for the retrieval of information available through NTP WWW documents. Only authorized WIPP administrators may make changes to the information. This document could not

  20. EXAMPLE OF A RISK BASED DISPOSAL APPROVAL SOLIDIFICATION OF HANFORD SITE TRANSURANIC (TRU) WASTE

    SciTech Connect (OSTI)

    PRIGNANO AL

    2007-11-14

    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 (WPP) 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.

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

    SciTech Connect (OSTI)

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

    1998-03-01

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

  2. Development of hydrogen gas getters for TRU waste

    SciTech Connect (OSTI)

    Kaszuba, J. P. (John P.); Mroz, E. J. (Eugene J.); Peterson, E. (Eric); Stone, M. (Mark); Haga, M. J. (Marc J.)

    2004-01-01

    Alpha radiolysis of hydrogenous waste and packaging materials generates hydrogen gas in radioactive storage containers. For this reason, the flammable gas (hydrogen) concentration in waste shipment containers (Transuranic Package Transporter-II or TP-II containers) is limited to the lower explosion limit of hydrogen in air (5 vol%). The use of hydrogen getters is being investigated to prevent the build up of hydrogen during storage and transport of the TP-II containers (up to 60 days). Preferred hydrogen getters are solid materials that scavenge hydrogen from the gas phase and chemically and irreversibly bind it in the solid state. One proven getter, 1,4-bis(phenylethynyl)benzene or DEB, belongs to a class of compounds called alkynes, which are characterized by the presence of carbon-carbon triple bonds. These carbon atoms will, in the presence of suitable catalysts such as palladium, irreversibly react with hydrogen to form the corresponding saturated alkane compounds. Because DEB contains two triple bonds, one mole of DEB reacts with 4 moles of hydrogen. The standard formulation for the 'DEB getter' is a mixture of 75% DEB and 25% carbon catalyst (5% palladium on carbon). Certain chemicals such as volatile organic compounds (VOCs) are known to 'poison' and reduce the activity of the catalyst. Therefore, in addition to the standard formulation, a semi-permeable barrier that encapsulates and protects the getter and its catalyst from poisons was also developed. The uncoated and polymer coated getter formulations were subjected to tests that determined the performance of the getters with regard to capacity, operating temperature range (with hydrogen in nitrogen and in air), hydrogen concentration, poisons, aging, pressure, reversibility, and radiation effects. This testing program was designed to address the following performance requirements: (1) Minimum rate for hydrogen removal of 1.2E-5 moles hydrogen per second for 60 days; (2) Sufficient getter material within the TP-II to ensure that no more than 50% of getter material is consumed during the 60 days; and (3) Adequate hydrogen removal rate from the getter reaction in the absence of the recombination reaction of hydrogen to produce water. This conservative approach provides a measure of safety for waste shipments by ensuring that sufficient getter material is present and by not taking credit for the recombination reaction. The rationale for measuring and reporting the hydrogen removal rate at 50% getter capacity is thus derived. All of the coated getters as well as the uncoated DEB performed well above the performance requirements. Coating the DEB with polymers did not significantly enhance getter performance in the presence of poisons relative to uncoated DEB. The next phase of the project is to evaluate a scaled-up getter package for performance under waste shipping conditions anticipated in the TP-II.

  3. 2011-02 "Accelerating TRU Waste Shipments from Area G to WIPP" | Department

    Office of Environmental Management (EM)

    of Energy 2 "Accelerating TRU Waste Shipments from Area G to WIPP" 2011-02 "Accelerating TRU Waste Shipments from Area G to WIPP" The intent of this recommendation is to help ensure that the rate of removal of Transuranic Waste from Area G is consistent with the completion of milestones in the 2005 Order on Consent. It is hoped that all agencies can work together and that all available funds can be used for WIPP shipments rather than some monies being diverted to pay

  4. Improved Hydrogen Gas Getters for TRU Waste -- Final Report

    SciTech Connect (OSTI)

    Mark Stone; Michael Benson; Christopher Orme; Thomas Luther; Eric Peterson

    2005-09-01

    Alpha radiolysis of hydrogenous waste and packaging materials generates hydrogen gas in radioactive storage containers. For that reason, the Nuclear Regulatory Commission limits the flammable gas (hydrogen) concentration in the Transuranic Package Transporter-II (TRUPACT-II) containers to 5 vol% of hydrogen in air, which is the lower explosion limit. Consequently, a method is needed to prevent the build up of hydrogen to 5 vol% during the storage and transport of the TRUPACT-II containers (up to 60 days). One promising option is the use of hydrogen getters. These materials scavenge hydrogen from the gas phase and irreversibly bind it in the solid phase. One proven getter is a material called 1,4-bis (phenylethynyl) benzene, or DEB, characterized by the presence of carbon-carbon triple bonds. Carbon may, in the presence of suitable precious metal catalysts such as palladium, irreversibly react with and bind hydrogen. In the presence of oxygen, the precious metal may also eliminate hydrogen by catalyzing the formation of water. This reaction is called catalytic recombination. DEB has the needed binding rate and capacity for hydrogen that potentially could be generated in the TRUPACT II. Phases 1 and 2 of this project showed that uncoated DEB performed satisfactorily in lab scale tests. Based upon these results, Phase 3, the final project phase, included larger scale testing. Test vessels were scaled to replicate the ratio between void space in the inner containment vessel of a TRUPACT-II container and a payload of seven 55-gallon drums. The tests were run with an atmosphere of air for 63.9 days at ambient temperature (15-27C) and a scaled hydrogen generation rate of 2.60E-07 moles per second (0.35 cc/min). A second type of getter known as VEI, a proprietary polymer hydrogen getter characterized by carbon-carbon double bonds, was also tested in Phase 3. Hydrogen was successfully gettered by both getter systems. Hydrogen concentrations remained below 5 vol% (in air) for the duration of the tests. However, catalytic reaction of hydrogen with carbon triple or double bonds in the getter materials did not take place. Instead, catalytic recombination was the predominant gettering mechanism in both getter materials as evidenced by (1) consumption of oxygen in the belljars, (2) production of free water in the belljars, and (3) absence of chemical changes in both getter materials as shown by nuclear magnetic resonance spectra.

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

    SciTech Connect (OSTI)

    CANTALOUB, M.G.

    2002-01-02

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

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

    SciTech Connect (OSTI)

    WEST LD

    2011-01-13

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

  7. Central Characterization Program (CCP) Contact-Handled (CH) TRU...

    Office of Environmental Management (EM)

    Contact-Handled (CH) TRU Waste Certification and Waste Information SystemWaste Data System (WWISWDS) Data Entry Central Characterization Program (CCP) Contact-Handled (CH) TRU...

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

    SciTech Connect (OSTI)

    N /A

    2000-06-30

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

  9. GAS-GENERATION EXPERIMENTS FOR LONG-TERM STORAGE OF TRU WASTES AT WIPP

    SciTech Connect (OSTI)

    Felicione, F.S.; Carney, K.P.; Dwight, C.C.; Cummings, D.G.; Foulkrod, L.E.

    2003-02-27

    An experimental investigation was conducted for gas generation in contact-handled transuranic (CH-TRU) wastes subjected for several years to conditions similar to those expected to occur at the Waste Isolation Pilot Plant (WIPP) should the repository eventually become inundated with brine. Various types of actual CH-TRU wastes were placed into 12 corrosion-resistant vessels. The vessels were loosely filled with the wastes, which were submerged in synthetic brine having the same chemical composition as that in the WIPP vicinity. The vessels were also inoculated with microbes found in the Salado Formation at WIPP. The vessels were sealed, purged, and the approximately 750-ml headspace was pressurized with nitrogen gas to approximately 146 atmospheres to create anoxic conditions at the lithostatic pressure expected in the repository were it inundated. The temperature was maintained at the expected 30 C. The test program objective was to measure the quantities and species of gases generate d by metal corrosion, radiolysis, and microbial activity. These data will assist in the specification of the rates at which gases are produced under inundated repository conditions for use in the WIPP Performance Assessment computer models. These experiments were very carefully designed, constructed, instrumented, and performed. Approximately 6-1/2 years of continuous, undisturbed testing were accumulated. Several of the vessels showed significantly elevated levels of generated gases, virtually all of which was hydrogen. One vessel measured over 4.2% hydrogen, by volume. Two other vessels generated well over 1% hydrogen, and another was at nearly 1%. Only small quantities of other gases, principally carbon dioxide, were detected. Gas generation was found to depend strongly on the waste composition. The maximum hydrogen generation occurred in tests containing carbon steel. Average corrosion penetration rates in carbon-steel of up to 2.3 microns per year were deduced. Conversion of carbon to carbon dioxide was calculated to be up to 4.7 {micro}g-mol/yr/g-carbon.

  10. Design and operation of a passive neutron monitor for assaying the TRU content of solid wastes

    SciTech Connect (OSTI)

    Brodzinski, R.L.; Brown, D.P.; Rieck, H.G. Jr.; Rogers, L.A.

    1984-02-01

    A passive neutron monitor has been designed and built for determining the residual transuranic (TRU) and plutonium content of chopped leached fuel hulls and other solid wastes from spent Fast Flux Test Facility (FFTF) fuel. The system was designed to measure as little as 8 g of plutonium or 88 mg of TRU in a waste package as large as a 208-l drum which could be emitting up to 220,000 R/hr of gamma radiation. For practical purposes, maximum assay times were chosen to be 10,000 sec. The monitor consists of 96 /sup 10/BF/sub 3/ neutron sensitive proportional counting tubes each 5.08 cm in diameter and 183 cm in active length. Tables of neutron emission rates from both spontaneous fission and (..cap alpha..,n) reactions on oxygen are given for all contributing isotopes expected to be present in spent FFTF fuel. Tables of neutron yeilds from isotopic compositions predicted for various exposures and cooling times are also given. Methods of data reduction and sources, magnitude, and control of errors are discussed. Backgrounds and efficiencies have been measured and are reported. A section describing step-by-step operational procedures is included. Guidelines and procedures for quality control and troubleshooting are also given. 13 references, 15 figures, 4 tables.

  11. Project Plan, Status, and Lessons Learned for the LANL 3,706 m{sup 3} TRU Waste Campaign - 13085

    SciTech Connect (OSTI)

    Johns-Hughes, K.W.; Clemmons, J.S.; Cox, D.R.; Hargis, K.M.; Bishop, M.L.

    2013-07-01

    The Los Alamos National Laboratory (LANL) is currently engaged in a campaign to disposition 3,706 m{sup 3} of transuranic (TRU) waste stored above grade at its Technical Area 54 (TA-54) Area G waste management facility before June 30, 2014. This campaign includes complete removal of all non-cemented above-grade TRU waste that was in storage on October 1, 2011, and is defined as 3,706 m{sup 3} of material. TRU waste containers were placed into storage up to 40 years ago, and most of the older containers must be remediated to address compliance issues before the waste can be characterized, certified as meeting the Waste Isolation Pilot Plant (WIPP) Waste Acceptance Criteria (WAC), and shipped for disposition. More than half of the remaining TRU waste volume stored above grade is contained within oversize boxes that contain waste items that must be repackaged or size reduced. Facilities and major types of equipment needed to remediate and characterize the TRU waste inventory include two additional oversize box processing lines that are being brought into service as Nuclear Hazard Category III facilities in fiscal year (FY) 2013. Multiple work shifts are scheduled for most remediation lines in FY 2013. An integrated risk-based project management schedule for all disposition activities has been developed that is based on a 'Solution Package' approach. Inventories of containers that have issues in common were compiled into about 15 waste categories and about 75 'Solution Packages' that identify all of the activities needed to disposition the inventory of TRU waste in storage. Scheduled activities include all precursor activities to begin remediation, remediation processing, characterization and certification to the WIPP WAC, and shipping of containers to WIPP. Other industrial processing practices that have been adopted to improve efficiency include staging of containers for remediation, characterization, and shipping; establishment of a transportation center; and load management practices for transportation payloads. Progress and accomplishments during FY 2012 are reviewed, and plans for FY 2013 are presented in some detail. Lessons learned on adoption of industrial processing practices are also discussed. (authors)

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

    SciTech Connect (OSTI)

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

    2013-07-01

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

  13. Transportation considerations related to waste forms and canisters for Defense TRU wastes

    SciTech Connect (OSTI)

    Schneider, K.J.; Andrews, W.B.; Schreiber, A.M.; Rosenthal, L.J.; Odle, C.J.

    1981-09-01

    This report identifies and discusses the considerations imposed by transportation on waste forms and canisters for contact-handled, solid transuranic wastes from the US Department of Energy (DOE) activities. The report reviews (1) the existing raw waste forms and potential immobilized waste forms, (2) the existing and potential future DOE waste canisters and shipping containers, (3) regulations and regulatory trends for transporting commercial transuranic wastes on the ISA, (4) truck and rail carrier requirements and preferences for transporting the wastes, and (5) current and proposed Type B external packagings for transporting wastes.

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

    SciTech Connect (OSTI)

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

    1998-05-01

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

  15. Project Plan for the evaluation of REDC waste for TRU-waste radionuclides

    SciTech Connect (OSTI)

    Nguyen, L.; Yong, L.; Chapman, J.

    1996-09-01

    This project plan describes the plan to determine whether the solid radioactive wastes generated by the Radiochemical Engineering Development Center (REDC) meet the Department of Energy`s definition of transuranic wastes. Existing waste characterization methods will be evaluated, as well as historical data, and recommendations will be made as necessary.

  16. WIPP Documents - National TRU Program

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

    Label 1 Content 1 Label 2 Content 2 Large file size alert This symbol means the document may be a large file size. National TRU Program Annual Transuranic Waste Inventory Report - 2015 DOE/TRU-15-3425 Rev 0 Effective date 12/15 The information presented in the ATWIR - 2015 serves as a current baseline of the TRU waste inventory for potential disposal at WIPP and may be considered in future Compliance Recertification Applications. The TRU Waste Inventory Profile Reports (Appendices A and B)

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

    SciTech Connect (OSTI)

    Smith, R.J.

    1998-03-31

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

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

    Broader source: Energy.gov [DOE]

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

  19. Status and use of the Rocky Flats Environmental Technology Site Pipe Overpack Container for TRU waste storage and shipments

    SciTech Connect (OSTI)

    Thorp, D.T.; Geinitz, R.R.; Rivera, M.A.

    1998-03-03

    The Pipe Overpack Container was designed to optimize shipments of high plutonium content transuranic waste from Rocky Flats Environmental Technology Site (RFETS) to Waste Isolation Pilot Plant (WIPP). The container was approved for use in the TRUPACT-II shipping container by the Nuclear Regulatory Commission in February 1997. The container optimizes shipments to WIPP by increasing the TRUPACT-II criticality limit from 325 fissile grams equivalent (FGE) to 2,800 FGE and provides additional shielding for handling wastes with high americium-241 (Am-241) content. The container was subsequently evaluated and approved for storage of highly dispersible TRU wastes and residues at RFETS. Thermal evaluation of the container shows that the container will mitigate the impact of a worst case thermal event from reactive or potentially pyrophoric materials. These materials contain hazards postulated by the Defense Nuclear Facilities Safety Board for interim storage. Packaging these reactive or potentially pyrophoric residues in the container without stabilizing the materials is under consideration at RFETS. The design, testing, and evaluations used in the approvals, and the current status of the container usage, will be discussed.

  20. Model Based Structural Evaluation & Design of Overpack Container for Bag-Buster Processing of TRU Waste Drums

    SciTech Connect (OSTI)

    D. T. Clark; A. S. Siahpush; G. L. Anderson

    2004-07-01

    This paper describes a materials and computational model based analysis utilized to design an engineered overpack container capable of maintaining structural integrity for confinement of transuranic wastes undergoing the cryo-vacuum stress based Bag-Buster process and satisfying DOT 7A waste package requirements. The engineered overpack is a key component of the Ultra-BagBuster process/system being commercially developed by UltraTech International for potential DOE applications to non-intrusively breach inner confinement layers (poly bags/packaging) within transuranic (TRU) waste drums. This system provides a lower cost/risk approach to mitigate hydrogen gas concentration buildup limitations on transport of high alpha activity organic transuranic wastes. Four evolving overpack design configurations and two materials (low carbon steel and 300 series stainless) were considered and evaluated using non-linear finite element model analyses of structural response. Properties comparisons show that 300-series stainless is required to provide assurance of ductility and structural integrity at both room and cryogenic temperatures. The overpack designs were analyzed for five accidental drop impact orientations onto an unyielding surface (dropped flat on bottom, bottom corner, side, top corner, and top). The first three design configurations failed the bottom and top corner drop orientations (flat bottom, top, and side plates breached or underwent material failure). The fourth design utilized a protruding rim-ring (skirt) below the overpacks bottom plate and above the overpacks lid plate to absorb much of the impact energy and maintained structural integrity under all accidental drop loads at both room and cryogenic temperature conditions. Selected drop testing of the final design will be required to confirm design performance.

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

    SciTech Connect (OSTI)

    DEROSA, D.C.

    2000-01-13

    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.

  2. Strategies for the cost effective treatment of Oak Ridge legacy wastes

    SciTech Connect (OSTI)

    Compere, A.L.; Griffith, W.L.; Huxtable, W.P.; Wilson, D.F.

    1998-03-01

    Research and development treatment strategies for treatment or elimination of several Oak Ridge plant liquid, solid, and legacy wastes are detailed in this report. Treatment strategies for volumetrically contaminated nickel; enriched uranium-contaminated alkali metal fluorides; uranium-contaminated aluminum compressor blades; large, mercury-contaminated lithium isotope separations equipment; lithium process chlorine gas streams; high-concentration aluminum nitrate wastes, and high-volume, low-level nitrate wastes are discussed. Research needed to support engineering development of treatment processes is detailed.

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

    SciTech Connect (OSTI)

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

    1998-07-01

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

  4. New Facility Saves $20 Million, Accelerates Waste Processing | Department

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

    of Energy Facility Saves $20 Million, Accelerates Waste Processing New Facility Saves $20 Million, Accelerates Waste Processing August 15, 2012 - 12:00pm Addthis The new Cask Processing Enclosure (CPE) facility is located at the Transuranic Waste Processing Center (TWPC). The Transuranic Waste Processing Center (TWPC) processes, repackages, and ships the site's legacy TRU waste offsite. OAK RIDGE, Tenn. - Oak Ridge's EM program recently began operations at a newly constructed facility that

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

    SciTech Connect (OSTI)

    Hallman, Anne K.; Meyer, Dann; Rellergert, Carla A.; Schriner, Joseph A.

    1998-06-01

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

  6. Comparative assessment of TRU waste forms and processes. Volume II. Waste form data, process descriptions, and costs.

    SciTech Connect (OSTI)

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

    1982-09-01

    This volume contains supporting information for the comparative assessment of the transuranic waste forms and processes summarized in Volume I. Detailed data on the characterization of the waste forms selected for the assessment, process descriptions, and cost information are provided. The purpose of this volume is to provide additional information that may be useful when using the data in Volume I and to provide greater detail on particular waste forms and processes. Volume II is divided into two sections and two appendixes. The first section provides information on the preparation of the waste form specimens used in this study and additional characterization data in support of that in Volume I. The second section includes detailed process descriptions for the eight processes evaluated. Appendix A lists the results of MCC-1 leach test and Appendix B lists additional cost data. 56 figures, 12 tables.

  7. The Challenges of Creating a Real-Time Data Management System for TRU-Mixed Waste at the Advanced Mixed Waste Treatment Plant

    SciTech Connect (OSTI)

    Paff, S. W; Doody, S.

    2003-02-25

    This paper discusses the challenges associated with creating a data management system for waste tracking at the Advanced Mixed Waste Treatment Plant (AMWTP) at the Idaho National Engineering Lab (INEEL). The waste tracking system combines data from plant automation systems and decision points. The primary purpose of the system is to provide information to enable the plant operators and engineers to assess the risks associated with each container and determine the best method of treating it. It is also used to track the transuranic (TRU) waste containers as they move throughout the various processes at the plant. And finally, the goal of the system is to support paperless shipments of the waste to the Waste Isolation Pilot Plant (WIPP). This paper describes the approach, methodologies, the underlying design of the database, and the challenges of creating the Data Management System (DMS) prior to completion of design and construction of a major plant. The system was built utilizing an Oracle database platform, and Oracle Forms 6i in client-server mode. The underlying data architecture is container-centric, with separate tables and objects for each type of analysis used to characterize the waste, including real-time radiography (RTR), non-destructive assay (NDA), head-space gas sampling and analysis (HSGS), visual examination (VE) and coring. The use of separate tables facilitated the construction of automatic interfaces with the analysis instruments that enabled direct data capture. Movements are tracked using a location system describing each waste container's current location and a history table tracking the container's movement history. The movement system is designed to interface both with radio-frequency bar-code devices and the plant's integrated control system (ICS). Collections of containers or information, such as batches, were created across the various types of analyses, which enabled a single, cohesive approach to be developed for verification and validation activities. The DMS includes general system functions, including task lists, electronic signature, non-conformance reports and message systems, that cut vertically across the remaining subsystems. Oracle's security features were utilized to ensure that only authorized users were allowed to log in, and to restrict access to system functionality according to user role.

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

    SciTech Connect (OSTI)

    Aponte, C.I.

    2000-02-17

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

  9. RH TRU Waste Program

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

    as addressed in WIPP's first environmental impact statement in 1980 and the 1992 federal WIPP ... and NMED must approve the site's procedures for characterization, determining ...

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

    SciTech Connect (OSTI)

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

    1984-01-01

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

  11. Survey of DOE NDA practices for CH-Tru waste certification--illustrated with a greater than 10,000 drum NDA data base

    SciTech Connect (OSTI)

    Schultz, F.J.; Caldwell, J.T.; Smith, J.R.

    1988-01-01

    We have compiled a greater than 10,000 CH-TRU waste drum data base from seven DOE sites which have utilized such multiple NDA measurements within the past few years. Most of these nondestructive assay (NDA) technique assay result comparisons have been performed on well-characterized, segregated waste categories such as cemented sludges, combustibles, metals, graphite residues, glasses, etc., with well-known plutonium isotopic compositions. Waste segregation and categorization practices vary from one DOE site to another. Perhaps the most systematic approach has been in use for several years at the Rocky Flats Plant (RFP), operated by Rockwell International, and located near Golden, Colorado. Most of the drum assays in our data base result from assays of RFP wastes, with comparisons available between the original RFP assays and PAN assays performed independently at the Idaho National Engineering Laboratory (INEL) Solid Waste Examination Pilot Plant (SWEPP) facility. Most of the RFP assays were performed with hyperpure germanium (HPGe)-based SGS assay units. However, at least one very important waste category, processed first-stage sludges, is assayed at RFP using a sludge batch-sampling procedure, prior to filling of the waste drums. 5 refs., 5 figs.

  12. Westinghouse TRU Solutions LLC Assumes WIPP Operations

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

    Westinghouse TRU Solutions LLC Assumes WIPP Operations CARLSBAD, N.M., February 1, 2001 - Westinghouse TRU Solutions LLC (WTS) today assumed responsibility for the management and operation of the U.S. Department of Energy's (DOE) Waste Isolation Pilot Plant (WIPP). Heading up the new management team is Henry F. "Hank" Herrera, President and General Manager of WTS. A retired U.S. Navy Rear Admiral, Herrera has more than 27 years of nuclear operations and radioactive waste management

  13. Preliminary Notice of Violation, Washington TRU Solutions, LLC- EA-2004-08

    Broader source: Energy.gov [DOE]

    Issued to Washington TRU Solutions, LLC, related to the Transportainer Procurement and Fabrication Deficiencies at the Waste Isolation Pilot Plant

  14. Transuranic Waste Processing Center Oak Ridge Site Specific...

    Office of Environmental Management (EM)

    Transuranic Waste Processing Update Oak Ridge Site Specific Advisory Board May 14, 2014 ...EM 3 Oak Ridge Transuranic (TRU) Waste Inventory * TRU waste is waste ...

  15. Washington TRU Solutions LLC Announces New Name and New General Manager

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

    TRU Solutions News For Immediate Release Washington TRU Solutions LLC Announces New Name and New General Manager CARLSBAD, N.M., January 14, 2003 - Washington Group International, Inc., today announced it has changed the name of Westinghouse TRU Solutions LLC to Washington TRU Solutions LLC (WTS) and named Dr. Steven D. Warren as President and General Manager. Washington TRU Solutions is the management and operating contractor for the U.S. Department of Energy's Waste Isolation Pilot Plant

  16. TRU TeamWorks

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

    , 2004 By the Numbers WIPP marks five-year anniversary Shipments scheduled to arrive at WIPP for the week of 4/4/04 - 4/10/04: 18 Total shipments received at WIPP: 2,456 Total volume disposed at WIPP: 19,042 m 3 FY04 Performance Metrics D E P A R T M E N T O F E N E R G Y U N I T E D S T A T ES O F A M E R I C A TeamWorks TeamWorks TRU A weekly e-newsletter for the Waste Isolation Pilot Plant team For those who endured the early morning cold of March 26, 1999, to witness WIPP's first shipment,

  17. WIPP TRU TeamWorks - About Us

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

    About Us TRU TeamWorks is an e-newsletter published for the Waste Isolation Pilot Plant team. Mission Statement: To provide WIPP employees and stakeholders with relevant, timely information that highlights project accomplishments, incorporates messages related to project goals and advances the WIPP viewpoint. Submissions: Have an article suggestion or submittal? Send an e-mail to the TRU TeamWorks staff.

  18. Legacy Management Sites | Department of Energy

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

    to managing its responsibilities associated with the environmental legacy of World War II and the Cold War. This legacy includes radioactive and chemical waste, environmental...

  19. Safety evaluation for packaging (onsite) for concrete-shielded RHTRU waste drum for the 327 postirradiation testing laboratory

    SciTech Connect (OSTI)

    Adkins, H.E.

    1996-10-29

    This safety evaluation for packaging authorizes onsite transport of Type B quantities of radioactive material in the Concrete- Shielded Remote-Handled Transuranic Waste (RH TRU) Drum per WHC-CM-2-14, Hazardous Material Packaging and Shipping. The drum will be used for transport of 327 Building legacy waste from the 300 Area to the Transuranic Waste Storage and Assay Facility in the 200 West Area and on to a Solid Waste Storage Facility, also in the 200 Area.

  20. Review: Waste-Pretreatment Technologies for Remediation of Legacy Defense Nuclear Wastes

    SciTech Connect (OSTI)

    Wilmarth, William R.; Lumetta, Gregg J.; Johnson, Michael E.; Poirier, Micheal R.; Thompson, Major C.; Suggs, Patricia C.; Machara, N.

    2011-01-13

    The U.S. Department of Energy (DOE) is responsible for retrieving, immobilizing, and disposing of radioactive waste that has been generated during the production of nuclear weapons in the United States. The vast bulk of this waste material is stored in underground tanks at the Savannah River Site in South Carolina and the Hanford Site in Washington State. The general strategy for treating the radioactive tank waste consists of first separating the waste into high-level and low-activity fractions. This initial partitioning of the waste is referred to as pretreatment. Following pretreatment, the high-level fraction will be immobilized in a glass form suitable for disposal in a geologic repository. The low-activity waste will be immobilized in a waste form suitable for disposal at the respective site. This paper provides a review of recent developments in the application of pretreatment technologies to the processing of the Hanford and Savannah River radioactive tank wastes. Included in the review are discussions of 1) solid/liquid separations methods, 2) cesium separation technologies, and 3) other separations critical to the success of the DOE tank waste remediation effort. Also included is a brief discussion of the different requirements and circumstances at the two DOE sites that have in some cases led to different choices in pretreatment technologies.

  1. Transuranic contaminated waste form characterization and data base

    SciTech Connect (OSTI)

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

    1980-07-01

    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.

  2. DOE - Office of Legacy Management -- MonValley

    Office of Legacy Management (LM)

    ... at the Monument Valley, Arizona, DOE Legacy Waste Site-2008 Pilot Study Status Report ... Arizona, and Shiprock, New Mexico, DOE Legacy Waste Sites-2007 Pilot Study Status ...

  3. U.S. Department of Energy Carlsbad Field Office Waste Isolation Pilot Plant

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

    U.S. Department of Energy Carlsbad Field Office Waste Isolation Pilot Plant P.O. Box 3090 Carlsbad, New Mexico Media Contact: Deb Gill U.S. DOE Carlsbad Field Office (575) 234-7270 www.wipp.energy.gov DOE Completes TRU Waste Cleanup at Bettis CARLSBAD, N.M., September 23, 2011 - The U.S. Department of Energy (DOE) has successfully completed cleanup of all Cold War legacy transuranic (TRU) waste at the Bettis Atomic Power Laboratory (BAPL) near Pittsburgh, Pa., permanently disposing of it at the

  4. Memo - Legacy Technical Area (TA)-55 Nitrate Salt Wastes at TA...

    Office of Environmental Management (EM)

    on February 14, 2014, report in Attachment F. Bibliography and References, are available on various public websites. PDF icon Memo - Legacy Technical Area (TA)-55 Nitrate Salt ...

  5. DISPOSAL OF TRU WASTE FROM THE PLUTONIUM FINISHING PLANT IN PIPE OVERPACK CONTAINERS TO WIPP INCLUDING NEW SECURITY REQUIREMENTS

    SciTech Connect (OSTI)

    Hopkins, A.M.; Sutter, C.; Hulse, G.; Teal, J.

    2003-02-27

    The Department of Energy is responsible for the safe management and cleanup of the DOE complex. As part of the cleanup and closure of the Plutonium Finishing Plant (PFP) located on the Hanford site, the nuclear material inventory was reviewed to determine the appropriate disposition path. Based on the nuclear material characteristics, the material was designated for stabilization and packaging for long term storage and transfer to the Savannah River Site or, a decision for discard was made. The discarded material was designated as waste material and slated for disposal to the Waste Isolation Pilot Plant (WIPP). Prior to preparing any residue wastes for disposal at the WIPP, several major activities need to be completed. As detailed a processing history as possible of the material including origin of the waste must be researched and documented. A technical basis for termination of safeguards on the material must be prepared and approved. Utilizing process knowledge and processing history, the material must be characterized, sampling requirements determined, acceptable knowledge package and waste designation completed prior to disposal. All of these activities involve several organizations including the contractor, DOE, state representatives and other regulators such as EPA. At PFP, a process has been developed for meeting the many, varied requirements and successfully used to prepare several residue waste streams including Rocky Flats incinerator ash, Hanford incinerator ash and Sand, Slag and Crucible (SS&C) material for disposal. These waste residues are packed into Pipe Overpack Containers for shipment to the WIPP.

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

    SciTech Connect (OSTI)

    Love, Gregory A.; Glazner, Christopher G.; Steckley, Sam

    2013-07-01

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

  7. Fabrication of a Sludge-Conditioning System for Processing Legacy Wastes from the Gunite and Associated Tanks

    SciTech Connect (OSTI)

    Randolph, J.D.; Lewis, B.E.; Farmer, J.R.; Johnson, M.A.

    2000-08-01

    The Sludge Conditioning System (SCS) for the Gunite and Associated Tanks (GAATs) is designed to receive, monitor, characterize and process legacy waste materials from the South Tank Farm tanks in preparation for final transfer of the wastes to the Melton Valley Storage Tanks (MVSTs), which are located at Oak Ridge National Laboratory. The SCS includes (1) a Primary Conditioning System (PCS) Enclosure for sampling and particle size classification, (2) a Solids Monitoring Test Loop (SMTL) for slurry characterization, (3) a Waste Transfer Pump to retrieve and transfer waste materials from GAAT consolidation tank W-9 to the MVSTs, (4) a PulsAir Mixing System to provide mixing of consolidated sludges for ease of retrieval, and (5) the interconnecting piping and valving. This report presents the design, fabrication, cost, and fabrication schedule information for the SCS.

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

    Broader source: Energy.gov [DOE]

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

  9. Hazardous and Corrosive Gas Production in the Radiolysis of Water/Organic Mixtures in Model TRU Waste

    SciTech Connect (OSTI)

    LaVerne, Jay A.

    2005-06-01

    Experiments in combination with diffusion-kinetic modeling incorporating track structure simulations are used to examine the radiation chemistry of aqueous systems containing chlorinated hydrocarbons. Irradiations with both Co-60 gamma rays and alpha particles are employed in order to simulate typical mixed radiation environments encountered in waste management. The goal is to determine fundamental mechanisms, kinetics, and yields for the formation of potentially explosive gases and corrosive agents, such as H2 and HCl, respectively, in the radiolysis of water-organic mixtures. The radiation chemical systems studied are found throughout the DOE portfolio and are important in radioactive waste remediation and management.

  10. Characterization and Disposition of Legacy Low-Level Waste at the Y-12 National Security Complex - 12133

    SciTech Connect (OSTI)

    Tharp, Tim; Donnelly, Jim

    2012-07-01

    The Y-12 National Security Complex (Y-12) is concluding a multi-year program to characterize and dispose of all legacy low-level waste (LLW). The inventory of legacy waste at Y-12 has been reduced from over 3500 containers in Fiscal Year (FY) 2000 to 6 containers at the end of FY2011. In addition, the site recently eliminated the inventory of other low-level waste that is greater than 365 days old (i.e., >365-Day LLW), to be in full compliance with DOE Order 435.1. A consistent technical characterization approach emerged for both of these populations of backlogged waste: (1) compile existing historical data and process knowledge and conduct interviews with site personnel; (2) inspect the containers and any tags, labels, or other markings to confirm or glean additional data; (3) with appropriate monitoring, open the container, visually inspect and photograph the contents while obtaining preliminary radiological surveys; (4) obtain gross weight and field non-destructive assay (NDA) data as needed; (5) use the non-public Oak Ridge Reservation Haul Road to ship the container to a local offsite vendor for waste sorting and segregation; (6) sort, drain, sample, and remove prohibited items; and (7) compile final data and prepare for shipment to disposal. After disposing of this backlog, the focus has now turned to avoiding the recurrence of this situation by maintaining low inventories of low-level waste and shortening the duration between waste generation and disposal. An enhanced waste tracking system and monthly metric charts are used to monitor and report progress to contractor and federal site office management. During the past 2 years, the average age of LLW onsite at Y-12 has decreased from more than 180 days to less than 60 days. (authors)

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

    SciTech Connect (OSTI)

    Rajiv Bhatt; Soli Khericha

    2005-02-01

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

  12. Enforcement Letter, Washington TRU Solutions- September 8, 2006

    Broader source: Energy.gov [DOE]

    Issued to Washington TRU Solutions, LLC related to Quality Assurance Deficiencies associated with the Super High-Efficiency Neutron Counter Non-Destructive Assay System Refurbishment at the Waste Isolation Pilot Plant

  13. Westinghouse TRU Solutions Launches New Web Site

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

    TRU Solutions LLC Launches New Web Site CARLSBAD, N.M., February 2, 2001 - Westinghouse TRU Solutions LLC (WTS) today launched its new Web site. WTS is the new management and operating contractor for the U.S. Department of Energy (DOE) at the Waste Isolation Pilot Plant (WIPP). The Web site, www.trusolutionsnm.com, is designed to provide up-to-date information about WTS and establish a mechanism for receiving feedback. "We want to make the transition to the new company as smooth as

  14. DOE - Office of Legacy Management -- Monument Valley Mill Site...

    Office of Legacy Management (LM)

    at the Monument Valley, Arizona, DOE Legacy Waste Site 2008 Pilot Study Status Report ... at the Monument Valley, Arizona, DOE Legacy Phytoremediation of the ...

  15. DOE - Office of Legacy Management -- Gen_Atomics

    Office of Legacy Management (LM)

    for the GA Project Files to the Office of Legacy Management (DOE memorandum) September 3, ... April 2002 General Atomics Final Drum of Legacy Mixed Wastes (Department of Toxic ...

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

    SciTech Connect (OSTI)

    Wenner, Michael; Franceschini, Fausto; Ferroni, Paolo; Sartori, Alberto; Ricotti, Marco

    2012-07-01

    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 exhausted. The radiotoxicity of the actinide waste during the various phases has been characterized, showing the beneficial effect of the decreasing content of TRU in the recycled fuel as the transition to a closed Th-based fuel cycle is undertaken. Due to the back-to-front nature of the proposed methodology, detailed designs are not the first step taken when assessing a fuel cycle scenario potential. As a result, design refinement is still required and should be expected in future studies. Moreover, significant safety assessment, including determination of associated reactivity coefficients, fuel and reprocessing feasibility studies and economic assessments will still be needed for a more comprehensive and meaningful comparison against other potential solutions. With the above considerations in mind, the potential advantages of thorium fuelled reactors on HLW management optimization lead us to believe that thorium fuelled reactor systems can play a significant role in the future and deserve further consideration. (authors)

  17. TRASH TO TREASURE: CONVERTING COLD WAR LEGACY WASTE INTO WEAPONS AGAINST CANCER

    SciTech Connect (OSTI)

    Nicholas, R.G.; Lacy, N.H.; Butz, T.R.; Brandon, N.E.

    2004-10-06

    As part of its commitment to clean up Cold War legacy sites, the U.S. Department of Energy (DOE) has initiated an exciting and unique project to dispose of its inventory of uranium-233 (233U) stored at Oak Ridge National Laboratory (ORNL), and extract isotopes that show great promise in the treatment of deadly cancers. In addition to increasing the supply of potentially useful medical isotopes, the project will rid DOE of a nuclear concern and cut surveillance and security costs. For more than 30 years, DOE's ORNL has stored over 1,200 containers of fissile 233U, originally produced for several defense-related projects, including a pilot study that looked at using 233U as a commercial reactor fuel. This uranium, designated as special nuclear material, requires expensive security, safety, and environmental controls. It has been stored at an ORNL facility, Building 3019A, that dates back to the Manhattan Project. Down-blending the material to a safer form, rather than continuing to store it, will eliminate a $15 million a year financial liability for the DOE and increase the supply of medical isotopes by 5,700 percent. During the down-blending process, thorium-229 (229Th) will be extracted. The thorium will then be used to extract actinium-225 (225Ac), which will ultimately supply its progeny, bismuth-213 (213Bi), for on-going cancer research. The research includes Phase II clinical trials for the treatment of acute myelogenous leukemia at Sloan-Kettering Memorial Cancer Center in New York, as well as other serious cancers of the lungs, pancreas, and kidneys using a technique known as alpha-particle radioimmunotherapy. Alpha-particle radioimmunotherapy is based on the emission of alpha particles by radionuclides. 213Bi is attached to a monoclonal antibody that targets specific cells. The bismuth then delivers a high-powered but short-range radiation dose, effectively killing the cancerous cells but sparing the surrounding tissue. Production of the actinium and bismuth would be a private venture at no cost to the government. Isotek Systems, LLC, was commissioned by the DOE to execute the project, known as the 233U Disposition, Medical Isotope Production, and Building 3019 Complex Shutdown Project. Isotek is a partnership between Duratek Federal Services, Burns and Roe Enterprises, and Nuclear Fuel Services. By pooling their pioneering experiences in nuclear engineering and design, nuclear recycling, and waste management, the partnership has developed a novel process to meet this clean-up milestone. The project is not only important for its cancer treatment potential, but also for setting the stage for reducing global threats through the down-blending of materials.

  18. Hazardous and Corrosive Gas Production in the Radiolysis of Water/Organic Mixtures in Model TRU Waste

    SciTech Connect (OSTI)

    LaVerne, Jay A.

    2004-12-01

    Scope. The radiation chemistry of aqueous systems containing chlorinated hydrocarbons is investigated using a multi-pronged approach employing 60Co gamma ray and alpha particle irradiation experiments in conjunction with diffusion-kinetic modeling incorporating track structure simulations. The goal is to determine mechanisms, kinetics, and yields for the formation of potentially explosive gases and corrosive agents, such as H2 and HCl, respectively, in the radiolysis of water-organic mixtures. The information obtained is of a fundamental nature, but the radiation chemical systems studied are found throughout the DOE portfolio and are important in radioactive waste remediation and management. Program Highlights. Radiation-induced production of H2 and HCl from chlorinated hydrocarbons. 60Co gamma-radiolysis experiments and stochastic kinetic modeling have been used to investigated the radiation-induced yield of H2 and Cl- from aqueous solutions of 1,2-dichloroethane (1,2-DCE) and 1,1-dichloroethane (1,1-DCE) over the concentration range 1-80 mM. In deoxygenated solution, the yield of H2 from both 1,2-DCE and 1,1-DCE solutions decreases as the concentration of DCE is increased. The decrease in the H2 yield shows that the reaction of H atom with DCE does not lead to the production of H2. This observation is unexpected and reflects the reverse of the effect seen in the gas phase, where the reaction of H atom with 1,2-DCE and 1,1-DCE leads to the production of H2. The yield of Cl- from 1,2-DCE and 1,1-DCE solutions increases slightly from 2.8 ions/100eV to 3.6 over the concentration range 10-50 mM, demonstrating the increased competition of the DCE with intra-track processes. Comparison of the measured yields of Cl- with the predictions of stochastic kinetic modeling shows that the reactions of eaq- with 1,2-DCE and with 1,1-DCE are quantitative, and that the reaction of H atom with both DCEs leads to the production of Cl- (and Haq+). In aerated solution, the yield of Cl- from 1,2-DCE and from 1,1-DCE solutions is very significantly higher ({approx} x 3-4) than from deoxygenated solution. Furthermore, the observed yield is both dose and dose rate dependent. The mechanisms for Cl- production in aerated aqueous solutions of 1,2-DCE and of 1,1-DCE are currently under investigation. Rate coefficients for the reaction of eaq- and -OH with chlorinated hydrocarbons. There is considerable disagreement over the rate coefficients for the reaction of the primary radiation-produced reducing and oxidizing radicals from water, eaq- and -OH respectively, with 1,2-DCE and with 1,1-DCE. Electron pulse-radiolysis experiments monitoring the decay of eaq- have been used to measure the rate coefficients: 1,2 DCE eaq- + CH2Cl-CH2Cl ' CH2Cl-CH2- + Cl- k1 = 2.3 x 109 dm3 mole-1 s-1 1,1 DCE eaq- + CH3Cl-CHCl2 ' CH3-CHCl- + Cl- k2 = 3.5 x 109 dm3 mole-1 s-1 while competition kinetic experiments were employed to determine the rate coefficients: 1,2 DCE -OH + CH2Cl-CH2Cl ' CH2Cl-CHCl- + H2O k3 = 1.8 x 108 dm3 mole-1 s-1 1,1 DCE -OH + CH3Cl-CHCl2 ' CH3-CCl2- + H2O k4 = 1.1 x 108 dm3 mole-1 s-1 The values obtained are similar to those measured by Asmus and co-workers, but there is a significant discrepancy from the estimate of Getoff and co-workers for k1. Rate coefficient for the reaction of OH with thiocyanide ion. The rate coefficient for the reaction of the -OH radical with a chlorinated hydrocarbon is obtained by a competition experiment, in which the change in the radiation-induced yield of (SCN)2-- from an aqueous SCN- solution is monitored on the addition of the hydrocarbon. The mechanism for the radiation-induced formation of (SCN)2-- from a SCN- is complex and involves a number of equilibria. Careful electron pulse radiolysis experiments have been performed and analyzed, employing the full, complex reaction mechanism, to re-evaluated the rate coefficient for the fundamental reaction -OH + SCN- ' (HOSCN)-- k5 = 1.4 x 1010 dm3 mole-1 s-1 This reaction is central to the experimental determination of the rate coefficient of a solute with OH using the

  19. Waste Isolation Pilot Plant | Department of Energy

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

    Waste Isolation Pilot Plant Waste Isolation Pilot Plant Waste Isolation Pilot Plant | June 2007 Salt Disposal Investigations Waste Isolation Pilot Plant | June 2007 Salt Disposal Investigations The mission of the Waste Isolation Pilot Plant site is to provide permanent, underground disposal of TRU and TRU-mixed wastes (wastes that also have hazardous chemical components). TRU waste consists of clothing, tools, and debris left from the research and production of nuclear weapons. TRU waste is

  20. Waste Isolation Pilot Plant | Department of Energy

    Energy Savers [EERE]

    Waste Isolation Pilot Plant Waste Isolation Pilot Plant Waste Isolation Pilot Plant | June 2007 Salt Disposal Investigations Waste Isolation Pilot Plant | June 2007 Salt Disposal Investigations The mission of the Waste Isolation Pilot Plant site is to provide permanent, underground disposal of TRU and TRU-mixed wastes (wastes that also have hazardous chemical components). TRU waste consists of clothing, tools, and debris left from the research and production of nuclear weapons. TRU waste is

  1. DRAFT EM SSAB Chair's Meeting Waste Disposition Strategies...

    Energy Savers [EERE]

    ship TRU offsite www.energy.govEM 7 Savannah River * Reduced legacy CH-TRU stored down to ... shipped in FY 2013 Paducah C-410 Feed Plant building slated for demolition in FY2014 ...

  2. Packing TRU Waste Containers Design

    Broader source: Energy.gov [DOE]

    Supporting Technical Document for the Radiological Release Accident Investigation Report (Phase II Report)

  3. Physics Features of TRU-Fueled VHTRs

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Lewis, Tom G.; Tsvetkov, Pavel V.

    2009-01-01

    The current waste management strategy for spent nuclear fuel (SNF) mandated by the US Congress is the disposal of high-level waste (HLW) in a geological repository at Yucca Mountain. Ongoing efforts on closed-fuel cycle options and difficulties in opening and safeguarding such a repository have led to investigations of alternative waste management strategies. One potential strategy for the US fuel cycle would be to make use of fuel loadings containing high concentrations of transuranic (TRU) nuclides in the next-generation reactors. The use of such fuels would not only increase fuel supply but could also potentially facilitate prolonged operation modes (viamore » fertile additives) on a single fuel loading. The idea is to approach autonomous operation on a single fuel loading that would allow marketing power units as nuclear batteries for worldwide deployment. Studies have already shown that high-temperature gas-cooled reactors (HTGRs) and their Generation IV (GEN IV) extensions, very-high-temperature reactors (VHTRs), have encouraging performance characteristics. This paper is focused on possible physics features of TRU-fueled VHTRs. One of the objectives of a 3-year U.S. DOE NERI project was to show that TRU-fueled VHTRs have the possibility of prolonged operation on a single fuel loading. A 3D temperature distribution was developed based on conceivable operation conditions of the 600 MWth VHTR design. Results of extensive criticality and depletion calculations with varying fuel loadings showed that VHTRs are capable for autonomous operation and HLW waste reduction when loaded with TRU fuel.« less

  4. WIPP TRU TeamWorks - Acronym List

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

    Acronym List AK Acceptable Knowledge ANL-E Argonne National Laboratory - East (Analytical Laboratory) BLM Bureau of Land Management C of C Certificate of Compliance CAST Colorado All State Transportation, Inc. CBFO Carlsbad Field Office (DOE) CCA Compliance Certification Application CCP Central Characterization Project CH-TRU Contact-Handled Transuranic (waste) CMR Central Monitoring Room CTAC Carlsbad Field Office Technical Assistance Contractor DOE United States Department of Energy DOE-CBFO

  5. Waste Management Magazine Highlights Nevada National Security Site |

    Office of Environmental Management (EM)

    Waste Isolation Pilot Plant Waste Isolation Pilot Plant Waste Isolation Pilot Plant | June 2007 Salt Disposal Investigations Waste Isolation Pilot Plant | June 2007 Salt Disposal Investigations The mission of the Waste Isolation Pilot Plant site is to provide permanent, underground disposal of TRU and TRU-mixed wastes (wastes that also have hazardous chemical components). TRU waste consists of clothing, tools, and debris left from the research and production of nuclear weapons. TRU waste is

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

    SciTech Connect (OSTI)

    Schruder, Kristan; Goodwin, Derek

    2013-07-01

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

  7. Washington TRU Solutions Inc | Open Energy Information

    Open Energy Info (EERE)

    Washington TRU Solutions Inc Jump to: navigation, search Name: Washington TRU Solutions, Inc. Place: Carlsbad, New Mexico Zip: 88220 Product: New Mexico-based managing and...

  8. ANALYSIS OF AVAILABLE HYDROGEN DATA & ACCUMULATION OF HYDROGEN IN UNVENTED TRANSURANIC (TRU) DRUMS

    SciTech Connect (OSTI)

    DAYLEY, L

    2004-06-24

    This document provides a response to the second action required in the approval for the Justification for Continued Operations (JCO) Assay and Shipment of Transuranic (TRU) Waste Containers in 218-W-4C. The Waste Management Project continues to make progress toward shipping certified TRU waste to the Waste Isolation Pilot Plant (WIPP). As the existing inventory of TRU waste in the Central Waste Complex (CWC) storage buildings is shipped, and the uncovered inventory is removed from the trenches and prepared for shipment from the Hanford Site, the covered inventory of suspect TRU wastes must be retrieved and prepared for processing for shipment to WIPP. Accumulation of hydrogen in unvented TRU waste containers is a concern due to the possibility of explosive mixtures of hydrogen and oxygen. The frequency and consequence of these gas mixtures resulting in an explosion must be addressed. The purpose of this study is to recommend an approach and schedule for venting TRU waste containers in the low-level burial ground (LLBG) trenches in conjunction with TRU Retrieval Project activities. This study provides a detailed analysis of the expected probability of hydrogen gas accumulation in significant quantities in unvented drums. Hydrogen gas accumulation in TRU drums is presented and evaluated in the following three categories: Hydrogen concentrations less than 5 vol%; Hydrogen between 5-15 vol%; and Hydrogen concentrations above 15 vol%. This analysis is based on complex-wide experience with TRU waste drums, available experimental data, and evaluations of storage conditions. Data reviewed in this report includes experience from the Idaho National Environmental Engineering Laboratories (INEEL), Savannah River Site (SRS), Los Alamos National Laboratories (LANL), Oak Ridge National Laboratories, (ORNL), Rocky Flats sites, Matrix Depletion Program and the National Transportation and Packaging Program. Based on this analysis, as well as an assessment of the probability and frequency of postulated credible accident scenarios, this study presents a plan and schedule for accomplishing necessary venting for segregated unvented TRU drums. A recommended method for venting TRU drums is proposed. Upon revision of the authorization basis document to include TRU drum venting, and successful completion of readiness activities; TRU drum venting will be implemented in the LLBG.

  9. TRU TeamWorks - August 14, 2003

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

    Thursday 8-14-03 | LANL Hosts RH Demo | WIPP launches new e-newsletter, TRU TeamWorks. Weekly pu A weekly e-newsletter for the Waste Isolation Pilot Plant team August 14, 2003 The Big Story LANL RH Demo a Big Success Topics Characterization News Transportation News Disposal News Safety News Working Smart Announcements Our Team Tools Acronym List Archives WIPP Home Page Links Feedback Contact us with feedback or submit your e-mail address for updates. Click here to e-mail. WIPP Shipments 16

  10. Westinghouse TRU Solutions LLC Earns Superior Star Award for Safety

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

    TRU Solutions LLC Earns Superior Star Award for Safety CARLSBAD, N.M., September 20, 2001 - The U.S. Department of Energy (DOE) has recognized Westinghouse TRU Solutions LLC (WTS) for its ongoing safety performance with the Voluntary Protection Program (VPP) "Superior Star" award. WTS is the management and operating contractor for DOE at the Waste Isolation Pilot Plant (WIPP). Dr. Inés Triay, Manager of DOE's Carlsbad Field Office, today presented the award to WTS President and

  11. Annual Transuranic Waste Inventory Report - 2013

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

    0 Page 4 of 382 Table of Figures Figure 1-1. U.S. Department of Energy TRU Waste Generator Sites ... 17 Figure 2-1. TRU Waste Inventory Process Flowchart...

  12. Microsoft Word - Transmittal of the Certification Audit Report for the Hanford TRU Program.doc

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

    389:UFC 2300.00 Department of Energy Carlsbad Field Office P. O. Box 3090 Carlsbad, New Mexico 88221 October 15, 2008 Mr. Steve Zappe, Project Leader Hazardous Waste Bureau New Mexico Environment Department 2905 Rodeo Park Drive East, Building 1 Santa Fe, New Mexico 87505-6303 Subject: Transmittal of the Certification Audit Report for the Hanford TRU Program Dear Mr. Zappe: Enclosed is the Hanford TRU Program Audit Report for the processes performed to characterize and certify waste as required

  13. Deployment at the Savannah River Site of a standardized, modular transportable and connectable hazard category 2 nuclear system for repackaging TRU waste

    SciTech Connect (OSTI)

    Lussiez, G.; Hickman, S.; Anast, K. R.; Oliver, W. B.

    2004-01-01

    This paper describes the conception, design, fabrication and deployment of a modular, transportable, connectable Category 2 nuclear system deployed at the Savannah River site to be used for characterizing and repackaging Transuranic Waste destined for the Waste Isolation Pilot Plant (WIPP). A standardized Nuclear Category 2 and Performance Category 2 envelope called a 'Nuclear Transportainer' was conceived and designed that provides a safety envelope for nuclear operations. The Nuclear Transportainer can be outfitted with equipment that performs functions necessary to meet mission objectives, in this case repackaging waste for shipment to WIPP. Once outfitted with process and ventilation systems the Nuclear Transportainer is a Modular Unit (MU). Each MU is connectable to other MUS - nuclear or non-nuclear - allowing for multiple functions, command & control, or increasing capacity. The design took advantage of work already in-progress at Los Alamos National Laboratory (LANL) for a similar system to be deployed at LANL's Technical Area 54.

  14. TruRead | Open Energy Information

    Open Energy Info (EERE)

    TruRead Jump to: navigation, search Name: TruRead Place: Cheshire, United Kingdom Zip: SK9 5AG Sector: Services Product: Provides integrated services for end-to-end collection and...

  15. Contact-Handled and Remote-Handled Transuranic Waste Packaging

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

    2011-08-09

    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/supersede other directives.

  16. TRU TeamWorks

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

    9, 2012 WIPP Quick Facts (As of 11-28-12) 11,014 Shipments received since opening (10,395 CH and 619 RH) 84,718 Cubic meters of waste disposed (83,411 CH and 307 RH) 163,960 Containers disposed in the underground (163,347 CH and 613 RH) File Photo WIPP receives 11,000th shipment Shipment Number 1 arrived at the Waste Isolation Pilot Plant (WIPP) in March 1999 and now, less than 14 years later, the facility has received Number 11,000. The milestone shipment was received at WIPP's main gate at

  17. DOE Exercises 5 Year Option on Washington TRU Solutions Contract to Operate

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

    WIPP | Department of Energy Exercises 5 Year Option on Washington TRU Solutions Contract to Operate WIPP DOE Exercises 5 Year Option on Washington TRU Solutions Contract to Operate WIPP January 18, 2005 - 9:55am Addthis WASHINGTON, DC - The U.S. Department of Energy (DOE) announced today that it has decided to exercise the five year option in the Washington TRU Solutions LLC ("WTS") contract to continue managing and operating the Department's Waste Isolation Pilot Plant (WIPP),

  18. RECOVERY ACT LEADS TO CLEANUP OF TRANSURANIC WASTE SITES

    Broader source: Energy.gov [DOE]

    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.

  19. TRU TeamWorks

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

    4, 2013 WIPP Quick Facts (As of 1-23-13) 11,112 Shipments received since opening (10,483 CH and 629 RH) 85,498 Cubic meters of waste disposed (85,185 CH and 313 RH) 165,172 Containers disposed in the underground (164,545 CH and 627 RH) WIPP employee honored by American Red Cross WIPP's Bob Walker was among a handful of honorees at the American Red Cross' Southeastern New Mexico Real Heroes Breakfast & Awards held January 10 in Hobbs. The organization awarded Real Heroes in various

  20. TRU TeamWorks

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

    3 WIPP Quick Facts (As of 3-26-13, 6 a.m.) 11,1159 Shipments received since opening (10,521 CH and 638 RH) 85,719 Cubic meters of waste disposed (85,403 CH and 316 RH) 165,362 Containers disposed in the underground (164,731 CH and 631 RH) WIPP Laboratories receives Certificate of Registration WIPP Laboratories has received a Certificate of Registration for Clinical Laboratory Improvement Amendment (CLIA). The certificate permits the laboratory to conduct radiochemical testing of emergency

  1. TRU TeamWorks

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

    8, 2012 WIPP Quick Facts (As of 9-26-12) 10,849 Shipments received since opening (10,252 CH and 597 RH) 83,693 Cubic meters of waste disposed (82,394 CH and 299 RH) 162,472 Containers disposed in the underground (161,882 CH and 590 RH) Photo above right: CBFO Deputy Manager Ed Ziemianski presents a WIPP team with the Green Zia Program Silver Level Award from the New Mexico Environment Department on Aug. 15, 2012 in recognition of environmental initiatives. Shown right of Ziemianski is Farok

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

    Office of Scientific and Technical Information (OSTI)

    Sections (Technical Report) | SciTech Connect LWR First Recycle of TRU with Thorium Oxide for Transmutation and Cross Sections Citation Details In-Document Search Title: LWR First Recycle of TRU with Thorium Oxide for Transmutation and Cross Sections Thorium has been considered as an option to uranium-based fuel, based on considerations of resource utilization (thorium is approximately three times more plentiful than uranium) and as a result of concerns about proliferation and waste

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

    Office of Scientific and Technical Information (OSTI)

    Sections (Technical Report) | SciTech Connect LWR First Recycle of TRU with Thorium Oxide for Transmutation and Cross Sections Citation Details In-Document Search Title: LWR First Recycle of TRU with Thorium Oxide for Transmutation and Cross Sections Thorium has been considered as an option to uranium-based fuel, based on considerations of resource utilization (thorium is approximately three times more plentiful than uranium) and as a result of concerns about proliferation and waste

  4. Workers at Hanford Site Achieve Recovery Act Legacy Cleanup Goals Ahead of Schedule

    Broader source: Energy.gov [DOE]

    The Hanford Site recently surpassed American Recovery and Reinvestment Act goals to accelerate the cleanup of legacy waste and fuels.

  5. Westinghouse TRU Solutions LLC Earns Corporate Award for Mining Operations

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

    Earns Corporate Award for Mining Operations CARLSBAD, N.M., May 3, 2001 - Washington Group International has selected Westinghouse TRU Solutions LLC (WTS) for a 2000 Eagle Award. WTS is the management and operating contractor for the U.S. Department of Energy (DOE) at the Waste Isolation Pilot Plant (WIPP). Washington Group International's annual Eagle Awards Program acknowledges and honors extraordinary projects, teams and individual performers. Washington Group International is the parent

  6. DOE - Office of Legacy Management -- Seymour_FUSRAP

    Office of Legacy Management (LM)

    DOE will determine if waste management is required for the supplemental limits material. Office of Legacy Management activities currently consist of managing site records and ...

  7. DOE - Office of Legacy Management -- Niagara Falls Storage Site...

    Office of Legacy Management (LM)

    of Engineers but will eventually transfer to the U.S. Department of Energy Office of Legacy Management. Assessment of Historical Knolls Atomic Power Laboratory Waste Storage...

  8. Managing Legacy Records for Formerly Utilized Sites Remedial Action Program

    Energy Savers [EERE]

    Sites | Department of Energy Managing Legacy Records for Formerly Utilized Sites Remedial Action Program Sites Managing Legacy Records for Formerly Utilized Sites Remedial Action Program Sites Managing Legacy Records for Formerly Utilized Sites Remedial Action Program Sites (Waste Management Conference 2008) PDF icon Managing Legacy Records for Formerly Utilized Sites Remedial Action Program Sites More Documents & Publications FUSRAP Overview Recent Developments in DOE FUSRAP Process for

  9. NATIONAL TRU PROGRAM LESSONS LEARNED PLAN

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

    16-3560 Revision 0 NATIONAL TRU PROGRAM LESSONS LEARNED PLAN Revision 0 March 2016 U.S. DEPARTMENT OF ENERGY CARLSBAD FIELD OFFICE DOE/CBFO 16-3560 Revision 0 2 NATIONAL TRU PROGRAM LESSONS LEARNED PLAN Revision 0 Effective March 9, 2016 Prepared by: //Signature on File// Date: March 7,2016 J.R. Stroble, Director TRU Sites and Transportation Division Concurred by: //Signature on File// Date: March 7,2016 Casey Gadbury, Assistant Manager Office of the Program Management National TRU Program

  10. Marchetti New CEO of Washington TRU Solutions

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

    Release Marchetti New CEO of Washington TRU Solutions CARLSBAD, N.M., July 31, 2003 - Stephen Marchetti, Executive Vice President of Operations for the Energy and Environment unit...

  11. Transuranic (TRU) Waste Site Certification/ Recertification ...

    Office of Environmental Management (EM)

    This document was used to determine facts and conditions during the Department of Energy Accident Investigation Board's investigation into the radiological release event at the ...

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

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

    Exercises 5 Year Option on Washington TRU Solutions Contract to Operate WIPP DOE Exercises 5 Year Option on Washington TRU Solutions Contract to Operate WIPP January 18, 2005 - ...

  13. COMPREHENSIVE LEGACY MANAGEMENT

    Office of Legacy Management (LM)

    Fernald Preserve, Fernald, Ohio Comprehensive Legacy Management and Institutional Controls ... blank LMSFERS03496-8.0 Comprehensive Legacy Management and Institutional Controls ...

  14. CH-TRU Content Codes (CH-TRUCON)

    SciTech Connect (OSTI)

    Washington TRU Solutions LLC

    2005-10-15

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

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

    Broader source: Energy.gov [DOE]

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

  16. D11 WASTE DISPOSAL FACILITIES FOR TRANSURANIC WASTE

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

    92 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)).

  17. DOE Awards Contract for Oak Ridge Transuranic Waste Processing...

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

    announced the award of a contract to North Wind Solutions, LLC for waste processing ... TRU waste; perform surveillance and maintenance activities; provide support to the ...

  18. Transuranic contaminated waste form characterization and data base

    SciTech Connect (OSTI)

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

    1980-07-01

    This volume contains appendices A to F. The properties of transuranium (TRU) radionuclides are described. Immobilization of TRU wastes by bituminization, urea-formaldehyde polymers, and cements is discussed. Research programs at DOE facilities engaged in TRU waste characterization and management studies are described.

  19. Microsoft Word - ARRA INVESTMENT RELEASE REVISED FINAL Aug 2

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

    were cleaned of legacy TRU waste during its first 10 years. Through the Recovery Act investment, eight additional sites will be cleaned of legacy TRU waste during the three year...

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

    SciTech Connect (OSTI)

    Carelli, M.D.; Franceschini, F.; Lahoda, E.J.; Petrovic, B.

    2012-07-01

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

  1. Potential Flammable Gas Explosion in the TRU Vent and Purge Machine

    SciTech Connect (OSTI)

    Vincent, A

    2006-04-05

    The objective of the analysis was to determine the failure of the Vent and Purge (V&P) Machine due to potential explosion in the Transuranic (TRU) drum during its venting and/or subsequent explosion in the V&P machine from the flammable gases (e.g., hydrogen and Volatile Organic Compounds [VOCs]) vented into the V&P machine from the TRU drum. The analysis considers: (a) increase in the pressure in the V&P cabinet from the original deflagration in the TRU drum including lid ejection, (b) pressure wave impact from TRU drum failure, and (c) secondary burns or deflagrations resulting from excess, unburned gases in the cabinet area. A variety of cases were considered that maximized the pressure produced in the V&P cabinet. Also, cases were analyzed that maximized the shock wave pressure in the cabinet from TRU drum failure. The calculations were performed for various initial drum pressures (e.g., 1.5 and 6 psig) for 55 gallon TRU drum. The calculated peak cabinet pressures ranged from 16 psig to 50 psig for various flammable gas compositions. The blast on top of cabinet and in outlet duct ranged from 50 psig to 63 psig and 12 psig to 16 psig, respectively, for various flammable gas compositions. The failure pressures of the cabinet and the ducts calculated by structural analysis were higher than the pressure calculated from potential flammable gas deflagrations, thus, assuring that V&P cabinet would not fail during this event. National Fire Protection Association (NFPA) 68 calculations showed that for a failure pressure of 20 psig, the available vent area in the V&P cabinet is 1.7 to 2.6 times the required vent area depending on whether hydrogen or VOCs burn in the V&P cabinet. This analysis methodology could be used to design the process equipment needed for venting TRU waste containers at other sites across the Department of Energy (DOE) Complex.

  2. Hanford site transuranic waste certification plan

    SciTech Connect (OSTI)

    GREAGER, T.M.

    1999-05-12

    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).

  3. WASTE DISPOSITION PROJECT MAKES GREAT STRIDES AT THE IDAHO SITE |

    Energy Savers [EERE]

    Department of Energy WASTE DISPOSITION PROJECT MAKES GREAT STRIDES AT THE IDAHO SITE WASTE DISPOSITION PROJECT MAKES GREAT STRIDES AT THE IDAHO SITE April 1, 2010 - 12:00pm Addthis An operator uses robotic manipulators to process RH TRU. An operator uses robotic manipulators to process RH TRU. Idaho - The Waste Disposition Project Team at the Department of Energy's Idaho Site has continued to keep its commitment to remove remote handled (RH) transuranic (TRU) waste out of Idaho, protecting

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

    SciTech Connect (OSTI)

    Not Available

    1993-03-01

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

  5. Natural and Enhanced Attenuation of Soil and Groundwater at the Monument Valley, Arizona, DOE Legacy Waste Site10281

    SciTech Connect (OSTI)

    Waugh, W.J.; Miller, D.E.; Morris, S.A.; Sheader, L.R.; Glenn, E.P.; Moore, D.; Carroll, K.C.; Benally, L.; Roanhorse, M.; Bush, R.P.; none,

    2010-03-07

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

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

    SciTech Connect (OSTI)

    Platt, A.M.; Powell, J.A.

    1980-06-01

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

  7. DRAFT EM SSAB Chairs Meeting Waste Disposition Strategies Update

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

    EM Complex Waste Management Update Frank Marcinowski Deputy Assistant Secretary for Waste Management Office of Environmental Management December 2013 www.energy.gov/EM 2 * Waste Management Accomplishments and Priorities * National TRU Program Update * LLW/MLLW Disposal Update * Other Programmatic Updates Discussion Outline www.energy.gov/EM 3 FY13 Waste Management Accomplishments * WIPP: Emplaced 5,065 cubic meters of TRU with 89 percent of shipments departed from TRU waste sites as planned *

  8. Letter from EM-1, Assistant Secretary, Jessie H. Roberson regarding

    Office of Environmental Management (EM)

    Services » Legacy Waste Legacy Waste Legacy Waste The Environmental Management Los Alamos Field Office's (EM-LA) Solid Waste Stabilization and Disposition Project Team is dedicated to packaging, shipping and disposing legacy waste - low-level, mixed low-level, and transuranic (TRU) waste - from Los Alamos National Laboratory (LANL). The most challenging legacy waste at LANL is TRU, which is currently stored at Area G, located on a mesa 1.3 miles north of the residential community of White Rock

  9. Los Alamos National Laboratory Accelerates Transuranic Waste Shipments:

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

    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 | Department of Energy 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

  10. Lab sets new record for waste volume removed

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

    this important milestone goes to the many team members who made it possible," said Lee Bishop, TRU waste manager at the Department of Energy's National Nuclear Security...

  11. Office of Legacy Management

    Office of Legacy Management (LM)

    Energy Office of Legacy Management JUL 1 0 2008 Alonso Ramirez, Scientific Director EI Verde Research Station Institute for Tropical Ecosystem Studies University of Puerto Rico...

  12. Waste Processing | Department of Energy

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

    Processing Waste Processing Workers process and repackage waste at the Transuranic Waste Processing Center’s Cask Processing Enclosure. Workers process and repackage waste at the Transuranic Waste Processing Center's Cask Processing Enclosure. Transuranic waste, or TRU, is one of several types of waste handled by Oak Ridge's EM program. This waste contains manmade elements heavier than uranium, hence the name "trans" or "beyond" uranium. Transuranic waste material

  13. AN NDA Technique for the Disposition of Mixed Low Level Waste at the Advanced Mixed Waste Treatment Project

    SciTech Connect (OSTI)

    M.J. Clapham; J.V. Seamans; R.E. Arbon

    2006-05-16

    The AMWTP is aggressively characterizing and shipping transuranic (TRU) waste to meet the DOE-IDs goal of 6000m3 of TRU waste to the Waste Isolation Pilot Plant (WIPP). The AMWTP shipping schedule requires streamlined waste movements and efficient waste characterization. Achieving this goal is complicated by the presence of waste that cannot be shipped to WIPP. A large amount of this waste is non-shippable due to the fact that no measurable TRU activity is identified during non-destructive assay (NDA).

  14. Plutonium-238 Transuranic Waste Decision Analysis

    SciTech Connect (OSTI)

    Brown, Mike; Lechel, David J.; Leigh, C.D.

    1999-06-29

    Five transuranic (TRU) waste sites in the Department of Energy (DOE) complex, collectively, have more than 2,100 cubic meters of Plutonium-238 (Pu-238) TRU waste that exceed the wattage restrictions of the Transuranic Package Transporter-II (TRUPACT-11). The Waste Isolation Pilot Plant (WIPP) is being developed by the DOE as a repository for TRU waste. With the Waste Isolation Pilot Plant (WIPP) opening in 1999, these sites are faced with a need to develop waste management practices that will enable the transportation of Pu-238 TRU waste to WIPP for disposal. This paper describes a decision analysis that provided a logical framework for addressing the Pu-238 TRU waste issue. The insights that can be gained by performing a formalized decision analysis are multifold. First and foremost, the very process. of formulating a decision tree forces the decision maker into structured, logical thinking where alternatives can be evaluated one against the other using a uniform set of criteria. In the process of developing the decision tree for transportation of Pu-238 TRU waste, several alternatives were eliminated and the logical order for decision making was discovered. Moreover, the key areas of uncertainty for proposed alternatives were identified and quantified. The decision analysis showed that the DOE can employ a combination approach where they will (1) use headspace gas analyses to show that a fraction of the Pu-238 TRU waste drums are no longer generating hydrogen gas and can be shipped to WIPP ''as-is'', (2) use drums and bags with advanced filter systems to repackage Pu-238 TRU waste drums that are still generating hydrogen, and (3) add hydrogen getter materials to the inner containment vessel of the TRUPACT-11to relieve the build-up of hydrogen gas during transportation of the Pu-238 TRU waste drums.

  15. DOE Cites Washington TRU Solutions for Nuclear Safety Violations |

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

    Department of Energy TRU Solutions for Nuclear Safety Violations DOE Cites Washington TRU Solutions for Nuclear Safety Violations December 22, 2005 - 4:53pm Addthis WASHINGTON, D.C. -- The Department of Energy (DOE) today notified Washington TRU Solutions (WTS) that it will fine the company $192,500 for violations of the department's nuclear safety requirements. The Preliminary Notice of Violation (PNOV) issued today cites a number of deficiencies that led to a series of low-level plutonium

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

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

    PDF icon deer08bruenke.pdf More Documents & Publications Verifying TRU Passive DPF Cold Ambient Performance Active Diesel Emission Control Technology for Transport Refrigeration ...

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

    SciTech Connect (OSTI)

    Tozer, Justin C.; Sanchez, Edwina G.; Dorries, Alison M.

    2013-07-01

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

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

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

    Processes to Their Environmental Consequences | Department of Energy Linking Legacies: Connecting the Cold War Nuclear Weapons Production Processes to Their Environmental Consequences Linking Legacies: Connecting the Cold War Nuclear Weapons Production Processes to Their Environmental Consequences This report described each step in the cycle of nuclear weapons production and defined for the first time a planned disposition path for all waste streams generated prior to 1992 as a result of

  19. Los Alamos National Laboratory Transuranic Waste Program Exceeds Planned

    Energy Savers [EERE]

    Shipping Goal | Department of Energy 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

  20. WIPP | U.S. Department of Energy | Waste Isolation Pilot Plant...

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

    and efficient characterization, transportation, and disposal of defense-related TRU waste. Its vision is to enable a nuclear future for our country by providing safe and...

  1. ISSUED DOE/WIPP-09-3427 Waste Data System User's Manual U.S...

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

    ... Agency (EPA) Compliance Recertification Decision and approval for polychlorinated biphenyls (PCBs) disposal * The EPA letter of approval of the DOE's RH-TRU Waste ...

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

    Broader source: Energy.gov [DOE]

    DOE achieved a major environmental cleanup milestone this week with the first shipment of remote-handled TRU waste leaving DOE’s Oak Ridge Reservation.

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

    SciTech Connect (OSTI)

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

    2010-02-01

    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.

  4. Los Alamos exceeds waste shipping goal

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

    exceeds waste shipping goal Los Alamos exceeds waste shipping goal Los Alamos shipped more than 3,000 cubic meters of transuranic (TRU) and mixed low-level waste to the Waste Isolation Pilot Plant and other approved waste disposal facilities. July 8, 2013 A shipment carrying Los Alamos transuranic waste headed to the Waste Isolation Pilot Plant in southeastern New Mexico. A shipment carrying Los Alamos transuranic waste headed to the Waste Isolation Pilot Plant in southeastern New Mexico.

  5. Los Alamos exceeds waste shipping goal

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

    Los Alamos exceeds waste shipping goal Los Alamos exceeds waste shipping goal Los Alamos shipped 1,074 cubic meters of transuranic (TRU) and mixed low-level waste to the Waste Isolation Pilot Plant and other approved waste disposal facilities. July 8, 2013 A shipment carrying Los Alamos transuranic waste heads down NM 502, bound for the Waste Isolation Pilot Plant in southeastern New Mexico. A shipment carrying Los Alamos transuranic waste heads down NM 502, bound for the Waste Isolation Pilot

  6. Los Alamos exceeds waste shipping goal

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

    Los Alamos exceeds waste shipping goal Los Alamos exceeds waste shipping goal Los Alamos shipped 1,074 cubic meters of transuranic (TRU) and mixed low-level waste to the Waste Isolation Pilot Plant and other approved waste disposal facilities. July 8, 2013 A shipment carrying Los Alamos transuranic waste heads down NM 502, bound for the Waste Isolation Pilot Plant in southeastern New Mexico. A shipment carrying Los Alamos transuranic waste heads down NM 502, bound for the Waste Isolation Pilot

  7. Comprehensive Legacy Management and Institutional Controls Plan

    Office of Legacy Management (LM)

    Department of Energy Comprehensive Legacy Management and Institutional Controls Plan Doc. .........32 Comprehensive Legacy Management and Institutional Controls ...

  8. Comprehensive Legacy Management and Institutional Controls Plan

    Office of Legacy Management (LM)

    Department of Energy Comprehensive Legacy Management and Institutional Controls Plan Doc. .........49 Comprehensive Legacy Management and Institutional Controls ...

  9. Comprehensive Legacy Management and Institutional Controls Plan

    Office of Legacy Management (LM)

    Department of Energy Comprehensive Legacy Management and Institutional Controls Plan Doc. .........52 Comprehensive Legacy Management and Institutional Controls ...

  10. Comprehensive Legacy Management and Institutional Controls Plan

    Office of Legacy Management (LM)

    Department of Energy Comprehensive Legacy Management and Institutional Controls Plan Doc. .........33 Comprehensive Legacy Management and Institutional Controls ...

  11. Comprehensive Legacy Management and Institutional Controls Plan

    Office of Legacy Management (LM)

    Department of Energy Comprehensive Legacy Management and Institutional Controls Plan Doc. .........34 Comprehensive Legacy Management and Institutional Controls ...

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

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

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

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

    SciTech Connect (OSTI)

    1995-03-31

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

  14. Legacy: Order (2015-CE-14025)

    Broader source: Energy.gov [DOE]

    DOE ordered The Legacy Companies to pay a $8,000 civil penalty after finding Legacy had failed to certify that refrigerator Maxx-Ice brand basic model MCR3U complies with the applicable energy conservation standards.

  15. Idaho's Advanced Mixed Waste Treatment Project Details 2013Accomplish...

    Office of Environmental Management (EM)

    (MLLW). The defense-related TRU waste is sent to the Waste Isolation Pilot Plant in New Mexico, and the MLLW is sent to other federal and commercial disposal sites. AMWTP is the...

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

    Office of Environmental Management (EM)

    Plant, National Transuranic Program Have Banner Year in 2013 Waste Isolation Pilot Plant, ... WIPP has permanently disposed of more than 89,000 cubic meters of TRU waste enough ...

  17. Los Alamos National Laboratory opens new waste repackaging facility

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

    Los Alamos to repackage transuranic (TRU) waste stored in large boxes. Built inside a dome once used to house containers of waste at the Laboratory, the facility is the largest...

  18. Lab Ahead of Schedule Processing Waste in Large Boxes

    Broader source: Energy.gov [DOE]

    LOS ALAMOS, N.M. – The TRU Waste Program at Los Alamos National Laboratory is currently two months ahead of schedule processing and repackaging waste stored in large fiberglass-reinforced boxes (FRPs).

  19. Transuranic Waste Processing Center Contract Awarded to Wastren Advantage, Inc.

    Broader source: Energy.gov [DOE]

    The U. S. Department of Energy announces the award of a contract to Wastren Advantage, Inc. (WAI) to manage waste management activities at the Oak Ridge Transuranic (TRU) Waste Processing Center.

  20. Waste acceptance criteria for the Waste Isolation Pilot Plant

    SciTech Connect (OSTI)

    NONE

    1996-04-01

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

  1. Tru-ly Clean - What Does It Mean?

    SciTech Connect (OSTI)

    Hopkins, A.

    2008-07-01

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

  2. Microsoft Word - Final_DOE_Cleanup_of_Legacy_TRU_at_SNL_Release...

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

    Field Office (575) 234-7270 www.wipp.energy.gov - 2 - New Mexico Governor Susana Martinez, who was on hand to see the shipments leave Sandia, said the milestone is extremely...

  3. Turning nuclear waste into glass

    SciTech Connect (OSTI)

    Pegg, Ian L.

    2015-02-15

    Vitrification has emerged as the treatment option of choice for the most dangerous radioactive waste. But dealing with the nuclear waste legacy of the Cold War will require state-of-the-art facilities and advanced glass formulations.

  4. Westinghouse TRU Solutions LLC Earns Small Business Program Award

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

    For Immediate Release Westinghouse TRU Solutions LLC Earns Small Business Program Award CARLSBAD, N.M., July 10, 2001 - Westinghouse TRU Solutions LLC (WTS) was recognized recently by the U.S. Department of Energy (DOE) with the Outstanding HUBZone Business Achievement Award. WTS was selected for the award by DOE's Secretarial Small Business Program "This award is a reflection of our commitment to DOE's Small Business Program to provide opportunities for small business concerns," said

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

    SciTech Connect (OSTI)

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

    2006-04-17

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

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

    Broader source: Energy.gov [DOE]

    CARLSBAD, N.M. – EM’s Waste Isolation Pilot Plant (WIPP), America’s only operating deep geologic repository for the permanent disposal of defense-related transuranic (TRU) waste, and the Carlsbad Field Office (CBFO) National TRU Program continued to be in the global spotlight with significant accomplishments throughout 2013.

  7. Settlement Agreement on TRU Mixed Waste Storage at Nevada Test...

    Office of Environmental Management (EM)

    contained within this Agreement. * The State covenants not to initiate or maintain any civil claim or action against DOE for the alleged violations addressed by this Agreement,...

  8. Training Underway for TRU Waste Employees Hired For Recovery...

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

    the facility. Most of the new hires are currently in 90-day training period that includes classroom and hands-on practical exercises on methods for characterizing, sorting, and...

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

    SciTech Connect (OSTI)

    1998-01-23

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

  10. Hydrogen Gas Generation Model for Fuel-Based Remote-Handled Transuranic Waste Stored at the INEEL

    SciTech Connect (OSTI)

    Khericha, S.; Bhatt, R.; Liekhus, K.

    2003-01-14

    The Idaho National Environmental and Engineering Laboratory (INEEL) initiated efforts to calculate the hydrogen gas generation in remote-handled transuranic (RH-TRU) containers in order to evaluate continued storage of unvented RH-TRU containers in vaults and to identify any potential problems during retrieval and aboveground storage. A computer code is developed to calculate the hydrogen concentration in the stored RH-TRU waste drums for known configuration, waste matrix, and radionuclide inventories as a function of time.

  11. Waste Treatment and Immobilization Plant Communications Approach Tools and Techniques

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

    Processing Waste Processing Workers process and repackage waste at the Transuranic Waste Processing Center’s Cask Processing Enclosure. Workers process and repackage waste at the Transuranic Waste Processing Center's Cask Processing Enclosure. Transuranic waste, or TRU, is one of several types of waste handled by Oak Ridge's EM program. This waste contains manmade elements heavier than uranium, hence the name "trans" or "beyond" uranium. Transuranic waste material

  12. WIPP contractor receives VPP Legacy of Stars Award 2013

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

    Management and Operating Contractor Recognized for Continuous Safety Performance CARLSBAD, N.M., September 20, 2013 - The U.S. Department of Energy (DOE) recognized Nuclear Waste Partnership LLC (NWP), the Waste Isolation Pilot Plant (WIPP) management and operating (M&O) contractor, with the Voluntary Protection Program (VPP) Legacy of Stars Award in latter August 2013. "Safety is central to everything we do, and achieving this elite designation validates our work and the safety-focused

  13. Phase 2, Solid waste retrieval strategy

    SciTech Connect (OSTI)

    Johnson, D.M.

    1994-09-29

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

  14. 1994 Solid waste forecast container volume summary

    SciTech Connect (OSTI)

    Templeton, K.J.; Clary, J.L.

    1994-09-01

    This report describes a 30-year forecast of the solid waste volumes by container type. The volumes described are low-level mixed waste (LLMW) and transuranic/transuranic mixed (TRU/TRUM) waste. These volumes and their associated container types will be generated or received at the US Department of Energy Hanford Site for storage, treatment, and disposal at Westinghouse Hanford Company`s Solid Waste Operations Complex (SWOC) during a 30-year period from FY 1994 through FY 2023. The forecast data for the 30-year period indicates that approximately 307,150 m{sup 3} of LLMW and TRU/TRUM waste will be managed by the SWOC. The main container type for this waste is 55-gallon drums, which will be used to ship 36% of the LLMW and TRU/TRUM waste. The main waste generator forecasting the use of 55-gallon drums is Past Practice Remediation. This waste will be generated by the Environmental Restoration Program during remediation of Hanford`s past practice sites. Although Past Practice Remediation is the primary generator of 55-gallon drums, most waste generators are planning to ship some percentage of their waste in 55-gallon drums. Long-length equipment containers (LECs) are forecasted to contain 32% of the LLMW and TRU/TRUM waste. The main waste generator forecasting the use of LECs is the Long-Length Equipment waste generator, which is responsible for retrieving contaminated long-length equipment from the tank farms. Boxes are forecasted to contain 21% of the waste. These containers are primarily forecasted for use by the Environmental Restoration Operations--D&D of Surplus Facilities waste generator. This waste generator is responsible for the solid waste generated during decontamination and decommissioning (D&D) of the facilities currently on the Surplus Facilities Program Plan. The remaining LLMW and TRU/TRUM waste volume is planned to be shipped in casks and other miscellaneous containers.

  15. Comprehensive Legacy Management and Institutional Controls Plan

    Office of Legacy Management (LM)

    Section 4.0 No significant changes. Comprehensive Legacy Management and Institutional Controls Plan, Revision 9, Draft Volume I, Legacy Management Plan Significant Changes Summary ...

  16. Comprehensive Legacy Management and Institutional Controls Plan

    Office of Legacy Management (LM)

    Department of Energy Comprehensive Legacy Management and Institutional Controls Plan Doc. ... Appendix A Contact List Comprehensive Legacy Management and Institutional Controls ...

  17. DOE - Office of Legacy Management -- Hallam

    Office of Legacy Management (LM)

    (D&D) Program, the Office of Legacy Management manages the Hallam ... The site transferred to the Office of Legacy Management in 2003 and requires routine ...

  18. Comprehensive Legacy Management and Institutional Controls Plan

    Office of Legacy Management (LM)

    Fernald Preserve, Fernald, Ohio Comprehensive Legacy Management and Institutional Controls ... blank LMSFERS03496-9.0 Comprehensive Legacy Management and Institutional Controls ...

  19. DOE - Office of Legacy Management -- Piqua

    Office of Legacy Management (LM)

    (D&D) Program, the Office of Legacy Management manages the Piqua ... The site transferred to the Office of Legacy Management in 2003 and requires routine ...

  20. DOE - Office of Legacy Management -- Fernald

    Office of Legacy Management (LM)

    for the Fernald Preserve pdficon 2016 Comprehensive Legacy Management and Institutional Controls Plan (LMICP): Volume I-Legacy Management Plan pdficon 2016 Volume ...

  1. DOE - Office of Legacy Management -- GJO

    Office of Legacy Management (LM)

    (D&D) Program, the Office of Legacy Management manages the Grand Junction ... The site transferred to the Office of Legacy Management in 2003 and requires routine ...

  2. DOE - Office of Legacy Management -- Ship

    Office of Legacy Management (LM)

    ... Legacy Management Site LMSSHPS05037 March 2009 Natural and Enhanced Attenuation of Soil and Groundwater at Monument Valley, Arizona, and Shiprock, New Mexico, DOE Legacy ...

  3. Comprehensive Legacy Management and Institutional Controls Plan

    Office of Legacy Management (LM)

    Contact Legacy Management 24-hour Monitored Security Telephone Number (877) 695-5322 This page intentionally left blank U.S. Department of Energy Comprehensive Legacy Management ...

  4. Environmental Remediation program completes legacy mercury cleanup...

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

    Stories Legacy slope-side cleanup Environmental Remediation program completes legacy mercury cleanup near Smith's Marketplace Los Alamos National Laboratory performed a ...

  5. TRU-DOENV--787Rev3.indd

    National Nuclear Security Administration (NNSA)

    National Nuclear Security Administration Nevada Site Offi ce at the Nevada Test Site. ... Most of the transuranic waste managed at the Nevada Test Site was generated as part of a ...

  6. CsIX/TRU Grout Feasibility Study

    SciTech Connect (OSTI)

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

    1998-11-01

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

  7. Waste Isolation Pilot Plant

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

    2/25/16 WIPP Home Page About WIPP Contact Us Search About WIPP The nation's only deep geologic repository for nuclear waste The U.S. Department of Energy's (DOE) Waste Isolation Pilot Plant (WIPP) is a deep geologic repository for permanent disposal of a specific type of waste that is the byproduct of the nation's nuclear defense program. CH and RH Waste WIPP is the nation's only repository for the disposal of nuclear waste known as transuranic, or TRU, waste. It consists of clothing, tools,

  8. CHALLENGES WITH RETRIEVING TRANSURANIC WASTE FROM THE HANFORD BURIAL GROUNDS

    SciTech Connect (OSTI)

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

    2007-08-06

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

  9. Legacy Cleanup Completion Project

    Broader source: Energy.gov [DOE]

    Presentation from the 2015 DOE National Cleanup Workshop by Christine Gelles, Associate Deputy Assistant Secretary, Waste Management EM HQ.

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

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

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

  11. 2011-07 "Maximum Utilization of WIPP by Increasing MDA G TRU...

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

    7 "Maximum Utilization of WIPP by Increasing MDA G TRU Shipments" 2011-07 "Maximum Utilization of WIPP by Increasing MDA G TRU Shipments" The intent of this recommendation is to ...

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

    SciTech Connect (OSTI)

    Not Available

    1991-12-01

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

  13. LEGACY MANAGEMENT REQUIRES INFORMATION

    SciTech Connect (OSTI)

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

    2006-12-14

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

  14. A Legacy of Benefit | Department of Energy

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

    A Legacy of Benefit A Legacy of Benefit Over more than three decades, FE research and development has established a legacy of significant achievement and return of value and benefits for the public funds invested. PDF icon Fossil Energy Research Benefits - A Legacy of Benefit More Documents & Publications Carbon Capture and Storage Return on Investment Fossil Energy Today - Fourth Quarter, 2011

  15. New Fact Sheet Highlights Waste Isolation Pilot Plant Recovery Progress |

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

    Department of Energy Fact Sheet Highlights Waste Isolation Pilot Plant Recovery Progress New Fact Sheet Highlights Waste Isolation Pilot Plant Recovery Progress February 25, 2016 - 12:00pm Addthis Workers lift a waste box from a TruPact II container at the Waste Isolation Pilot Plant. Workers lift a waste box from a TruPact II container at the Waste Isolation Pilot Plant. CARLSBAD, N.M. - In a new fact sheet, DOE's Carlsbad Field Office (CBFO) chronicles the significant progress in recovery

  16. Transuranic waste disposal in the United State

    SciTech Connect (OSTI)

    Thompson, J.D.

    1986-01-01

    The US is unique in having created a special class of radioactive waste disposal based on the concentration of transuranic (TRU) elements in the waste. Since 1970, the US has been placing newly generated TRU waste in retrievable storage. It is intended that these wastes will be placed in a permanent deep geologic repository, the Waste Isolation Pilot Plant (WIPP). The WIPP opening for a demonstration emplacement period is set for October 1988. Transuranic wastes derive from some of the manufacturing and research activities carried out by the US Department of Energy (DOE). The bulk of this waste is generated in plutonium parts fabrication activities. A variety of plutonium-contaminated materials ranging from glove boxes, high-efficiency particulate air filters, and machine tools, to chemical sludges derived from plutonium recovery streams are stored as TRU wastes. Other processes that generate TRU waste are plutonium production operations, preparation for and cleanup from fuel reprocessing, manufacturing of plutonium heat sources, and nuclear fuel cycle research activities. Extensive procedures will be used to examine and prepare waste before it is placed in the WIPP for disposal. After the WIPP opens, certified waste will be transported to it and emplaced in the repository.

  17. Advanced Safeguards Approaches for New TRU Fuel Fabrication Facilities

    SciTech Connect (OSTI)

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

    2007-12-15

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

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

    Broader source: Energy.gov [DOE]

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

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

    Broader source: Energy.gov [DOE]

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

  20. Waste Isolation Pilot Plant Update | Department of Energy

    Office of Environmental Management (EM)

    Codes (TRUCON-III) "TRU" Success: SRS Recovery Act Prepares to Complete Shipment of More Than 5,000 Cubic Meters of Nuclear Waste to WIPP EIS-0026-SA-06: Supplement Analysis

  1. Idaho Site Taps Old World Process to Treat Nuclear Waste

    Broader source: Energy.gov [DOE]

    IDAHO FALLS, Idaho – The EM program at the Idaho site is using an age-old process to treat transuranic (TRU) waste left over from nuclear reactor experiments.

  2. LANL sets waste shipping record for fourth consecutive year

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

    184 shipments, and we are on track to surpass that by a substantial margin," said Lee Bishop, TRU waste manager at the Department of Energy's Los Alamos Site Office. "We expect to...

  3. LANL sets waste shipping record for fourth consecutive year

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

    184 shipments and we are on track to surpass that by a substantial margin," said Lee Bishop, TRU waste manager at the Department of Energy's Los Alamos Site Office. "We expect to...

  4. Innovative Technique Accelerates Waste Disposal at Idaho Site

    Broader source: Energy.gov [DOE]

    IDAHO FALLS, Idaho – An innovative treatment and disposal technique is enabling the Idaho site to accelerate shipments of legacy nuclear waste for permanent disposal.

  5. Laboratory increases shipments of waste to WIPP repository

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

    repository The campaign will eliminate LANL's existing backlog of approximately 1,500 drums of legacy transuranic waste awaiting shipment to WIPP. February 11, 2010 Los Alamos...

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

    SciTech Connect (OSTI)

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

    2013-03-01

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

  7. Microsoft Word - Argonne Release Final

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

    Achieves Second TRU Waste Cleanup Goal in Two Weeks CARLSBAD, N.M., October 6, 2011 -The U.S. Department of Energy has successfully removed all legacy contact-handled transuranic (TRU) waste from the Argonne National Laboratory (ANL), near Chicago, Illinois. In September, all legacy TRU waste was removed from the Bettis Atomic Power Laboratory (BAPL), near Pittsburgh, Pennsylvania. Maintained by the DOE, ANL is the country's first science and engineering research national laboratory. This

  8. Transuranic waste disposal in the United States

    SciTech Connect (OSTI)

    Hoffman, R.B.

    1986-01-01

    The United States is unique in having created a special class of radioactive waste disposal based on the concentration of transuranic elements in the waste. Since 1970, the US has been placing newly generated transuranic waste in retrievable storage. It is intended that these wastes will be placed in a permanent deep geologic repository, the Waste Isolation Pilot Plant (WIPP). WIPP opening for a demonstration emplacement period is set for October, 1988. Transuranic wastes derive from some of the manufacturing and research activities carried out by DOE. The bulk of this waste is generated in plutonium parts fabrication activities. A variety of plutonium contaminated materials ranging from glove boxes, HEPA filters, and machine tools, to chemical sludges derived from plutonium recovery streams are stored as TRU wastes. Other processes that generate TRU waste are plutonium production operations, preparation for and cleanup from fuel reprocessing, manufacturing of plutonium heat sources, and nuclear fuel cycle research activities.

  9. WIPP Receives First Remote-Handled Waste Shipment From Sandia Labs

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

    For immediate release WIPP Receives First Remote-Handled Waste Shipment From Sandia Labs CARLSBAD, N.M., December 21, 2011 - The U.S. Department of Energy's (DOE) Waste Isolation Pilot Plant (WIPP) has received the first of eight planned defense-related remote- handled transuranic (RH-TRU) waste shipments from Sandia National Laboratories (SNL) in Albuquerque. The shipment arrived December 16 for permanent disposal in WIPP's underground repository. DOE National TRU Program Director J.R. Stroble

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

    SciTech Connect (OSTI)

    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.

    2003-02-27

    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.

  11. Waste Isolation Pilot Plant Nitrate Salt Bearing Waste Container

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

    Waste Isolation Pilot Plant (WIPP) Recovery Waste Isolation Pilot Plant (WIPP) Recovery The U.S. Department of Energy’s (DOE) Waste Isolation Pilot Plant (WIPP) is a deep geologic repository for permanent disposal of a specific type of waste that is the byproduct of the nation's nuclear defense program. WIPP is the nation's only repository for the disposal of nuclear waste known as transuranic, or TRU, waste. Two incidents occurred in February 2014 that led to the current shutdown of the

  12. MSFR TRU-burning potential and comparison with an SFR

    SciTech Connect (OSTI)

    Fiorina, C.; Cammi, A.; Franceschini, F.; Krepel, J.

    2013-07-01

    The objective of this work is to evaluate the Molten Salt Fast Reactor (MSFR) potential benefits in terms of transuranics (TRU) burning through a comparative analysis with a sodium-cooled FR. The comparison is based on TRU- and MA-burning rates, as well as on the in-core evolution of radiotoxicity and decay heat. Solubility issues limit the TRU-burning rate to 1/3 that achievable in traditional low-CR FRs (low-Conversion-Ratio Fast Reactors). The softer spectrum also determines notable radiotoxicity and decay heat of the equilibrium actinide inventory. On the other hand, the liquid fuel suggests the possibility of using a Pu-free feed composed only of Th and MA (Minor Actinides), thus maximizing the MA burning rate. This is generally not possible in traditional low-CR FRs due to safety deterioration and decay heat of reprocessed fuel. In addition, the high specific power and the lack of out-of-core cooling times foster a quick transition toward equilibrium, which improves the MSFR capability to burn an initial fissile loading, and makes the MSFR a promising system for a quick (i.e., in a reactor lifetime) transition from the current U-based fuel cycle to a novel closed Th cycle. (authors)

  13. DOE - Office of Legacy Management -- Tuba

    Office of Legacy Management (LM)

    to DOE for long-term custody and managed by the Office of Legacy Management. The site transferred to the Office of Legacy Management in 2003 and requires routine inspection and ...

  14. DOE - Office of Legacy Management -- Falls

    Office of Legacy Management (LM)

    to DOE for long-term custody and managed by the Office of Legacy Management. The site transferred to the Office of Legacy Management in 2003 and requires routine inspection and ...

  15. DOE - Office of Legacy Management -- Burrell

    Office of Legacy Management (LM)

    to DOE for long-term custody and managed by the Office of Legacy Management. The site transferred to the Office of Legacy Management in 2003 and requires routine inspection and ...

  16. DOE - Office of Legacy Management -- Ship

    Office of Legacy Management (LM)

    to DOE for long-term custody and managed by the Office of Legacy Management. The site transferred to the Office of Legacy Management in 2003 and requires routine inspection and ...

  17. DOE - Office of Legacy Management -- Lowman

    Office of Legacy Management (LM)

    to DOE for long-term custody and managed by the Office of Legacy Management. The site transferred to the Office of Legacy Management in 2003 and requires routine inspection and ...

  18. DOE - Office of Legacy Management -- Riverton

    Office of Legacy Management (LM)

    to DOE for long-term custody and managed by the Office of Legacy Management. The site transferred to the Office of Legacy Management in 2003 and requires routine inspection and ...

  19. DOE - Office of Legacy Management -- Maybell

    Office of Legacy Management (LM)

    to DOE for long-term custody and managed by the Office of Legacy Management. The site transferred to the Office of Legacy Management in 2003 and requires routine inspection and ...

  20. DOE - Office of Legacy Management -- Spook

    Office of Legacy Management (LM)

    to DOE for long-term custody and managed by the Office of Legacy Management. The site transferred to the Office of Legacy Management in 2003 and requires routine inspection and ...

  1. DOE - Office of Legacy Management -- AMB

    Office of Legacy Management (LM)

    to DOE for long-term custody and managed by the Office of Legacy Management. The site transferred to the Office of Legacy Management in 2003 and requires routine inspection and ...

  2. DOE - Office of Legacy Management -- Canon

    Office of Legacy Management (LM)

    to DOE for long-term custody and managed by the Office of Legacy Management. The site transferred to the Office of Legacy Management in 2003 and requires routine inspection and ...

  3. 2012 Annual Planning Summary for Legacy Management

    Broader source: Energy.gov [DOE]

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

  4. Sustainable Disposal Cell Covers: Legacy Management Practices,

    Energy Savers [EERE]

    Improvements, and Long-Term Performance | Department of Energy Sustainable Disposal Cell Covers: Legacy Management Practices, Improvements, and Long-Term Performance Sustainable Disposal Cell Covers: Legacy Management Practices, Improvements, and Long-Term Performance Sustainable Disposal Cell Covers: Legacy Management Practices, Improvements, and Long-Term Performance PDF icon Sustainable Disposal Cell Covers: Legacy Management Practices, Improvements, and Long-Term Performance More

  5. WIPP Uses Recovery Act Funding to Reduce Nuclear Waste Footprint

    Office of Energy Efficiency and Renewable Energy (EERE)

    CARLSBAD, N.M., August 1, 2011 The U.S. Department of Energys (DOEs) Carlsbad Field Office (CBFO) reduced the nuclear waste footprint by using American Recovery and Reinvestment Act funds to expedite the clean up of five transuranic (TRU) waste storage sites and to make important infrastructure improvements at the Waste Isolation Pilot Plant (WIPP).

  6. Preliminary Notice of Violation, Washington TRU Solutions, LLC- EA-2005-08

    Broader source: Energy.gov [DOE]

    Issued to Washington TRU Solutions, LLC, related to Radiological Uptakes at the Mobile Visual Examination and Repackaging Facility at Lawrence Livermore National Laboratory

  7. Certification document for newly generated contact-handled transuranic waste

    SciTech Connect (OSTI)

    Box, W.D.; Setaro, J.

    1984-01-01

    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.

  8. Assessment of gas flammability in transuranic waste container

    SciTech Connect (OSTI)

    Connolly, M.J.; Loehr, C.A.; Djordjevic, S.M.; Spangler, L.R.

    1995-12-01

    The Safety Analysis Report for the TRUPACT-II Shipping Package [Transuranic Package Transporter-II (TRUPACT-II) SARP] set limits for gas generation rates, wattage limits, and flammable volatile organic compound (VOC) concentrations in transuranic (TRU) waste containers that would be shipped to the Waste Isolation Pilot Plant (WIPP). Based on existing headspace gas data for drums stored at the Idaho National Engineering Laboratory (INEL) and the Rocky Flats Environmental Technology Site (RFETS), over 30 percent of the contact-handled TRU waste drums contain flammable VOC concentrations greater than the limit. Additional requirements may be imposed for emplacement of waste in the WIPP facility. The conditional no-migration determination (NMD) for the test phase of the facility required that flame tests be performed if significant levels of flammable VOCs were present in TRU waste containers. This paper describes an approach for investigating the potential flammability of TRU waste drums, which would increase the allowable concentrations of flammable VOCS. A flammability assessment methodology is presented that will allow more drums to be shipped to WIPP without treatment or repackaging and reduce the need for flame testing on drums. The approach includes experimental work to determine mixture lower explosive limits (MLEL) for the types of gas mixtures observed in TRU waste, a model for predicting the MLEL for mixtures of VOCS, hydrogen, and methane, and revised screening limits for total flammable VOCs concentrations and concentrations of hydrogen and methane using existing drum headspace gas data and the model predictions.

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

    Broader source: Energy.gov [DOE]

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

  10. 2010-01 "Disposition of Remote-Handled Waste Buried in 33 Shafts...

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

    The intent of this recommendation is to remove the highly radioactive RH-TRU wastes from TA-54 in a safe manner with a minimum of radiation exposure to workers at all levels. ...

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

    SciTech Connect (OSTI)

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

    1981-09-01

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

  12. U.S. Department of Energy Carlsbad Field Office Waste Isolation Pilot Plant

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

    U.S. DOE Carlsbad Field Office (575) 234-7270 www.wipp.energy.gov For Immediate Release National TRU Program Director Selected CARLSBAD, N.M., November 18, 2010 - The U.S. Department of Energy's (DOE) Carlsbad Field Office (CBFO) announced that J.R. Stroble has been selected as director of the National TRU Program (NTP). The NTP was created in 2000 to integrate efforts to clean up and dispose of transuranic (TRU) defense-related wastes temporarily stored at waste generator sites around the

  13. Hanford site transuranic waste sampling plan

    SciTech Connect (OSTI)

    GREAGER, T.M.

    1999-05-13

    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.

  14. Removing nuclear waste, one shipment at a time

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

    Removing nuclear waste, one shipment at a time Removing nuclear waste, one shipment at a time The Lab's 1,000th shipment of transuranic waste recently left Los Alamos, on its way to a permanent repository near Carlsbad, NM. June 26, 2012 Governor Martinez applauding the 1014th TRU waste shipment New Mexico Governor Susana Martinez and other dignitaries applaud as the 1,014th shipment of transuranic waste leaves Los Alamos National Laboratory. Contact Patti Jones Communications Office (505)

  15. Nuclear waste management. Quarterly progress report, July-September 1980

    SciTech Connect (OSTI)

    Chikalla, T.D.

    1980-11-01

    Research is reported on: high-level waste immobilization, alternative waste forms, TRU waste immobilization and decontamination, krypton solidification, thermal outgassing, /sup 129/I fixation, unsaturated zone transport, well-logging instrumentation, waste management system and safety studies, effectiveness of geologic isolation systems, waste/rock interactions, engineered barriers, backfill material, spent fuel storage (criticality), barrier sealing and liners for U mill tailings, and revegetation of inactive U tailings sites. (DLC)

  16. Lab sets new record for waste volume removed

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

    Lab Sets New Record for Waste Volume Removed Community Connections: Your link to news and opportunities from Los Alamos National Laboratory Latest Issue:May 2016 all issues All Issues » submit Lab sets new record for waste volume removed The Transuranic Waste Program has met its commitment to ship 800 cubic meters of TRU waste to the Waste Isolation Pilot Plant during fiscal year 2012. November 1, 2012 dummy image Read our archives Contacts Editor Linda Anderman Email Community Programs Office

  17. January 23, 2007: WIPP receives first shipment of waste | Department of

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

    Energy 23, 2007: WIPP receives first shipment of waste January 23, 2007: WIPP receives first shipment of waste January 23, 2007: WIPP receives first shipment of waste January 23, 2007 The Department's Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico, receives (pdf) its first shipment of remote-handled (RH) transuranic (TRU) radioactive waste. The waste, which consisted of three 30-gallon drums of radioactive debris waste and originated at DOE's Idaho National Laboratory, was

  18. WIPP Hazardous Waste Facility Permit - 2008 Update

    SciTech Connect (OSTI)

    Kehrman, R.F.; Most, W.A.

    2008-07-01

    Important new changes to the Hazardous Waste Facility Permit (HWFP) were implemented during 2007. The challenge was to implement these changes without impacting shipping schedules. Many of the changes required advanced preparation and coordination in order to transition to the new waste analysis paradigm, both at the generator sites and at the WIPP without interrupting the flow of waste to the disposal facility. Not only did aspects of waste characterization change, but also a new Permittees' confirmation program was created. Implementing the latter change required that new equipment and facilities be obtained, personnel hired, trained and qualified, and operating procedures written and approved without interruption to the contact-handled (CH) transuranic (TRU) waste shipping schedule. This was all accomplished successfully with no delayed or cancelled shipments. Looking forward to 2008 and beyond, proposed changes that will deal with waste in the DOE TRU waste complex is larger than the TRUPACT-IIs can handle. Size reduction of the waste would lead to unnecessary exposure risk and ultimately create more waste. The WIPP is working to have the Nuclear Regulatory Commission (NRC) certify the TRUPACT-III. The TRUPACT-III will be able to accommodate larger sized TRU mixed waste. Along with this new NRC-certified shipping cask, a new disposal container, the Standard Large Box, must be proposed in a permit modification. Containers for disposal of TRU mixed waste at the WIPP must meet the DOT 7A standards and be filtered. Additionally, as the TRUPACT-III/Standard Large Box loads and unloads from the end of the shipping cask, the proposed modification will add horizontal waste handling techniques to WIPP's vertical CH TRU waste handling operations. Another major focus will be the Hazardous Waste Facility Permit reapplication. The WIPP received its HWFP in October of 1999 for a term of ten years. The regulations and the HWFP require that a new permit application be submitted 180-days before the expiration date of the HWFP. At that time, the WIPP will request only one significant change, the permitting of Panel 8 to receive TRU mixed waste. (author)

  19. Los Alamos National Laboratory transuranic waste characterization and certification program - an overview of capabilities and capacity

    SciTech Connect (OSTI)

    Rogers, P.S.Z.; Sinkule, B.J.; Janecky, D.R.; Gavett, M.A. [and others

    1997-02-01

    The Los Alamos National Laboratory (LANL) has full capability to characterize transuranic (TRU) waste for shipment to and disposal at the Waste Isolation Pilot Plant (WIPP) for its projected opening. LANL TRU waste management operations also include facilities to repackage both drums of waste found not to be certifiable for WIPP and oversized boxes of waste that must be size reduced for shipment to WIPP. All characterization activities and repackaging are carried out under a quality assurance program designed to meet Carlsbad Area Office (CAO) requirements. The flow of waste containers through characterization operations, the facilities used for characterization, and the electronic data management system used for data package preparation and certification of TRU waste at LANL are described.

  20. Waste Isolation Pilot Plant Safety Analysis Report

    SciTech Connect (OSTI)

    1995-11-01

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

  1. DOE Identifies its Preferred Alternative for Certain Hanford Tank Wastes

    Broader source: Energy.gov [DOE]

    The U.S. Department of Energy (DOE) is announcing its preferred alternative for wastes contained in underground radioactive waste storage tanks evaluated in the Final Tank Closure and Waste Management Environmental Impact Statement for the Hanford Site, Richland, Washington (Final TC & WM EIS, DOE/EIS-0391, December 2012). With regard to those wastes that, in the future, may be properly and legally classified as mixed transuranic waste (mixed TRU waste). DOE's preferred alternative is to retrieve, treat, package, and characterize and certify the wastes for disposal at the Waste Isolation Pilot Plant (WIPP) in Carlsbad, New Mexico, a geologic repository for the disposal of mixed TRU waste generated by atomic energy defense activities.

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

    SciTech Connect (OSTI)

    Platt, A.M.; Powell, J.A.

    1980-09-01

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

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

    SciTech Connect (OSTI)

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

    1981-03-01

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

  4. Microsoft Word - sr201107.doc

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

    at Savannah River Site (SRS), has come online to process legacy transuranic (TRU) waste for off-site shipment and permanent disposal at the Waste Isolation Pilot Plant (WIPP), ...

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

    SciTech Connect (OSTI)

    Roggenthen, D. K.; McFeeters, T. L.; Nieweg, R. G.; Blakeslee, J. J.

    1993-03-01

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

  6. Waste Isolation Pilot Plant Recovery Plan

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

    Waste Isolation Pilot Plant Recovery Plan Revision 0 September 30, 2014 [This page left blank.] EXECUTIVE SUMMARY Overview This Recovery Plan provides a safe and compliant approach to resuming operations at the Waste Isolation Pilot Plant (WIPP), the repository for disposal of the nation's defense transuranic (TRU) waste. The U.S. Department of Energy (DOE) is committed to resuming operations by the first quarter of calendar year 2016, and this Recovery Plan outlines the Department's approach to

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

    SciTech Connect (OSTI)

    None

    1984-02-01

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

  8. Methods for removing transuranic elements from waste solutions

    SciTech Connect (OSTI)

    Slater, S.A.; Chamberlain, D.B.; Connor, C.; Sedlet, J.; Srinivasan, B.; Vandegrift, G.F.

    1994-11-01

    This report outlines a treatment scheme for separating and concentrating the transuranic (TRU) elements present in aqueous waste solutions stored at Argonne National Laboratory (ANL). The treatment method selected is carrier precipitation. Potential carriers will be evaluated in future laboratory work, beginning with ferric hydroxide and magnetite. The process will result in a supernatant with alpha activity low enough that it can be treated in the existing evaporator/concentrator at ANL. The separated TRU waste will be packaged for shipment to the Waste Isolation Pilot Plant.

  9. Legacy Cleanup Contract Awarded | Department of Energy

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

    Legacy Cleanup Contract Awarded Legacy Cleanup Contract Awarded September 23, 2015 - 6:00pm Addthis Cincinnati - The U.S. Department of Energy (DOE) today announced the award of a Cost-Plus-Award Fee contract to Los Alamos National Security, LLC (LANS) of Los Alamos, NM. This bridge contract is for the Office of Environmental Management (EM) funded legacy cleanup activities at the Los Alamos National Laboratory (LANL). LANS is formed by the University of California, Bechtel, Babcock & Wilcox

  10. DOE - Office of Legacy Management -- Monticello

    Office of Legacy Management (LM)

    The sites transferred to the Office of Legacy Management in 2003 and require operation and maintenance of remedial action systems, routine inspection and maintenance, ...

  11. DOE - Office of Legacy Management -- Rulison

    Office of Legacy Management (LM)

    Rulison, Colorado, Site A Nevada Offsite rulisonmap The DOE Office of Legacy Management assumed responsibility for long-term surveillance and maintenance at the Rulison site in ...

  12. DOE - Office of Legacy Management -- Maxey

    Office of Legacy Management (LM)

    and Liability Act (CERCLA) regulations. The site transferred to the Office of Legacy Management in 2004 and requires records-related activities and stakeholder support. ...

  13. DOE - Office of Legacy Management -- Blue

    Office of Legacy Management (LM)

    Mill Tailings Radiation Control Act (UMTRCA). The site transferred to the Office of Legacy Management in 2003 and is administered under the provisions of a general NRC license. ...

  14. DOE - Office of Legacy Management -- Amchitka

    Office of Legacy Management (LM)

    Alaska Amchitka, Alaska, Site A Nevada Offsite amchitkamap2.jpg The DOE Office of Legacy Management assumed responsibility for all activities associated with subsurface completion ...

  15. DOE - Office of Legacy Management -- Park

    Office of Legacy Management (LM)

    The site transferred to the Office of Legacy Management in 2003 and requires routine inspection and maintenance, records-related activities, and stakeholder support. For more ...

  16. DOE - Office of Legacy Management -- Shoal

    Office of Legacy Management (LM)

    Nevada Shoal, Nevada, Site A Nevada Offsite shoalmap The DOE Office of Legacy Management assumed responsibility for long-term surveillance and maintenance at the Shoal Site in ...

  17. DOE - Office of Legacy Management -- Pinellas

    Office of Legacy Management (LM)

    The site transferred to the Office of Legacy Management in 2004 and requires operation and maintenance of remedial action systems, routine inspection and maintenance, ...

  18. DOE - Office of Legacy Management -- Geothermal

    Office of Legacy Management (LM)

    After remediation, the site transferred to the Office of Legacy Management in 2005. The site requires records management and stakeholder support. For more information about the ...

  19. DOE - Office of Legacy Management -- Chariot

    Office of Legacy Management (LM)

    Alaska Chariot, Alaska, Site A Nevada Offsite chariotmap The DOE Office of Legacy Management assumed responsibility for long-term surveillance and maintenance at the Chariot Site ...

  20. DOE - Office of Legacy Management -- Gasbuggy

    Office of Legacy Management (LM)

    New Mexico Gasbuggy, New Mexico, Site A Nevada Offsite gasbuggymap The DOE Office of Legacy Management assumed responsibility for long-term surveillance and maintenance at the ...

  1. DOE - Office of Legacy Management -- Sherwood

    Office of Legacy Management (LM)

    Mill Tailings Radiation Control Act (UMTRCA). The site transferred to the Office of Legacy Management in 2003 and is administered under the provisions of a general NRC license. ...

  2. DOE - Office of Legacy Management -- MURR

    Office of Legacy Management (LM)

    After remediation, the site transferred to the Office of Legacy Management in 2005. The site requires records management and stakeholder support. For more information about the ...

  3. DOE - Office of Legacy Management -- Lbar

    Office of Legacy Management (LM)

    Mill Tailings Radiation Control Act (UMTRCA). The site transferred to the Office of Legacy Management in 2003 and is administered under the provisions of a general NRC license. ...

  4. DOE - Office of Legacy Management -- Rio

    Office of Legacy Management (LM)

    Colorado Rio Blanco, Colorado, Site A Nevada Offsite rioblancomap The DOE Office of Legacy Management assumed responsibility for long-term surveillance and maintenance at the Rio ...

  5. DOE - Office of Legacy Management -- Mound Site

    Office of Legacy Management (LM)

    U.S. Department of Energy Miamisburg Closure Project Risk Management Plan Volume III Legacy Management Transition Risks April 30, 2005 Site Transition Process Upon Cleanup ...

  6. DOE - Office of Legacy Management -- MURR

    Office of Legacy Management (LM)

    Research Reactor (MURR), Columbia, Missouri, and Transfer of Records to Office of Legacy Management (LM) August 24, 2004 Federal Facility Compliance Act 1999 Annual Site ...

  7. DOE - Office of Legacy Management -- Fernald

    Office of Legacy Management (LM)

    The site transferred to the Office of Legacy Management in 2006 and requires operation and maintenance of remedial action systems, environmental monitoring, routine inspection and ...

  8. DOE - Office of Legacy Management -- LEHR

    Office of Legacy Management (LM)

    The site transferred to the Office of Legacy Management in 2006 and requires routine inspection and maintenance, records-related activities, and stakeholder support. For more ...

  9. DOE - Office of Legacy Management -- ITL

    Office of Legacy Management (LM)

    The legislation releases DOE from all environmental liability at the Albuquerque site, including contamination from past, present, or future activities. The DOE Office of Legacy ...

  10. DOE - Office of Legacy Management -- Central

    Office of Legacy Management (LM)

    Central Nevada Test Area (CNTA), Nevada, Site A Nevada Offsite centralmap The DOE Office of Legacy Management assumed responsibility for long-term surveillance and maintenance at ...

  11. DOE - Office of Legacy Management -- Edge

    Office of Legacy Management (LM)

    Mill Tailings Radiation Control Act (UMTRCA). The site transferred to the Office of Legacy Management in 2003 and is administered under the provisions of a general NRC license. ...

  12. DOE - Office of Legacy Management -- GJD

    Office of Legacy Management (LM)

    Responsibility for custody and long-term management of the site transferred to DOE's Office of Legacy Management in 2003. Management responsibilities include routine inspection and ...

  13. DOE - Office of Legacy Management -- Salmon2

    Office of Legacy Management (LM)

    Mississippi Salmon, Mississippi, Site A Nevada Offsite salmonmap The DOE Office of Legacy Management assumed responsibility for long-term surveillance and maintenance at the ...

  14. DOE - Office of Legacy Management -- Shirley

    Office of Legacy Management (LM)

    The site transferred to the Office of Legacy Management in 2003 and is administered under the provisions of a general NRC license. The site requires routine inspection and ...

  15. DOE - Office of Legacy Management -- GJP

    Office of Legacy Management (LM)

    Responsibility for management and long-term custody of the site's contaminated groundwater transferred to DOE's Office of Legacy Management in 2003. Management requirements include ...

  16. DOE - Office of Legacy Management -- Columbus

    Office of Legacy Management (LM)

    Responsibility for maintaining records for the Columbus sites transferred to DOE's Office of Legacy Management in 2008. The sites require records management and stakeholder ...

  17. DOE - Office of Legacy Management -- CERCLA Home

    Office of Legacy Management (LM)

    Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Search CERCLA Collections CERCLA Help What is CERCLA? The Office of Legacy Management currently ...

  18. DOE - Office of Legacy Management -- Visitors Center

    Office of Legacy Management (LM)

    farming, uranium production, and environmental cleanup eras, as well as the recent ecological restoration and legacy management mission, is presented through a series of exhibits. ...

  19. DOE - Office of Legacy Management -- Ashtabula

    Office of Legacy Management (LM)

    for maintaining records for the Ashtabula site was transferred to DOE's Office of Legacy Management in 2010. The site requires records management and stakeholder support. For...

  20. Office of Legacy Management | Department of Energy

    Office of Legacy Management (LM)

    Office of Legacy Management Abandoned Uranium Mines Abandoned Uranium Mines Read more Amchitka, Alaska, Site Amchitka, Alaska, Site Read more Mexican Hat, Utah, Disposal Site...

  1. DOE - Office of Legacy Management -- CEER

    Office of Legacy Management (LM)

    for maintaining records for the CEER site transferred to DOE's Office of Legacy Management in 2006. The site requires records management and stakeholder support. For...

  2. DOE - Office of Legacy Management -- Bonus

    Office of Legacy Management (LM)

    of the DOE Defense Decontamination and Decommissioning (D&D) Program, the Office of Legacy Management manages the Boiling Nuclear Superheater (BONUS) Decommissioned Reactor Site...

  3. Legacy Management 2011-2020 Strategic Plan

    Broader source: Energy.gov [DOE]

    At the August 13, 2014 Committee meeting Tom Longo DOE, Provided Information on DOEs Long Term Stewardship Plan and Office of Legacy Management.

  4. 2011 Annual Planning Summary for Legacy Management (LM) | Department of

    Energy Savers [EERE]

    Energy Legacy Management (LM) 2011 Annual Planning Summary for Legacy Management (LM) The ongoing and projected Environmental Assessments and Environmental Impact Statements for 2011 and 2012 within Legacy Management (LM). PDF icon 2011 Annual Planning Summary for Legacy Management (LM) More Documents & Publications 2011 Annual Planning Summary for Office of Legacy Management (LM), Grand Junction (See LM APS) 2013 Annual Planning Summary for the Office of Legacy Management 2012

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

    SciTech Connect (OSTI)

    1996-04-01

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

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

    SciTech Connect (OSTI)

    Andrea Alfonsi; Gilles Youinou

    2012-07-01

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

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

    SciTech Connect (OSTI)

    Andrea Alfonsi; Gilles Youinou; Sonat Sen

    2013-02-01

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

  8. DOE - Office of Legacy Management -- SiteA

    Office of Legacy Management (LM)

    (D&D) Program, the Office of Legacy Management manages the Site APlot M ... The site transferred to the Office of Legacy Management in 2003 and requires routine ...

  9. DOE - Office of Legacy Management -- Durango Mill Site - CO 0...

    Office of Legacy Management (LM)

    ... Laura Kilpatrick November 15, 2011 U.S. Department of Energy Office of Legacy Management ... Colorado November 15, 2011 Office of Legacy Management Office of Site Operation ...

  10. DOE - Office of Legacy Management -- Tonawanda_FUSRAP

    Office of Legacy Management (LM)

    The site transferred to the Office of Legacy Management in 2008. Final Conditions-The ... Office of Legacy Management activities consist of managing site records and responding to ...

  11. DOE - Office of Legacy Management -- Monticello Mill Site - UT...

    Office of Legacy Management (LM)

    Properties Sites December 2005 Office of Legacy Management Monticello Mill Tailings Site ... Properties Sites December 2006 Office of Legacy Management Monticello Mill Tailings Site ...

  12. DOE - Office of Legacy Management -- Buffalo_FUSRAP

    Office of Legacy Management (LM)

    The site transferred to the Office of Legacy Management in 2003. Final Conditions-No ... Office of Legacy Management activities consist of managing site records and responding to ...

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

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

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

  14. 2011 Annual Planning Summary for Office of Legacy Management...

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

    Summary for Legacy Management (LM) 2013 Annual Planning Summary for the Office of Legacy Management 2012 Independent Communication and Outreach Stakeholder Satisfaction Survey

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

    SciTech Connect (OSTI)

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

    2003-02-27

    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.

  16. Fire hazards analysis for solid waste burial grounds

    SciTech Connect (OSTI)

    McDonald, K.M.

    1995-09-28

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

  17. Melter development needs assessment for RWMC buried wastes

    SciTech Connect (OSTI)

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

    1992-02-01

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

  18. Melter development needs assessment for RWMC buried wastes

    SciTech Connect (OSTI)

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

    1992-02-01

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

  19. Universal requisition for waste data collection

    SciTech Connect (OSTI)

    Nisbet, B.; Gage, M.

    1995-05-01

    Lawrence Livermore National Laboratory (LLNL) has developed a data management tool for information gathering that encompasses all types of waste generated by the site. It is referred to as the Universal Requisition. It can be used to record information for the following types of waste: non-hazardous, hazardous, low level radioactive, mixed, transuranic (TRU), and TRU mixed wastestreams. It provides the salient information needed for the safe handling, storage, and disposal of waste, and satisfies our regulatory, record keeping, and reporting requirements. There are forty two numbered fields on the requisition and several other fields for signatures, compatibility codes, internal tracking numbers, and other information. Not all of these fields are applicable to every type of waste. As an aid to using the Universal requisition, templates with the applicable fields highlighted in color were produced and distributed. There are six different waste type templates. Each is highlighted in a different color.

  20. Final Transuranic Waste Shipment Leaves Rocky Flats | Department of Energy

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

    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

  1. DOE Seeks Trucking Services for Transuranic Waste Shipments | Department of

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

    Energy 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

  2. Resuming Operations at WIPP and the National TRU Program

    Broader source: Energy.gov [DOE]

    Presentation from the 2015 DOE National Cleanup Workshop by Phil Breidenbach, Project Manager, Nuclear Waste Partnership, LLC.

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

    SciTech Connect (OSTI)

    Hladek, K.L.

    1997-10-07

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

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

    SciTech Connect (OSTI)

    Clements, Th.L.Jr.; Bhatt, R.N.; Troescher, P.D.; Lattin, W.J.

    2008-07-01

    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)

  5. Legacy Claims, PIA, Bechtel Jacobs Company, LLC | Department of Energy

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

    Legacy Claims, PIA, Bechtel Jacobs Company, LLC Legacy Claims, PIA, Bechtel Jacobs Company, LLC Legacy Claims, PIA, Bechtel Jacobs Company, LLC PDF icon Legacy Claims, PIA, Bechtel Jacobs Company, LLC More Documents & Publications Medgate, PIA, Bechtel Jacobs Company, LLC Electronic Document Management System PIA, BechtelJacobs Company, LLC Oracle Financials PIA, Bechtel Jacobs Company, LLC

  6. Waste to be Consolidated at I...

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

    Waste to be Consolidated at Idaho Site Before Shipment to WIPP The U.S. Department of Energy (DOE) is consolidating defense transuranic wastes at its Idaho Site for testing and treatment prior to shipment to the Waste Isolation Pilot Plant (WIPP) in New Mexico for disposal. Over the course of several years, 14 waste generator sites will ship transuranic, or TRU, wastes to Idaho for processing. Most of the sites do not have the infrastructure or certified programs necessary to test and treat

  7. WRAP Module 1 waste characterization plan

    SciTech Connect (OSTI)

    Mayancsik, B.A.

    1995-01-23

    The purpose of this document is to present the characterization methodology for waste generated, processed, or otherwise the responsibility of the Waste Receiving and Processing (WRAP) Module 1 facility. The scope of this document includes all solid low level waste (LLW), transuranic (TRU), mixed waste (MW), and dangerous waste. This document is not meant to be all-inclusive of the waste processed or generated within WRAP Module 1, but to present a methodology for characterization. As other streams are identified, the method of characterization will be consistent with the other streams identified in this plan. The WRAP Module 1 facility is located in the 200 West Area of the Hanford Site. The facility`s function is two-fold. The first is to verify/characterize, treat and repackage contact handled (CH) waste currently in retrievable storage in the LLW Burial Grounds, Hanford Central Waste Complex, and the Transuranic Storage and Assay Facility (TRUSAF). The second is to verify newly generated CH TRU waste and LLW, including MW. The WRAP Module 1 facility provides NDE and NDA of the waste for both drums and boxes. The NDE is used to identify the physical contents of the waste containers to support waste characterization and processing, verification, or certification. The NDA results determine the radioactive content and distribution of the waste.

  8. Dose Rate Calculation of TRU Metal Ingot in Pyroprocessing - 12202

    SciTech Connect (OSTI)

    Lee, Yoon Hee; Lee, Kunjai

    2012-07-01

    Spent fuel management has been a main problem to be solved for continuous utilization of nuclear energy. Spent fuel management policy of Korea is 'Wait and See'. It is focused on Pyro-process and SFR (Sodium-cooled Fast Reactor) for closed-fuel cycle research and development in Korea. For peaceful use of nuclear facilities, the proliferation resistance has to be proved. Proliferation resistance is one of key constraints in the deployment of advanced nuclear energy systems. Non-proliferation and safeguard issues have been strengthening internationally. Barriers to proliferation are that reduces desirability or attractiveness as an explosive and makes it difficult to gain access to the materials, or makes it difficult to misuse facilities and/or technologies for weapons applications. Barriers to proliferation are classified into intrinsic and extrinsic barriers. Intrinsic barrier is inherent quality of reactor materials or the fuel cycle that is built into the reactor design and operation such as material and technical barriers. As one of the intrinsic measures, the radiation from the material is considered significantly. Therefore the radiation of TRU metal ingot from the pyro-process was calculated using ORIGEN and MCNP code. (authors)

  9. Reduced waste generation, FY 1986

    SciTech Connect (OSTI)

    Not Available

    1986-02-01

    The United States Department of Energy is committed to the principles of minimizing the quantity and transuranic content of its transuranium (TRU) waste being generated at its nuclear facilities. The reasons are to reduce costs associated with waste handling and disposal, and also to reduce radiation exposure to workers and risk for radionuclide release to man and the environment. The purpose of this document is to provide the USDOE with a plan of research and development tasks for waste minimization, and is prepared so as to provide the maximum impact on volumes based on cost/benefit factors. The document is to be updated annually or as needed to reflect current and future tasks. The Reduced Waste Generation (RWG) tasks encompass a wide range of activities with the principal goals of (1) preventing the generation of waste and (2) converting TRU waste into low-level wastes (LLW) by sorting or decontamination. Concepts for reducing the volume such as in incineration and compaction are considered within the discipline of Reduced Waste Generation, but are considered as somewhat developed technology with only a need for implementation. 33 refs.

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

    Energy Savers [EERE]

    With the American Recovery and Reinvestment Act funding, Savannah River Site (SRS) continues ... EIS-0026-SA-06: Supplement Analysis Waste Isolation Pilot Plant Update Transuranic ...

  11. LWR First Recycle of TRU with Thorium Oxide for Transmutation...

    Office of Scientific and Technical Information (OSTI)

    more plentiful than uranium) and as a result of concerns about proliferation and waste ... Country of Publication: United States Language: English Subject: 11 NUCLEAR FUEL CYCLE AND ...

  12. 2013 Annual Planning Summary for the Office of Legacy Management |

    Energy Savers [EERE]

    Department of Energy Legacy Management 2013 Annual Planning Summary for the Office of Legacy Management The ongoing and projected Environmental Assessments and Environmental Impact Statements for 2013 and 2014 within the Office of Legacy Management . PDF icon LM_NEPA-APS-2013.pdf More Documents & Publications LM Annual NEPA Planning Summary 2014 2011 Annual Planning Summary for Legacy Management (LM) 2011 Annual Planning Summary for Office of Legacy Management (LM), Grand Junction (See

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

    SciTech Connect (OSTI)

    Metcalfe, D.; McCauley, D.; Miller, J.; Brooks, S.

    2013-07-01

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

  14. Commercial waste treatment program annual progress report for FY 1983

    SciTech Connect (OSTI)

    McElroy, J.L.; Burkholder, H.C. (comps.)

    1984-02-01

    This annual report describes progress during FY 1983 relating to technologies under development by the Commercial Waste Treatment Program, including: development of glass waste form and vitrification equipment for high-level wastes (HLW); waste form development and process selection for transuranic (TRU) wastes; pilot-scale operation of a radioactive liquid-fed ceramic melter (LFCM) system for verifying the reliability of the reference HLW treatment proces technology; evaluation of treatment requirements for spent fuel as a waste form; second-generation waste form development for HLW; and vitrification process control and product quality assurance technologies.

  15. Shipment and Disposal of Solidified Organic Waste (Waste Type IV) to the Waste Isolation Pilot Plant (WIPP)

    SciTech Connect (OSTI)

    D'Amico, E. L; Edmiston, D. R.; O'Leary, G. A.; Rivera, M. A.; Steward, D. M.

    2006-07-01

    In April of 2005, the last shipment of transuranic (TRU) waste from the Rocky Flats Environmental Technology Site to the WIPP was completed. With the completion of this shipment, all transuranic waste generated and stored at Rocky Flats was successfully removed from the site and shipped to and disposed of at the WIPP. Some of the last waste to be shipped and disposed of at the WIPP was waste consisting of solidified organic liquids that is identified as Waste Type IV in the Contact-Handled Transuranic Waste Authorized Methods for Payload Control (CH-TRAMPAC) document. Waste Type IV waste typically has a composition, and associated characteristics, that make it significantly more difficult to ship and dispose of than other Waste Types, especially with respect to gas generation. This paper provides an overview of the experience gained at Rocky Flats for management, transportation and disposal of Type IV waste at WIPP, particularly with respect to gas generation testing. (authors)

  16. Tank Waste Committee - Transcribed Flipcharts

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

    - Transcribed Flipcharts January 8, 2014 Framework 1. Is there anything in the Framework document the Board should respond to? o Any concepts the Board does not support? 2. Anything missing from IM discussion draft? o Agree/disagree with IM recommendation? Page 1 Framework * Missing: schedule & cost * Agree & support o Early LAW o Support TRU waste retrieval  Provided the State of New Mexico concurs  Determine not HLW (process knowledge)  As long as meets all applicable

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

    Office of Environmental Management (EM)

    Chair's Meeting Waste Disposition Strategies Update www.energy.gov/EM 1 Waste Disposition Strategies Update Frank Marcinowski Deputy Assistant Secretary for Waste Management Office of Environmental Management April 25, 2013 * Recent Program Accomplishments * FY13 Waste Management Priorities * FY14 Waste Management Priorities * Los Alamos Update * LLW/MLLW Disposition Options Discussion Outline www.energy.gov/EM 2 * Hanford TRU Tank Disposition Initiative * GTCC EIS * Mercury Supplemental EIS *

  18. Waste Isolation Pilot Plant Status and Plans - 2010 | Department of Energy

    Office of Environmental Management (EM)

    Status and Plans - 2010 Waste Isolation Pilot Plant Status and Plans - 2010 Overview of WIPP presented by Dr. Dave Moody. PDF icon Waste Isolation Pilot Plant Status and Plans - 2010 More Documents & Publications Central Characterization Program (CCP) Los Alamos National Laboratory (LANL) Interface Document Central Characterization Program (CCP) Transuranic Waste Certification Plan Central Characterization Program (CCP) Contact-Handled (CH) TRU Waste Certification and Waste Information

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

    SciTech Connect (OSTI)

    Washington TRU Solutions LLC

    2005-12-29

    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.

  20. INDIANAPOLIS LEAVES A LEGACY OF ENERGY EFFICIENCY

    Broader source: Energy.gov [DOE]

    The City of Indianapolis, Indiana, used its status as host of the 2012 Super Bowl to address inefficiencies in the area’s older housing stock and leave behind a legacy of energy efficiency. Seeking...

  1. DOE - Office of Legacy Management -- Weldon

    Office of Legacy Management (LM)

    The Weldon Spring Site was transferred to the Office of Legacy Management (LM) in 2003. LM conducts long-term surveillance and maintenance at the site which includes routine ...

  2. DOE - Office of Legacy Management -- Rulison

    Office of Legacy Management (LM)

    ... Path Forward LMSRULS04617 June 2010 Rulison Site U.S. Department of Energy Office of Legacy Management-Presentation to Colorado Oil and Gas Conservation Commission July 15, 2009 ...

  3. DOE - Office of Legacy Management -- Mound Site

    Office of Legacy Management (LM)

    The site long-term monitoring responsibility transferred to the Office of Legacy Management(LM) in 2010 and requires operation and maintenance of a pump and treatment system, ...

  4. DOE - Office of Legacy Management -- Rocky

    Office of Legacy Management (LM)

    Jurisdiction of the site was transferred to the Office of Legacy Management in 2008. For more information about the Rocky Flats site, view the fact sheet. Site History Site ...

  5. DOE - Office of Legacy Management -- Gnome

    Office of Legacy Management (LM)

    New Mexico Gnome-Coach, New Mexico, Site A Nevada Offsite gnomemap The DOE Office of Legacy Management assumed responsibility for long-term surveillance and maintenance at the ...

  6. MRI Beginnings - a Legacy | GE Global Research

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

    From Nobel Ideas to Industrial Success - Bill Edelstein's Legacy Click to email this to a friend (Opens in new window) Share on Facebook (Opens in new window) Click to share (Opens ...

  7. DOE - Office of Legacy Management -- Directions

    Office of Legacy Management (LM)

    Mailing: U.S. Department of Energy 10995 Hamilton-Cleves Hwy. Harrison, OH 45030 U.S. Department of Energy Office of Legacy Management Contractor Navarro Research and Engineering, ...

  8. Legacy: Proposed Penalty (2015-CE-14025)

    Broader source: Energy.gov [DOE]

    DOE alleged in a Notice of Proposed Civil Penalty that The Legacy Companies failed to certify refrigerator Maxx Ice-brand basic model MCR3U as compliant with the applicable energy conservation standards.

  9. Getting waste ready for shipment to the WIPP: integration of characterization and certification activities

    SciTech Connect (OSTI)

    Sinkule, B.; Knudsen, K.; Rogers, P.

    1996-06-01

    The Waste Isolation Pilot Plant (WIPP) Waste Acceptance Criteria (WAC) serve as the primary directive for assuring the safe handling, transportation, and disposal of transuranic (TRU) waste generated at Department of Energy (DOE) sites. The WIPP WAC address fulfillment of WIPP`s operational safety and performance assessment criteria, compliance with Resource Conservation and Recovery Act (RCRA) requirements, and preparation of waste packages that meet all transportation criteria. At individual generator sites, preparation of transuranic waste for final disposal at WIPP includes characterizing the waste to meet the requirements of the transuranic Waste Characterization Quality Assurance Program Plan (QAPP) and certifying waste containers to meet the WIPP WAC and the Transuranic Package Transporter-II Authorized Methods for Payload Control (TRAMPAC). This paper compares the quality assurance and quality control requirements specified in the WIPP WAC, QAPP, and TRAMPAC and discusses the potential to consolidate activities to comply with the TRU waste characterization and certification program requirements.

  10. WASTE ISOLATION PILOT PLANT (WIPP): THE NATIONS' SOLUTION TO NUCLEAR WASTE STORAGE AND DISPOSAL ISSUES

    SciTech Connect (OSTI)

    Lopez, Tammy Ann

    2014-07-17

    In the southeastern portion of my home state of New Mexico lies the Chihuahauan desert, where a transuranic (TRU), underground disposal site known as the Waste Isolation Pilot Plant (WIPP) occupies 16 square miles. Full operation status began in March 1999, the year I graduated from Los Alamos High School, in Los Alamos, NM, the birthplace of the atomic bomb and one of the nations main TRU waste generator sites. During the time of its development and until recently, I did not have a full grasp on the role Los Alamos was playing in regards to WIPP. WIPP is used to store and dispose of TRU waste that has been generated since the 1940s because of nuclear weapons research and testing operations that have occurred in Los Alamos, NM and at other sites throughout the United States (U.S.). TRU waste consists of items that are contaminated with artificial, man-made radioactive elements that have atomic numbers greater than uranium, or are trans-uranic, on the periodic table of elements and it has longevity characteristics that may be hazardous to human health and the environment. Therefore, WIPP has underground rooms that have been carved out of 2,000 square foot thick salt formations approximately 2,150 feet underground so that the TRU waste can be isolated and disposed of. WIPP has operated safely and successfully until this year, when two unrelated events occurred in February 2014. With these events, the safety precautions and measures that have been operating at WIPP for the last 15 years are being revised and improved to ensure that other such events do not occur again.

  11. Waste treatment facility passes federal inspection, completes final

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

    Waste and Materials Disposition Information Waste and Materials Disposition Information Waste and Materials Disposition Information As the Office of Environmental Management (EM) fulfills its mission, waste and materials disposition plays a vital role in the cleanup of radioactive waste and the environmental legacy of nuclear weapons production and nuclear energy research. Disposal of waste frequently falls on the critical path of cleanup projects. Significant planning resources are spent to

  12. Waste and Materials Disposition Information | Department of Energy

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

    Waste and Materials Disposition Information Waste and Materials Disposition Information Waste and Materials Disposition Information As the Office of Environmental Management (EM) fulfills its mission, waste and materials disposition plays a vital role in the cleanup of radioactive waste and the environmental legacy of nuclear weapons production and nuclear energy research. Disposal of waste frequently falls on the critical path of cleanup projects. Significant planning resources are spent to

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

    SciTech Connect (OSTI)

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

    2010-10-01

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

  14. Milestone reached: Waste shipment leaves Los Alamos National Laboratory

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

    Waste shipment leaves LANL Milestone reached: Waste shipment leaves Los Alamos National Laboratory The material, known as "remote-handled transuranic waste" (RH-TRU), has been stored at the Laboratory since 1995. June 2, 2009 Los Alamos National Laboratory sits on top of a once-remote mesa in northern New Mexico with the Jemez mountains as a backdrop to research and innovation covering multi-disciplines from bioscience, sustainable energy sources, to plasma physics and new materials.

  15. Waste Isolation Pilot Plant Recovery Plan | Department of Energy

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

    Recovery Plan Waste Isolation Pilot Plant Recovery Plan This Recovery Plan provides a safe and compliant approach to resuming operations at the Waste Isolation Pilot Plant (WIPP), the repository for disposal of the nation's defense transuranic (TRU) waste. The U.S. Department of Energy (DOE) is committed to resuming operations by the first quarter of calendar year 2016, and this Recovery Plan outlines the Department's approach to meet that schedule while prioritizing safety, health, and

  16. Nuclear Waste Partnership (NWP) Corrective Action Plan Addendum

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

    Radiological Release Event Phase II | Department of Energy Addendum Radiological Release Event Phase II Nuclear Waste Partnership (NWP) Corrective Action Plan Addendum Radiological Release Event Phase II On Friday, February 14, 2014 there was an incident in the underground (U/G) repository at the Waste Isolation Pilot Plant (WIPP), which resulted in the release of americium and plutonium from one or more transuranic (TRU) waste containers into the U/G mine and the environment. The accident

  17. Reduced waste generation technical work plan

    SciTech Connect (OSTI)

    Not Available

    1987-05-01

    The United States Department of Energy has established policies for avoiding plutonium losses to the waste streams and minimizing the generation of wastes produced at its nuclear facilities. This policy is evidenced in DOE Order 5820.2, which states Technical and administrative controls shall be directed towards reducing the gross volume of TRU waste generated and the amount of radioactivity in such waste.'' To comply with the DOE directive, the Defense Transuranic Waste Program (DTWP) supports and provides funding for specific research and development tasks at the various DOE sites to reduce the generation of waste. This document has been prepared to give an overview of current and past Reduced Waste Generation task activities which are to be based on technical and cost/benefit factors. The document is updated annually, or as needed, to reflect the status of program direction. Reduced Waste Generation (RWG) tasks encompass a wide range of goals which are basically oriented toward (1) avoiding the generation of waste, (2) changing processes or operations to reduce waste, (3) converting TRU waste into LLW by sorting or decontamination, and (4) reducing volumes through operations such as incineration or compaction.

  18. Waste Isolation Pilot Plant Recovery Plan Revision 0

    Broader source: Energy.gov [DOE]

    This Recovery Plan provides a safe and compliant approach to resuming operations at the Waste Isolation Pilot Plant (WIPP), the repository for disposal of the nation’s defense transuranic (TRU) waste. The U.S. Department of Energy (DOE) is committed to resuming operations by the first quarter of calendar year 2016, and this Recovery Plan outlines the Department’s approach to meet that schedule while prioritizing safety, health, and environmental protection. The recovery and resumption of TRU waste disposal operations at WIPP are central to the Department’s mission. This Recovery Plan summarizes the strategy, key activities, and management approach to safely return WIPP to its statutorily mandated mission of TRU waste disposal operations in support of the DOE’s mission requirements and its commitments to the public and the community, as well as TRU waste generator sites and their host states. This Recovery Plan is being issued before the investigations into the cause of the radiological release in the WIPP repository and other oversight actions are completed in order to inform all stakeholders of the status of the Department’s current plans and the effects of the suspension of WIPP operations.

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

    SciTech Connect (OSTI)

    NONE

    1997-04-14

    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.

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

    SciTech Connect (OSTI)

    KRISTOFZSKI, J.G.

    2000-10-26

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

  1. Intermediate depth burial of classified transuranic wastes in arid alluvium

    SciTech Connect (OSTI)

    Cochran, J.R. [Sandia National Labs., Albuquerque, NM (United States). Environmental Risk and Decision Analysis Dept.; Crowe, B.M. [Los Alamos National Lab., NM (United States). Geologic Integration Group; Di Sanza, F. [Dept. of Energy, Las Vegas, NV (United States). Nevada Operations Office

    1999-04-01

    Intermediate depth disposal operations were conducted by the US Department of Energy (DOE) at the DOE`s Nevada Test Site (NTS) from 1984 through 1989. These operations emplaced high-specific activity low-level wastes (LLW) and limited quantities of classified transuranic (TRU) wastes in 37 m (120-ft) deep, Greater Confinement Disposal (GCD) boreholes. The GCD boreholes are 3 m (10 ft) in diameter and founded in a thick sequence of arid alluvium. The bottom 15 m (50 ft) of each borehole was used for waste emplacement and the upper 21 m (70 ft) was backfilled with native alluvium. The bottom of each GCD borehole is almost 200 m (650 ft) above the water table. The GCD boreholes are located in one of the most arid portions of the US, with an average precipitation of 13 cm (5 inches) per year. The limited precipitation, coupled with generally warm temperatures and low humidities results in a hydrologic system dominated by evapotranspiration. The US Environmental Protection Agency`s (EPA`s) 40 CFR 191 defines the requirements for protection of human health from disposed TRU wastes. This EPA standard sets a number of requirements, including probabilistic limits on the cumulative releases of radionuclides to the accessible environment for 10,000 years. The DOE Nevada Operations Office (DOE/NV) has contracted with Sandia National Laboratories (Sandia) to conduct a performance assessment (PA) to determine if the TRU wastes emplaced in the GCD boreholes complies with the EPA`s 40 CFR 191 requirements. This paper describes DOE`s actions undertaken to evaluate whether the TRU wastes in the GCD boreholes will, or will not, endanger human health. Based on preliminary modeling, the TRU wastes in the GCD boreholes meet the EPA`s requirements, and are, therefore, protective of human health.

  2. Russian Experience in the Regulatory Supervision of the Uranium Legacy Sites - 12441

    SciTech Connect (OSTI)

    Kiselev, M.F.; Romanov, V.V.; Shandala, N.K.; Titov, A.V.; Kiselev, S.M.; Seregin, V.A.; Metlyaev, E.G.; Novikova, N.; Khokhlova, E.A.

    2012-07-01

    Management of the uranium legacy is accompanied with environmental impact intensity of which depends on the amount of the waste generated, the extent of that waste localization and environmental spreading. The question is: how hazardous is such impact on the environment and human health? The criterion for safety assurance is adequate regulation of the uranium legacy. Since the establishment of the uranium industry, the well done regulatory system operates in the FMBA of Russia. Such system covers inter alia, the uranium legacy. This system includes the extent laboratory network of independent control and supervision, scientific researches, regulative practices. The current Russian normative and legal basis of the regulation and its application practice has a number of problems relating to the uranium legacy, connected firstly with the environmental remediation. To improve the regulatory system, the urgent tasks are: -To introduce the existing exposure situation into the national laws and standards in compliance with the ICRP system. - To develop criteria for site remediation and return, by stages, to uncontrolled uses. The similar criteria have been developed within the Russian-Norwegian cooperation for the purpose of remediation of the sites for temporary storage of SNF and RW. - To consider possibilities and methods of optimization for the remediation strategies under development. - To separate the special category - RW resulted from uranium ore mining and dressing. The current Russian RW classification is based on the waste subdivision in terms of the specific activities. Having in mind the new RW-specific law, we receive the opportunity to separate some special category - RW originated from the uranium mining and milling. Introduction of such category can simplify significantly the situation with management of waste of uranium mining and milling processes. Such approach is implemented in many countries and approved by IAEA. The category of 'RW originated from uranium mining and milling' is to be introduced as the legal acts and regulatory documents. The recent ICRP recommendations provide the flexible approaches for solving of such tasks. The FMBA of Russia recognizes the problems of radiation safety assurance related to the legacy of the former USSR in the uranium mining industry. Some part of the regulatory problems assumes to be solved within the EurAsEC inter-state target program 'Reclamation of the territories of the EurAsEC member states affected by the uranium mining and milling facilities'. Using the example of the uranium legacy sites in Kyrgyz and Tajikistan which could result in the tran-boundary disasters and require urgent reclamation, the experience will be gained to be used in other states as well. Harmonization of the national legislations and regulative documents on radiation safety assurance is envisaged. (authors)

  3. Waste Isolation Pilot Plant (WIPP) Recovery | Department of Energy

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

    Waste Isolation Pilot Plant (WIPP) Recovery Waste Isolation Pilot Plant (WIPP) Recovery The U.S. Department of Energy’s (DOE) Waste Isolation Pilot Plant (WIPP) is a deep geologic repository for permanent disposal of a specific type of waste that is the byproduct of the nation's nuclear defense program. WIPP is the nation's only repository for the disposal of nuclear waste known as transuranic, or TRU, waste. Two incidents occurred in February 2014 that led to the current shutdown of the

  4. QA Objectives for Nondestructive Assay at the Waste Receiving & Processing (WRAP) Facility

    SciTech Connect (OSTI)

    CANTALOUB, M.G.

    2000-08-01

    The Waste Receiving and Processing (WRAP) facility, located on the Word Site in southeast Washington, is a key link in the certification of transuranic (TRU) waste for shipment to the Waste Isolation Pilot Plant (WIPP). Waste characterization is one of the vital functions performed at WRAP, and nondestructive assay (NDA) measurements of TRU waste containers is one of two required methods used for waste characterization. The Waste Acceptance Criteria for the Waste Isolation Pilot Plant, DOE/WIPP-069 (WIPP-WAC) delineates the quality assurance objectives which have been established for NDA measurement systems. Sites must demonstrate that the quality assurance objectives can be achieved for each radioassay system over the applicable ranges of measurement. This report summarizes the validation of the WRAP NDA systems against the radioassay quality assurance objectives or QAOs. A brief description of the each test and significant conclusions are included. Variables that may have affected test outcomes and system response are also addressed.

  5. QA Objectives for Nondestructive Assay at the Waste Receiving and Processing (WRAP) Facility

    SciTech Connect (OSTI)

    CANTALOUB, M.G.; WILLS, C.E.

    2000-03-24

    The Waste Receiving and Processing (WRAP) facility, located on the Hanford Site in southeast Washington, is a key link in the certification of transuranic (TRU) waste for shipment to the Waste Isolation Pilot Plant (WIPP). Waste characterization is one of the vital functions performed at WRAP, and nondestructive assay (NDA) measurements of TRU waste containers is one of two required methods used for waste characterization. The Waste Acceptance Criteria for the Waste Isolation Pilot Plant, DOEMPP-069 (WIPP-WAC) delineates the quality assurance objectives which have been established for NDA measurement systems. Sites must demonstrate that the quality assurance objectives can be achieved for each radioassay system over the applicable ranges of measurement. This report summarizes the validation of the WRAP NDA systems against the radioassay quality assurance objectives or QAOs. A brief description of the each test and significant conclusions are included. Variables that may have affected test outcomes and system response are also addressed.

  6. EP-AREAG-PLAN-1248, R.0 TA-54 Area G Nitrate-Salt Waste Container Response Instructions

    Office of Environmental Management (EM)

    EP-AREAG-PLAN-1248, R.0 TA-54 Area G Nitrate-Salt Waste Container Response Instructions Effective Date: 5/28/2014 The Responsible Manager has determined that the following organizations' review/concurrence is required for the initial document and for major revisions a same type and level review is required. Review documentation is contained in the Document History File: EWMO Engineering LANL TRU Programs - Shipping and Safe Storage Disposition LANL TRU Programs - Drum Disposition Project LANL

  7. WIPP Receives First Remote-Handled Waste Shipment From Sandia Labs

    Broader source: Energy.gov [DOE]

    CARLSBAD, N.M. – The U.S. Department of Energy’s (DOE) Waste Isolation Pilot Plant (WIPP) has received the first of eight planned defense-related remote-handled transuranic (RH-TRU) waste shipments from Sandia National Laboratories (SNL) in Albuquerque.

  8. Transient Safety Analysis of Fast Spectrum TRU Burning LWRs with Internal

    Office of Scientific and Technical Information (OSTI)

    Blankets (Technical Report) | SciTech Connect Transient Safety Analysis of Fast Spectrum TRU Burning LWRs with Internal Blankets Citation Details In-Document Search Title: Transient Safety Analysis of Fast Spectrum TRU Burning LWRs with Internal Blankets The objective of this proposal was to perform a detailed transient safety analysis of the Resource-Renewable BWR (RBWR) core designs using the U.S. NRC TRACE/PARCS code system. This project involved the same joint team that has performed the

  9. Waste Receiving and Processing Facility Module 1: Volume 1, Preliminary Design report

    SciTech Connect (OSTI)

    Not Available

    1992-03-01

    The Preliminary Design Report (Title 1) for the Waste Receiving and Processing (WRAP) Module 1 provides a comprehensive narrative description of the proposed facility and process systems, the basis for each of the systems design, and the engineering assessments that were performed to support the technical basis of the Title 1 design. The primary mission of the WRAP 1 Facility is to characterize and certify contact-handled (CH) waste in 55-gallon drums for disposal. Its secondary function is to certify CH waste in Standard Waste Boxes (SWBs) for disposal. The preferred plan consist of retrieving the waste and repackaging as necessary in the Waste Receiving and Processing (WRAP) facility to certify TRU waste for shipment to the Waste Isolation Pilot Plant (WIPP) in New Mexico. WIPP is a research and development facility designed to demonstrate the safe and environmentally acceptable disposal of TRU waste from National Defense programs. Retrieved waste found to be Low-Level Waste (LLW) after examination in the WRAP facility will be disposed of on the Hanford site in the low-level waste burial ground. The Hanford Site TRU waste will be shipped to the WIPP for disposal between 1999 and 2013.

  10. TRU TeamWorks 7-7-11

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

    7, 2011 WIPP Quick Facts (As of 7-6-11) 9,730 Shipments received since opening (9,234 CH and 496 RH) 75,969 Cubic meters of waste disposed (75,717 CH and 252 RH) 147,852 Containers disposed in the underground (147,357 CH and 495 RH) DOE completes cleanup at New York, California sites "Cleanup of these two sites represents important and continued progress in the Department of Energy's commitment to reducing the nation's nuclear waste footprint," said Assistant Secretary for

  11. DOE - Office of Legacy Management -- GrnRiv

    Office of Legacy Management (LM)

    to DOE for long-term custody and managed by the Office of Legacy Management. The site transferred to the Office of Legacy Management in 2003 and requires routine inspection and ...

  12. DOE - Office of Legacy Management -- MonValley

    Office of Legacy Management (LM)

    Act (UMTRCA) Title I site, is managed by the Office of Legacy Management. The site transferred to the Office of Legacy Management in 2003 and requires routine inspection and ...

  13. DOE - Office of Legacy Management -- Amchitka Island Test Center...

    Office of Legacy Management (LM)

    ... when a team led by the DOE Office of Legacy Management (LM) collected biological and ... LMSAMCS07053. March 2011 U.S. Department of Energy Office of Legacy Management Record of ...

  14. DOE - Office of Legacy Management -- Lake_D

    Office of Legacy Management (LM)

    to DOE for long-term custody and managed by the Office of Legacy Management. The site transferred to the Office of Legacy Management in 2003 and requires routine inspection and ...

  15. DOE - Office of Legacy Management -- Nat_D

    Office of Legacy Management (LM)

    to DOE for long-term custody and managed by the Office of Legacy Management. The site transferred to the Office of Legacy Management in 2003 and requires routine inspection and ...

  16. DOE - Office of Legacy Management -- Slick_P

    Office of Legacy Management (LM)

    to DOE for long-term custody and managed by the Office of Legacy Management. The site transferred to the Office of Legacy Management in 2003 and requires routine inspection and ...

  17. DOE - Office of Legacy Management -- Maybell_West(2)

    Office of Legacy Management (LM)

    to DOE for long-term custody and managed by the Office of Legacy Management. The site transferred to the Office of Legacy Management in 2010 and requires routine inspection and ...

  18. DOE - Office of Legacy Management -- Lake_P

    Office of Legacy Management (LM)

    to DOE for long-term custody and managed by the Office of Legacy Management. The site transferred to the Office of Legacy Management in 2003 and requires routine inspection and ...

  19. DOE - Office of Legacy Management -- SLC_D

    Office of Legacy Management (LM)

    to DOE for long-term custody and managed by the Office of Legacy Management. The site transferred to the Office of Legacy Management in 2003 and requires routine inspection and ...

  20. DOE - Office of Legacy Management -- Gun_D

    Office of Legacy Management (LM)

    to DOE for long-term custody and managed by the Office of Legacy Management. The site transferred to the Office of Legacy Management in 2003 and requires routine inspection and ...

  1. DOE - Office of Legacy Management -- Nat_P

    Office of Legacy Management (LM)

    to DOE for long-term custody and managed by the Office of Legacy Management. The site transferred to the Office of Legacy Management in 2003 and requires routine inspection and ...

  2. DOE - Office of Legacy Management -- Rifle_D

    Office of Legacy Management (LM)

    to DOE for long-term custody and managed by the Office of Legacy Management. The site transferred to the Office of Legacy Management in 2003 and requires routine inspection and ...

  3. DOE - Office of Legacy Management -- Mound Laboratory - OH 19

    Office of Legacy Management (LM)

    U.S. Department of Energy (DOE) Office of Legacy Management (LM) is conducting the fourth ... and current Office of Legacy Management activities at the Mound Site in Miamisburg, Ohio. ...

  4. Office of Legacy Management Tim Murphy, Chief Bureau of Federal...

    Office of Legacy Management (LM)

    Office of Legacy Management Tim Murphy, Chief Bureau of Federal Facilities Division of ... Murphy: On July 20, 2009, the U.S. Department of Energy, Office of Legacy Management ...

  5. DOE - Office of Legacy Management -- SLC_P

    Office of Legacy Management (LM)

    to DOE for long-term custody and managed by the Office of Legacy Management. The site transferred to the Office of Legacy Management in 2003 and requires routine inspection and ...

  6. DOE - Office of Legacy Management -- Gunnison Mill Site - CO...

    Office of Legacy Management (LM)

    ... DE-AC01-02GJ79491 for the U.S. Department of Energy Office of Legacy Management, Grand ... Processing Site September 2006 Office of Legacy Management DOE M1305-2006 -L Work ...

  7. DOE - Office of Legacy Management -- Dur_D

    Office of Legacy Management (LM)

    to DOE for long-term custody and managed by the Office of Legacy Management. The site transferred to the Office of Legacy Management in 2003 and requires routine inspection and ...

  8. DOE - Office of Legacy Management -- Slick Rock Mill Site - CO...

    Office of Legacy Management (LM)

    Sites, 2007 Update June 2008 Office of Legacy Management DOE M1577 2008 - -L Work Performed Under DOE Contract No. for the U.S. Department of Energy Office of Legacy Management. ...

  9. DOE - Office of Legacy Management -- Rifle_Old

    Office of Legacy Management (LM)

    to DOE for long-term custody and managed by the Office of Legacy Management. The site transferred to the Office of Legacy Management in 2003 and requires routine inspection and ...

  10. DOE - Office of Legacy Management -- Slick_D

    Office of Legacy Management (LM)

    to DOE for long-term custody and managed by the Office of Legacy Management. The site transferred to the Office of Legacy Management in 2003 and requires routine inspection and ...

  11. DOE - Office of Legacy Management -- Dur_P

    Office of Legacy Management (LM)

    to DOE for long-term custody and managed by the Office of Legacy Management. The site transferred to the Office of Legacy Management in 2003 and requires routine inspection and ...

  12. DOE - Office of Legacy Management -- Rifle_New

    Office of Legacy Management (LM)

    to DOE for long-term custody and managed by the Office of Legacy Management. The site transferred to the Office of Legacy Management in 2003 and requires routine inspection and ...

  13. DOE - Office of Legacy Management -- MexHat

    Office of Legacy Management (LM)

    to DOE for long-term custody and managed by the Office of Legacy Management. The site transferred to the Office of Legacy Management in 2003 and requires routine inspection and ...

  14. DOE - Office of Legacy Management -- Gun_P

    Office of Legacy Management (LM)

    to DOE for long-term custody and managed by the Office of Legacy Management. The site transferred to the Office of Legacy Management in 2003 and requires routine inspection and ...

  15. DRAFT EM SSAB Chairs Meeting Waste Disposition Strategies Update

    Energy Savers [EERE]

    EM HQ Updates Waste Disposition Overview Christine Gelles Associate Deputy Assistant Secretary for Waste Management Office of Environmental Management EM SSAB Chairs Meeting 5 November 2013 www.energy.gov/EM 2 * Waste Management Accomplishments and Priorities * National TRU Program Update * LLW/MLLW Disposal Update * Other Programmatic Updates * Disposition Maps - Current Tools Discussion Outline www.energy.gov/EM 3 FY13 Waste Management Accomplishments * WIPP: Emplaced 5,065 cubic meters of

  16. Defense Remote Handled Transuranic Waste Cost/Schedule Optimization Study

    SciTech Connect (OSTI)

    Pierce, G.D. . Joint Integration Office); Beaulieu, D.H. ); Wolaver, R.W.; Carson, P.H. Corp., Boulder, CO )

    1986-11-01

    The purpose of this study is to provide the DOE information with which it can establish the most efficient program for the long management and disposal, in the Waste Isolation Pilot Plant (WIPP), of remote handled (RH) transuranic (TRU) waste. To fulfill this purpose, a comprehensive review of waste characteristics, existing and projected waste inventories, processing and transportation options, and WIPP requirements was made. Cost differences between waste management alternatives were analyzed and compared to an established baseline. The result of this study is an information package that DOE can use as the basis for policy decisions. As part of this study, a comprehensive list of alternatives for each element of the baseline was developed and reviewed with the sites. The principle conclusions of the study follow. A single processing facility for RH TRU waste is both necessary and sufficient. The RH TRU processing facility should be located at Oak Ridge National Laboratory (ORNL). Shielding of RH TRU to contact handled levels is not an economic alternative in general, but is an acceptable alternative for specific waste streams. Compaction is only cost effective at the ORNL processing facility, with a possible exception at Hanford for small compaction of paint cans of newly generated glovebox waste. It is more cost effective to ship certified waste to WIPP in 55-gal drums than in canisters, assuming a suitable drum cask becomes available. Some waste forms cannot be packaged in drums, a canister/shielded cask capability is also required. To achieve the desired disposal rate, the ORNL processing facility must be operational by 1996. Implementing the conclusions of this study can save approximately $110 million, compared to the baseline, in facility, transportation, and interim storage costs through the year 2013. 10 figs., 28 tabs.

  17. 2013-08 "Waste Isolation Pilot Plant Storage for LANL"

    Broader source: Energy.gov [DOE]

    Approved July 31, 2013 The intent of this recommendation is that DOE/EM and WIPP set their priorities for the remaining storage facilities at WIPP to ensure that there will be enough capacity to hold all TRU waste remaining at LANL and that the current disposal schedules can be met.

  18. Generating code adapted for interlinking legacy scalar code and extended

    Office of Scientific and Technical Information (OSTI)

    vector code (Patent) | SciTech Connect Generating code adapted for interlinking legacy scalar code and extended vector code Citation Details In-Document Search Title: Generating code adapted for interlinking legacy scalar code and extended vector code Mechanisms for intermixing code are provided. Source code is received for compilation using an extended Application Binary Interface (ABI) that extends a legacy ABI and uses a different register configuration than the legacy ABI. First compiled

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

    SciTech Connect (OSTI)

    Gregory J. Shott; Vefa Yucel

    2009-07-16

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

  20. MRI Beginnings - a Legacy | GE Global Research

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

    From Nobel Ideas to Industrial Success - Bill Edelstein's Legacy Click to email this to a friend (Opens in new window) Share on Facebook (Opens in new window) Click to share (Opens in new window) Click to share on LinkedIn (Opens in new window) Click to share on Tumblr (Opens in new window) From Nobel Ideas to Industrial Success - Bill Edelstein's Legacy Scott Smith 2014.06.13 Edelstein_with-MRmachine Nuclear magnetic resonance (NMR) was discovered in the late 1940s by groups at Harvard and

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

    Broader source: Energy.gov [DOE]

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

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

    Broader source: Energy.gov [DOE]

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

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

    Broader source: Energy.gov [DOE]

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

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

    Broader source: Energy.gov [DOE]

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

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

    SciTech Connect (OSTI)

    Permana, Sidik; Suzuki, Mitsutoshi; Su'ud, Zaki

    2012-06-06

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

  6. Plasma filtering techniques for nuclear waste remediation

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Gueroult, Renaud; Hobbs, David T.; Fisch, Nathaniel J.

    2015-04-24

    Nuclear waste cleanup is challenged by the handling of feed stocks that are both unknown and complex. Plasma filtering, operating on dissociated elements, offers advantages over chemical methods in processing such wastes. The costs incurred by plasma mass filtering for nuclear waste pretreatment, before ultimate disposal, are similar to those for chemical pretreatment. However, significant savings might be achieved in minimizing the waste mass. As a result, this advantage may be realized over a large range of chemical waste compositions, thereby addressing the heterogeneity of legacy nuclear waste.

  7. Microsoft Word - Draft M-91 4-23 commentsmergedocx-nw.docx

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

    Transuranic (TRU) waste is radioactive waste containing more than 100 nanocuries of alpha-emitting transuranic isotopes, with half-lives greater than 20 years, per gram of waste (alpha particles are given off by the decay of many elements, e.g., uranium, plutonium, and radon). Legacy TRU waste is that waste in storage as of January, 2003. Transuranic Mixed (TRUM) waste is TRU waste that contains both radiological and hazardous (e.g., chemical) components that are subject to RCRA or the Dangerous

  8. LM-04-XXXX Office of Legacy Management

    Energy Savers [EERE]

    LM-04-XXXX Office of Legacy Management Information and Records Management Transition Guidance March 2004 LM Information and Records Management Transition Guidance March 2004 Contents Page ii Table of Contents Page Executive Summary................................................................................................................... iii 1.0 Introduction and Purpose ................................................................................................... 1 2.0 The Life Cycle

  9. Waste Isolation Pilot Plant Annual Site Enviromental Report for 2008

    SciTech Connect (OSTI)

    Washington Regulatory and Enviromnetal Services

    2009-09-21

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

  10. Settlement Agreement on TRU Mixed Waste Storage at Nevada Test Site

    Office of Environmental Management (EM)

    Department of Energy EAC 2014 Meetings » September 24 & 25, 2014 Meeting of the Electricity Advisory Committee September 24 & 25, 2014 Meeting of the Electricity Advisory Committee September 24 & 25, 2014 Meeting of the Electricity Advisory Committee Date: Wednesday, September 24, 2014 12:00 p.m. - 5:30 p.m. EDT Date: Thursday, September 25, 2014 8:00 a.m. - 4:00 p.m. EDT Location: National Rural Electric Cooperative Association (NRECA), 4301 Wilson Blvd, Arlington, VA 22203

  11. EP-AREAG-G-FO-DOP-124 Nitrate Salt Bearing TRU Waste Container Monitoring.pdf

    Office of Environmental Management (EM)

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

    Office of Environmental Management (EM)

    Contacts for the Advanced Manufacturing Office Contacts for the Advanced Manufacturing Office Welcome to the Advanced Manufacturing Office (AMO). Our address, email, and phone number are provided below. U.S. Department of Energy - Advanced Manufacturing Office (formerly Industrial Technologies Program) Room 5F-065, MS EE-5A 1000 Independence Ave, SW Washington, DC 20585 Phone: (202) 586-9488 Nearest Metro stop: Smithsonian (blue/orange line) Get directions Website Contact: Send us your comments,

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

    Office of Environmental Management (EM)

    of Energy Investigates Port Readiness for Offshore Wind New DOE Report Investigates Port Readiness for Offshore Wind October 1, 2013 - 1:22pm Addthis This is an excerpt from the Third Quarter 2013 edition of the Wind Program R&D Newsletter. Rows of wind turbine towers, nacelles, and blades line a port staging area. As offshore wind energy develops in the United States, port facilities will become strategic hubs in the offshore wind farm supply chain, because all plant and transport

  14. TRU TeamWorks - a biweekly e-newsletter for the Waste Isolation...

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

    WIPP security officers with Santa Fe Protective Services (SFPS) Inc. will soon add guns to their security belts. Many employees remember the early days at WIPP when security...

  15. PUBLIC AND REGULATORY ACCEPTANCE OF BLENDING OF RADIOACTIVE WASTE VS DILUTION

    SciTech Connect (OSTI)

    Goldston, W.

    2010-11-30

    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.

  16. DOE complex buried waste characterization assessment

    SciTech Connect (OSTI)

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

    1993-01-01

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

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

    SciTech Connect (OSTI)

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

    2013-09-01

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

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

    SciTech Connect (OSTI)

    Brann, E.C. II

    1994-09-09

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

  19. 2011-07 "Maximum Utilization of WIPP by Increasing MDA G TRU Shipments" |

    Office of Environmental Management (EM)

    Department of Energy 7 "Maximum Utilization of WIPP by Increasing MDA G TRU Shipments" 2011-07 "Maximum Utilization of WIPP by Increasing MDA G TRU Shipments" The intent of this recommendation is to ensure optimization of WIPP shipment schedules while helping to keep commitments to Consent Order milestones at MDA-G. PDF icon Rec 2011-07

  20. Characterization of the BVEST waste tanks located at ORNL

    SciTech Connect (OSTI)

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

    1997-01-01

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

  1. Conceptual study of measures against heat generation for TRU fuel fabrication system

    SciTech Connect (OSTI)

    Kawaguchi, Koichi; Namekawa, Takashi

    2007-07-01

    To lower the reprocessing cost and the environmental burden, the Japan Atomic Energy Agency (JAEA) has developed low decontamination TRU fuel fabrication system. TRU fuel contains MA of 1.2 to 5 wt% and its decay heat is estimated a few tens W/kg-HM. As the heat affects fuel quality through oxidation of fuel material and members, it is necessary to remove decay heat. In this work, authors designed concepts of the measures against heat generation at typical equipments using with the thermal hydraulics analysis technique. As a result, it is shown that it is possible to cool fuel materials with specific heat generation up to 20 W/kg-HM enough, though more detailed study is required for comprehensive equipments. (authors)

  2. General Atomics Final Drum of Legacy Mixed Wastes.

    Office of Legacy Management (LM)

  3. DOE - Office of Legacy Management -- Waste Isolation Pilot Plant...

    Office of Legacy Management (LM)

    After more than 20 years of scientific study and public input, WIPP began operations on ... in a 2,000-foot thick salt formation that has been stable for 200 million years. ...

  4. Solid Waste Assurance Program Implementation Plan

    SciTech Connect (OSTI)

    Irons, L.G.

    1995-06-19

    On June 6, 1995, a waiver to Hanford Site Solid Waste Acceptance Criteria, was approved by the US Department of Energy Richland Operations Office (RL) to replace the low-level, mixed, and transuranic (TRU) generator assessment programs with the Solid Waste Assurance Program (SWAP). This is associated with a waiver that was approved on March 16, 1995 to replace the Storage/Disposal Approval Record (SDAR) requirements with the Waste Specification System (WSS). This implementation plan and the SWAP applies to Solid Waste Disposal (SWD) functions, facilities, and personnel who perform waste acceptance, verification, receipt, and management functions of dangerous, radioactive, and mixed waste from on- and off-site generators who ship to or within the Hanford Site for treatment, storage, and/or disposal (TSD) at SWD TSD facilities.

  5. Waste Isolation Pilot Plant 2005 Site Environmental Report

    SciTech Connect (OSTI)

    Washington Regulatory and Environmental Services

    2006-10-13

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

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

    SciTech Connect (OSTI)

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

    1980-01-01

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

  7. Office of Legacy Management | Department of Energy

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

    Office of Legacy Management Abandoned Uranium Mines Abandoned Uranium Mines Read more Amchitka, Alaska, Site Amchitka, Alaska, Site Read more Mexican Hat, Utah, Disposal Site Mexican Hat, Utah, Disposal Site Read more Tuba City, Arizona, Disposal Site Tuba City, Arizona, Disposal Site Read more Rifle, Colorado, Disposal Site Rifle, Colorado, Disposal Site Read more Announcements LM has issued the Notice of LEHR CERCLA Five-Year Review. Guidance for Developing and Implementing Institutional

  8. 2014 Annual Planning Summary for the Office of Legacy Management |

    Energy Savers [EERE]

    Department of Energy Legacy Management 2014 Annual Planning Summary for the Office of Legacy Management The ongoing and projected Environmental Assessments and Environmental Impact Statements for 2014 and 2015 within the Office of Legacy Management.. PDF icon LM-NEPA-APS-2014.pdf More Documents & Publications 2014 Annual Planning Summary for the Oak Ridge Office of Environmental Management 2014 Annual Planning Summary for the NNSA Production Office 2014 Annual Planning Summary for the

  9. November 2015 Newsletter - Los Alamos Field Office Legacy Cleanup |

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

    Department of Energy November 2015 Newsletter - Los Alamos Field Office Legacy Cleanup November 2015 Newsletter - Los Alamos Field Office Legacy Cleanup November 30, 2015 - 12:00pm Addthis TA-21-286 being demolished TA-21-286 being demolished Safety Safety and health record for October is clean Safe storage plan for nitrate salts has been completed and implemented. Contracts/Acquisition Removing concrete at the airport landfill Los Alamos Legacy Cleanup Bridge Contract commenced October 1

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

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

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

  11. DOE - Office of Legacy Management -- Madison_FUSRAP

    Office of Legacy Management (LM)

    The site transferred to the Office of Legacy Management in 2003 and long-term surveillance and maintenance requirements consist of preserving site records and responding to ...

  12. DOE - Office of Legacy Management -- Riverton Mill Site - WY...

    Office of Legacy Management (LM)

    Control Act (UMTRCA) Title I Site April Gil, PhD Environment Team Lead Office of Legacy Management (LM) May 2, 20122 Status and Action Summary Surface Remediation ...

  13. DOE - Office of Legacy Management -- Bayo_FUSRAP

    Office of Legacy Management (LM)

    in conjunction with cleanup activities for the entire Los Alamos site. Office of Legacy Management activities consist of managing site records and responding to stakeholder ...

  14. DOE - Office of Legacy Management -- Gen_Atomics

    Office of Legacy Management (LM)

    After remediation, the site transferred to the Office of Legacy Management in 2005. The site requires records management and stakeholder support. For more information about the ...

  15. DOE - Office of Legacy Management -- Pinellas Plant General Electric...

    Office of Legacy Management (LM)

    of the Pinellas County, Florida, Site Office of Legacy Management Pinellas County, Florida, Site This fact sheet provides information about the Pinellas County, Florida, Site. ...

  16. DOE - Office of Legacy Management -- ChicSouth_FUSRAP

    Office of Legacy Management (LM)

    owned site, and DOE does not require on-site monitoring or surveillance. Office of Legacy Management activities consist of managing site records and responding to stakeholder ...

  17. DOE - Office of Legacy Management -- Hallam Nuclear Power Facility...

    Office of Legacy Management (LM)

    was successfully conducted on April 29, 2009. The inspectio FACT SHEET Office of Legacy Management Location of the Hallam Decommissioned Reactor Hallam, Nebraska, ...

  18. DOE - Office of Legacy Management -- Maybell Mill Site - CO 0...

    Office of Legacy Management (LM)

    Cell Design, and Program Act Long-Term Surveillance Plan for the Maybell, Colorado (UMTRCA Title I) Disposal Site Moffat County, Colorado April 2008 Office of Legacy Management

  19. DOE - Office of Legacy Management -- Ambrosia Lake Mill Site...

    Office of Legacy Management (LM)

    Surveillance Plan (LTSP) for the Ambrosia Lake, New Mexico Site. FACT SHEET Office of Legacy Management Ambrosia Lake, New Mexico, Disposal Site This fact sheet provides ...

  20. DOE - Office of Legacy Management -- Oxford_FUSRAP

    Office of Legacy Management (LM)

    Office of Legacy Management activities consist of managing site records and responding to stakeholder inquiries. For more information about the Oxford Site, view the fact sheet. ...