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


1

Transuranic Waste Processing Center Contract Awarded to Wastren...  

Office of Environmental Management (EM)

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

2

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

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

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

3

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

Office of Environmental Management (EM)

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

4

Process to separate transuranic elements from nuclear waste  

DOE Patents [OSTI]

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

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

1989-01-01T23:59:59.000Z

5

Transuranic Waste Processing Center Oak Ridge Site Specific...  

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

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

6

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

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

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

7

Independent Oversight Review, Oak Ridge Transuranic Waste Processing  

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

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

8

Independent Oversight Review, Oak Ridge Transuranic Waste Processing  

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

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

9

Process to separate transuranic elements from nuclear waste  

DOE Patents [OSTI]

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

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

1989-03-21T23:59:59.000Z

10

Process to separate transuranic elements from nuclear waste  

DOE Patents [OSTI]

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

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

1988-07-12T23:59:59.000Z

11

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.

12

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

Broader source: Energy.gov [DOE]

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

13

Voluntary Protection Program Onsite Review, Transuranic Waste...  

Energy Savers [EERE]

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

14

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

Broader source: Energy.gov [DOE]

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

15

Process Simulation as Applied to Transuranic Waste Management  

SciTech Connect (OSTI)

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

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

1999-01-01T23:59:59.000Z

16

Transuranic Waste Requirements  

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

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

1999-07-09T23:59:59.000Z

17

Transuranic Waste Transportation Working Group Agenda | Department...  

Office of Environmental Management (EM)

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

18

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.

19

Transuranic (TRU) Waste | Department of Energy  

Office of Environmental Management (EM)

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

20

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

SciTech Connect (OSTI)

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

DEROSA, D.C.

2000-01-13T23:59:59.000Z

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


21

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

Broader source: Energy.gov [DOE]

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

22

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

SciTech Connect (OSTI)

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

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

2010-02-01T23:59:59.000Z

23

Transuranic Waste Tabletop  

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

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

24

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

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

and Fire Protection Systems and Fire Protection Systems at the Transuranic Waste Processing Center December 2013 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U. S. Department of Energy Table of Contents 1.0 Purpose.................................................................................................................................................... 1 2.0 Background ............................................................................................................................................. 1 3.0 Scope....................................................................................................................................................... 2 4.0 Methodology .......................................................................................................................................... 2

25

Transuranic waste: long-term planning  

SciTech Connect (OSTI)

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

Young, K.C.

1985-07-01T23:59:59.000Z

26

Waste Processing | Department of Energy  

Office of Environmental Management (EM)

Processing Waste Processing Workers process and repackage waste at the Transuranic Waste Processing Centers Cask Processing Enclosure. Workers process and repackage waste at...

27

Annual Transuranic Waste Inventory Report - 2013  

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

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

28

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

Office of Environmental Management (EM)

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

29

Hanford Site Transuranic (TRU) Waste Certification Plan  

SciTech Connect (OSTI)

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

GREAGER, T.M.

1999-09-09T23:59:59.000Z

30

Hanford Site Transuranic (TRU) Waste Certification Plan  

SciTech Connect (OSTI)

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

GREAGER, T.M.

1999-12-14T23:59:59.000Z

31

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

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

Management of Safety Systems at the Oak Ridge Transuranic Waste Processing Center and Associated Feedback and Improvement Processes May 2011 February 2013 September 2013 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U. S. Department of Energy Table of Contents 1.0 Purpose.................................................................................................................................................... 1 2.0 Background ............................................................................................................................................. 1 3.0 Scope....................................................................................................................................................... 2

32

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

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

Management of Safety Systems at the Oak Ridge Transuranic Waste Processing Center and Associated Feedback and Improvement Processes May 2011 February 2013 September 2013 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U. S. Department of Energy Table of Contents 1.0 Purpose.................................................................................................................................................... 1 2.0 Background ............................................................................................................................................. 1 3.0 Scope....................................................................................................................................................... 2

33

Transuranic Waste Tabletop | Department of Energy  

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

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

34

Transuranic Waste Characterization Quality Assurance Program Plan  

SciTech Connect (OSTI)

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

NONE

1995-04-30T23:59:59.000Z

35

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

SciTech Connect (OSTI)

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

GREAGER, T.M.

1999-09-09T23:59:59.000Z

36

Remote-handled transuranic waste study  

SciTech Connect (OSTI)

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

NONE

1995-10-01T23:59:59.000Z

37

Repackaging Rocky Flats Legacy Transuranic Waste  

SciTech Connect (OSTI)

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

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

2008-01-15T23:59:59.000Z

38

Combined transuranic-strontium extraction process  

DOE Patents [OSTI]

The transuranic (TRU) elements neptunium, plutonium and americium can be separated together with strontium from nitric acid waste solutions in a single process. An extractant solution of a crown ether and an alkyl(phenyl)-N,N-dialkylcarbanylmethylphosphine oxide in an appropriate diluent will extract the TRU's together with strontium, uranium and technetium. The TRU's and the strontium can then be selectively stripped from the extractant for disposal.

Horwitz, E. Philip (Naperville, IL); Dietz, Mark L. (Evanston, IL)

1992-01-01T23:59:59.000Z

39

Transuranic waste form characterization and data base. Executive summary  

SciTech Connect (OSTI)

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

Not Available

1980-09-30T23:59:59.000Z

40

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

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

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

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


41

Hanford site transuranic waste sampling plan  

SciTech Connect (OSTI)

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

GREAGER, T.M.

1999-05-13T23:59:59.000Z

42

Annual Transuranic Waste Inventory Report - 2013  

Office of Environmental Management (EM)

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

43

Hanford site transuranic waste certification plan  

SciTech Connect (OSTI)

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

GREAGER, T.M.

1999-05-12T23:59:59.000Z

44

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

SciTech Connect (OSTI)

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

Not Available

1993-12-01T23:59:59.000Z

45

MANAGEMENT ALERT Remediation of Selected Transuranic Waste Drums...  

Office of Environmental Management (EM)

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

46

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

SciTech Connect (OSTI)

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

GREAGER, T.M.

2000-12-06T23:59:59.000Z

47

Transuranic contaminated waste form characterization and data base  

SciTech Connect (OSTI)

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

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

1980-07-01T23:59:59.000Z

48

Transuranic Waste Transportation Working Group Agenda  

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

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

49

In situ vitrification: application analysis for stabilization of transuranic waste  

SciTech Connect (OSTI)

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

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

1982-09-01T23:59:59.000Z

50

Los Alamos National Laboratory Accelerates Transuranic Waste Shipments:  

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

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

51

EM Makes Significant Progress on Dispositioning Transuranic Waste at Idaho  

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

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

52

EM Makes Significant Progress on Dispositioning Transuranic Waste at Idaho  

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

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

53

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

SciTech Connect (OSTI)

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

GREAGER, T.M.

1999-12-14T23:59:59.000Z

54

D11 WASTE DISPOSAL FACILITIES FOR TRANSURANIC WASTE  

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

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

55

Transuranic waste baseline inventory report. Revision No. 3  

SciTech Connect (OSTI)

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

NONE

1996-06-01T23:59:59.000Z

56

Contact-Handled and Remote-Handled Transuranic Waste Packaging  

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

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

2011-08-09T23:59:59.000Z

57

DESTRUCTION TECHNOLOGY DEMONSTRATION FOR ORGANICS IN TRANSURANIC WASTE  

SciTech Connect (OSTI)

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

Mike Spritzer

2003-02-01T23:59:59.000Z

58

Idaho Workers Complete Last of Transuranic Waste Transfers Funded by  

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

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

59

Savannah River Site Achieves Transuranic Waste Disposition Goal in 2013 |  

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

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

60

New facility boosts Lab's ability to ship transuranic waste  

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

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

Note: This page contains sample records for the topic "transuranic waste processing" from the National Library of EnergyBeta (NLEBeta).
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61

Los Alamos National Laboratory Transuranic Waste Program Exceeds Planned  

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

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

62

Waste management facilities cost information for transuranic waste  

SciTech Connect (OSTI)

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

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

1995-06-01T23:59:59.000Z

63

DOE Seeks Trucking Services for Transuranic Waste Shipments | Department of  

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

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

64

Transuranic waste characterization sampling and analysis methods manual  

SciTech Connect (OSTI)

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

NONE

1995-05-01T23:59:59.000Z

65

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

SciTech Connect (OSTI)

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

NONE

1995-07-01T23:59:59.000Z

66

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

Office of Environmental Management (EM)

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

67

Final Transuranic Waste Shipment Leaves Rocky Flats | Department of Energy  

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

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

68

Oak Ridge National Laboratory Transuranic Waste Certification Program  

SciTech Connect (OSTI)

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

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

1988-08-01T23:59:59.000Z

69

Accelerating the disposition of transuranic waste from LANL - 9495  

SciTech Connect (OSTI)

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

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

2009-01-01T23:59:59.000Z

70

Keeping Track of the National Transuranic Program Complex Defense Transuranic Waste  

SciTech Connect (OSTI)

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

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

2007-07-01T23:59:59.000Z

71

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

SciTech Connect (OSTI)

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

NONE

1995-02-01T23:59:59.000Z

72

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

SciTech Connect (OSTI)

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

Anastas, G.; Channell, J. K.

2002-02-26T23:59:59.000Z

73

Documentation of acceptable knowledge for LANL Plutonium Facility transuranic waste streams  

SciTech Connect (OSTI)

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

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

1998-07-01T23:59:59.000Z

74

A new DOE standard for transuranic waste nuclear safety analysis  

SciTech Connect (OSTI)

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

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

2007-07-01T23:59:59.000Z

75

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

SciTech Connect (OSTI)

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

NONE

1995-02-01T23:59:59.000Z

76

Transuranic (TRU) Waste Phase I Retrieval Plan  

SciTech Connect (OSTI)

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

MCDONALD, K.M.

1999-08-27T23:59:59.000Z

77

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

SciTech Connect (OSTI)

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

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

1996-03-01T23:59:59.000Z

78

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

SciTech Connect (OSTI)

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

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

1983-01-01T23:59:59.000Z

79

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

SciTech Connect (OSTI)

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

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

1982-01-01T23:59:59.000Z

80

Certification document for newly generated contact-handled transuranic waste  

SciTech Connect (OSTI)

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

Box, W.D.; Setaro, J.

1984-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "transuranic waste processing" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
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We encourage you to perform a real-time search of NLEBeta
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81

Long-range master plan for defense transuranic waste management  

SciTech Connect (OSTI)

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

Not Available

1988-12-01T23:59:59.000Z

82

Annual Transuranic Waste Inventory Report - 2013  

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

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

83

Waste Isolation Pilot Plant, National Transuranic Program Have Banner Year  

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

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

84

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

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

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

85

Transuranic waste characterization sampling and analysis methods manual. Revision 1  

SciTech Connect (OSTI)

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

Suermann, J.F.

1996-04-01T23:59:59.000Z

86

Identification of potential transuranic waste tanks at the Hanford Site  

SciTech Connect (OSTI)

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

Colburn, R.P.

1995-05-05T23:59:59.000Z

87

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

SciTech Connect (OSTI)

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

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

2010-01-01T23:59:59.000Z

88

Transuranic (TRU) Waste Phase I Retrieval Plan  

SciTech Connect (OSTI)

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

MCDONALD, K.M.

2000-09-28T23:59:59.000Z

89

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

SciTech Connect (OSTI)

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

WINTERHALDER, J.A.

1999-09-29T23:59:59.000Z

90

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

SciTech Connect (OSTI)

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

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

1992-05-01T23:59:59.000Z

91

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

SciTech Connect (OSTI)

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

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

1992-05-01T23:59:59.000Z

92

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

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

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

93

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

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

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

94

Safer Transportation and Disposal of Remote Handled Transuranic Waste - 12033  

SciTech Connect (OSTI)

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

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

2012-07-01T23:59:59.000Z

95

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

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

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

96

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

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

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

97

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

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

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

98

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

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

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

99

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

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

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

100

DOE Announces Preference for Disposal of Hanford Transuranic Tank Waste at  

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

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

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


101

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

SciTech Connect (OSTI)

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

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

2009-01-01T23:59:59.000Z

102

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

SciTech Connect (OSTI)

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

NONE

1997-04-14T23:59:59.000Z

103

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

SciTech Connect (OSTI)

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

Unknown

2001-08-31T23:59:59.000Z

104

SUPPLEMENT ANALYSIS OF TRANSURANIC WASTE CHARACTERIZATION AND REPACKAGING A  

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

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

105

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

National Nuclear Security Administration (NNSA)

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

106

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

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

Facility Saves $20 Million, Accelerates Waste Processing 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 will accelerate the completion of remote-handled transuranic (TRU) waste processing at the site by two years and save taxpayers more than $20 million. The new Cask Processing Enclosure (CPE) facility is located at the Transuranic Waste Processing Center (TWPC). TWPC processes, repackages, and

107

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

SciTech Connect (OSTI)

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

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

1994-03-01T23:59:59.000Z

108

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

SciTech Connect (OSTI)

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

Not Available

1988-08-01T23:59:59.000Z

109

Waste immobilization process development at the Savannah River Plant  

SciTech Connect (OSTI)

Processes to immobilize various wasteforms, including waste salt solution, transuranic waste, and low-level incinerator ash, are being developed. Wasteform characteristics, process and equipment details, and results from field/pilot tests and mathematical modeling studies are discussed.

Charlesworth, D L

1986-01-01T23:59:59.000Z

110

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

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

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

111

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

SciTech Connect (OSTI)

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

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

1997-04-01T23:59:59.000Z

112

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

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

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

113

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

SciTech Connect (OSTI)

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

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

1997-02-03T23:59:59.000Z

114

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

SciTech Connect (OSTI)

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

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

2003-02-27T23:59:59.000Z

115

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

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

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

116

An assessment of the flammability and explosion potential of transuranic waste  

SciTech Connect (OSTI)

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

Silva, M.

1991-06-01T23:59:59.000Z

117

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

SciTech Connect (OSTI)

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

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

1993-01-01T23:59:59.000Z

118

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

SciTech Connect (OSTI)

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

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

1993-02-01T23:59:59.000Z

119

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

SciTech Connect (OSTI)

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

Washington TRU Solutions LLC

2005-12-29T23:59:59.000Z

120

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

SciTech Connect (OSTI)

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

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

1990-08-01T23:59:59.000Z

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


121

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

Energy Savers [EERE]

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

122

Savannah River Site Achieves Transuranic Waste Disposition Goal...  

Office of Environmental Management (EM)

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

123

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

SciTech Connect (OSTI)

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

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

1994-09-01T23:59:59.000Z

124

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

SciTech Connect (OSTI)

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

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

2008-04-01T23:59:59.000Z

125

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

SciTech Connect (OSTI)

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

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

2008-07-01T23:59:59.000Z

126

Thermal processing systems for TRU mixed waste  

SciTech Connect (OSTI)

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

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

1992-01-01T23:59:59.000Z

127

Thermal processing systems for TRU mixed waste  

SciTech Connect (OSTI)

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

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

1992-08-01T23:59:59.000Z

128

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

SciTech Connect (OSTI)

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

Anastas, G.; Walker, B.A.

2003-02-24T23:59:59.000Z

129

Transuranic contaminated waste container characterization and data base. Revision I  

SciTech Connect (OSTI)

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

Kniazewycz, B.G.

1980-05-01T23:59:59.000Z

130

Construction Begins on New Waste Processing Facility | Department of Energy  

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

Construction Begins on New Waste Processing Facility Construction Begins on New Waste Processing Facility Construction Begins on New Waste Processing Facility February 9, 2012 - 12:00pm Addthis Workers construct a new facility that will help Los Alamos National Laboratory accelerate the shipment of transuranic (TRU) waste to the Waste Isolation Pilot Plant (WIPP) in Carlsbad for permanent disposal. Workers construct a new facility that will help Los Alamos National Laboratory accelerate the shipment of transuranic (TRU) waste to the Waste Isolation Pilot Plant (WIPP) in Carlsbad for permanent disposal. Construction has begun on a new facility that will help Los Alamos National Laboratory accelerate the shipment of transuranic (TRU) waste stored in large boxes at Technical Area 54, Area G. Construction has begun on a new facility that will help Los Alamos National

131

Characteristics of transuranic waste at Department of Energy sites  

SciTech Connect (OSTI)

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

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

1983-05-01T23:59:59.000Z

132

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

SciTech Connect (OSTI)

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

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

2006-01-19T23:59:59.000Z

133

Gas generation results and venting study for transuranic waste drums  

SciTech Connect (OSTI)

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

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

1985-09-23T23:59:59.000Z

134

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

SciTech Connect (OSTI)

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

Not Available

1990-02-01T23:59:59.000Z

135

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

SciTech Connect (OSTI)

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

Not Available

1980-10-01T23:59:59.000Z

136

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

SciTech Connect (OSTI)

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

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

2002-02-26T23:59:59.000Z

137

Recommended strategy for the disposal of remote-handled transuranic waste  

SciTech Connect (OSTI)

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

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

1994-07-01T23:59:59.000Z

138

Transuranic Waste Program Framework Agreement - December Deliverable July 2012  

SciTech Connect (OSTI)

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

Jones, Patricia [Los Alamos National Laboratory

2012-07-19T23:59:59.000Z

139

Application of cryogenic grinding to achieve homogenization of transuranic wastes  

SciTech Connect (OSTI)

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

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

1996-08-01T23:59:59.000Z

140

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

SciTech Connect (OSTI)

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

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

2008-07-01T23:59:59.000Z

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


141

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

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

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

142

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

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

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

143

Magnetically assisted chemical separation (MACS) process: Preparation and optimization of particles for removal of transuranic elements  

SciTech Connect (OSTI)

The Magnetically Assisted Chemical Separation (MACS) process combines the selectivity afforded by solvent extractants with magnetic separation by using specially coated magnetic particles to provide a more efficient chemical separation of transuranic (TRU) elements, other radionuclides, and heavy metals from waste streams. Development of the MACS process uses chemical and physical techniques to elucidate the properties of particle coatings and the extent of radiolytic and chemical damage to the particles, and to optimize the stages of loading, extraction, and particle regeneration. This report describes the development of a separation process for TRU elements from various high-level waste streams. Polymer-coated ferromagnetic particles with an adsorbed layer of octyl(phenyl)-N,N-diisobutylcarbamoylmethylphosphine oxide (CMPO) diluted with tributyl phosphate (TBP) were evaluated for use in the separation and recovery of americium and plutonium from nuclear waste solutions. Due to their chemical nature, these extractants selectively complex americium and plutonium contaminants onto the particles, which can then be recovered from the solution by using a magnet. The partition coefficients were larger than those expected based on liquid[liquid extractions, and the extraction proceeded with rapid kinetics. Extractants were stripped from the particles with alcohols and 400-fold volume reductions were achieved. Particles were more sensitive to acid hydrolysis than to radiolysis. Overall, the optimization of a suitable NMCS particle for TRU separation was achieved under simulant conditions, and a MACS unit is currently being designed for an in-lab demonstration.

Nunez, L.; Kaminski, M.; Bradley, C.; Buchholz, B.A.; Aase, S.B.; Tuazon, H.E.; Vandegrift, G.F. [Argonne National Lab., IL (United States); Landsberger, S. [Univ. of Illinois, Urbana, IL (United States)

1995-05-01T23:59:59.000Z

144

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

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

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

145

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

SciTech Connect (OSTI)

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

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

1999-02-01T23:59:59.000Z

146

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

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

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

147

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

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

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

148

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

SciTech Connect (OSTI)

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

Trabalka, J.R.

1997-09-01T23:59:59.000Z

149

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

SciTech Connect (OSTI)

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

GREENWLL, R.D.

2005-01-20T23:59:59.000Z

150

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

SciTech Connect (OSTI)

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

Not Available

1990-10-26T23:59:59.000Z

151

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

SciTech Connect (OSTI)

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

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

2008-07-01T23:59:59.000Z

152

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

SciTech Connect (OSTI)

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

Not Available

1989-01-01T23:59:59.000Z

153

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

SciTech Connect (OSTI)

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

Not Available

1989-01-01T23:59:59.000Z

154

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

SciTech Connect (OSTI)

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

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

1991-08-01T23:59:59.000Z

155

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

SciTech Connect (OSTI)

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

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

2008-07-01T23:59:59.000Z

156

WIPP TRANSURANIC WASTE How has the WIPP TRU Waste Inventory Changed  

E-Print Network [OSTI]

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

157

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

SciTech Connect (OSTI)

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

NONE

1995-02-01T23:59:59.000Z

158

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

DOE Patents [OSTI]

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

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

1982-03-31T23:59:59.000Z

159

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

SciTech Connect (OSTI)

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

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

2002-01-01T23:59:59.000Z

160

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

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

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

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


161

Record of Decision for the Solid Waste Program, Hanford Site, Richland, WA: Storage and Treatment of Low-Level Waste and Mixed Low-Level Waste; Disposal of Low-Level Waste and Mixed Low-Level Waste, and Storage, Processing, and Certification of Transuran  

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

9 9 Federal Register / Vol. 69, No. 125 / Wednesday, June 30, 2004 / Notices mixed low-level waste, and TRU waste shipments using Year 2000 census data and an updated version of the RADTRAN computer code to calculate potential risks associated with shipping. This analysis included the route- specific impacts of transporting the West Jefferson TRU waste to Hanford and subsequent shipment of this waste to WIPP. Due to the additional TRU waste generated and identified at West Jefferson subsequent to DOE's September 6, 2002, decision, DOE's currently estimated total number of 18 shipments (3 completed RH-TRU waste shipments, 14 remaining RH-TRU waste shipments, and 1 remaining CH-TRU waste shipment) exceeds DOE's prior estimate of total shipments by 3. However, the currently estimated

162

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

SciTech Connect (OSTI)

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

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

2009-01-01T23:59:59.000Z

163

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

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

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

164

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

SciTech Connect (OSTI)

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

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

1996-08-01T23:59:59.000Z

165

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

SciTech Connect (OSTI)

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

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

1997-09-01T23:59:59.000Z

166

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

SciTech Connect (OSTI)

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

Duncan, D.R.

1996-05-07T23:59:59.000Z

167

Remote-handled transuranic system assessment appendices. Volume 2  

SciTech Connect (OSTI)

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

NONE

1995-11-01T23:59:59.000Z

168

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

SciTech Connect (OSTI)

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

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

1996-03-01T23:59:59.000Z

169

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

SciTech Connect (OSTI)

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

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

2000-05-01T23:59:59.000Z

170

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

SciTech Connect (OSTI)

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

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

2006-01-18T23:59:59.000Z

171

Lab Ahead of Schedule Processing Waste in Large Boxes | Department of  

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

Lab Ahead of Schedule Processing Waste in Large Boxes Lab Ahead of Schedule Processing Waste in Large Boxes Lab Ahead of Schedule Processing Waste in Large Boxes March 30, 2012 - 12:00pm Addthis A framework agreement between DOE and the State of New Mexico calls for the Lab’s TRU Waste Program to ship 3,706 cubic meters of combustible or dispersible transuranic waste to WIPP for permanent disposal by June 30, 2014. A framework agreement between DOE and the State of New Mexico calls for the Lab's TRU Waste Program to ship 3,706 cubic meters of combustible or dispersible transuranic waste to WIPP for permanent disposal by June 30, 2014. Processing waste in large boxes is ahead of schedule due to worker skill, efficient processing and good planning. Processing waste in large boxes is ahead of schedule due to worker skill,

172

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

SciTech Connect (OSTI)

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

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

1984-01-01T23:59:59.000Z

173

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

SciTech Connect (OSTI)

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

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

2012-07-01T23:59:59.000Z

174

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

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

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

175

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

SciTech Connect (OSTI)

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

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

2006-04-17T23:59:59.000Z

176

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

SciTech Connect (OSTI)

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

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

1994-08-01T23:59:59.000Z

177

Process development for remote-handled mixed-waste treatment  

SciTech Connect (OSTI)

The Oak Ridge National Laboratory (ORNL) is developing a treatment process for remote-handled (RH) liquid transuranic mixed waste governed by the concept of minimizing the volume of waste requiring disposal. This task is to be accomplished by decontaminating the bulk components so the process effluent can be disposed with less risk and expense. Practical processes have been demonstrated on the laboratory scale for removing cesium 137 and strontium 90 isotopes from the waste, generating a concentrated waste volume, and rendering the bulk of the waste nearly radiation free for downstream processing. The process is projected to give decontamination factors of 10{sup 4} for cesium and 10{sup 3} for strontium. Because of the extent of decontamination, downstream processing will be contact handled. The transuranic, radioactive fraction of the mixed waste stream will be solidified using a thin-film evaporator and/or microwave solidification system. Resultant solidified waste will be disposed at the Waste Isolation Pilot Plant (WIPP). 8 refs., 2 figs., 3 tabs.

Berry, J.B.; Campbell, D.O.; Lee, D.D.; White, T.L.

1990-01-01T23:59:59.000Z

178

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

SciTech Connect (OSTI)

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

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

2003-02-27T23:59:59.000Z

179

Salt Waste Processing Initiatives  

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

Patricia Suggs Patricia Suggs Salt Processing Team Lead Assistant Manager for Waste Disposition Project Office of Environmental Management Savannah River Site Salt Waste Processing Initiatives 2 Overview * Current SRS Liquid Waste System status * Opportunity to accelerate salt processing - transformational technologies - Rotary Microfiltration (RMF) and Small Column Ion Exchange (SCIX) - Actinide Removal Process/Modular Caustic Side Solvent Extraction (ARP/MCU) extension with next generation extractant - Salt Waste Processing Facility (SWPF) performance enhancement - Saltstone enhancements * Life-cycle impacts and benefits 3 SRS Liquid Waste Total Volume >37 Million Gallons (Mgal) Total Curies 183 MCi (51% ) 175 MCi (49% ) >358 Million Curies (MCi) Sludge 34.3 Mgal (92% ) 3.0 Mgal (8%)

180

Transuranic decontamination of nitric acid solutions by the TRUEX solvent extraction process: preliminary development studies. [Octyl(phenyl)-N,N-diisobutylcarbamoylmethylphosphine oxide  

SciTech Connect (OSTI)

This report summarizes the work that has been performed to date at Argonne National Laboratory on the development of the TRUEX process, a solvent extraction process employing a bifunctional organophosphorous reagent in a PUREX process solvent (tributyl phosphate-normal paraffinic hydrocarbons). The purpose of this extraction process is to separate and concentrate transuranic (TRU) elements from nuclear waste. Assessments were made of the use of two TRUEX solvents: one incorporating the well-studied dihexyl-N,N-diethylcarbamoylmethylphosphonate (DHDECMP) and a second incorporating an extractant with superior properties for a 1M HNO/sub 3/ acid feed, octyl(phenyl)-N,N-diisobutylcarbamoylmethylphosphine oxide (O/sub phi/D(IB)CMPO). In this report, conceptual flowsheets for the removal of soluble TRUs from high-level nuclear wastes using these two TRUEX proces solvents are presented, and flowsheet features are discussed in detail. The conceptual flowsheet for TRU-element removal from a PUREX waste by the O/sub phi/D(IB)CMPO-TRUEX process solvent was tested in a bench-scale countercurrent experiment, and results of that experiment are presented and discussed. The conclusion of this study is that the TRUEX process is able to separate TRUs from high-level wastes so that the major portion of the solid waste (approx. 99%) can be classified as non-TRU. Areas where more experimentation is needed are listed at the end of the report. 45 references, 17 figures, 56 tables.

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

1984-07-01T23:59:59.000Z

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


181

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

SciTech Connect (OSTI)

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

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

2007-07-01T23:59:59.000Z

182

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

SciTech Connect (OSTI)

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.

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.

1982-09-01T23:59:59.000Z

183

Building 251 Radioactive Waste Characterization by Process Knowledge  

SciTech Connect (OSTI)

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

Dominick, J L

2002-05-29T23:59:59.000Z

184

Thermal processing system concepts and considerations for RWMC buried waste  

SciTech Connect (OSTI)

This report presents a preliminary determination of ex situ thermal processing system concepts and related processing considerations for application to remediation of transuranic (TRU)-contaminated buried wastes (TRUW) at the Radioactive Waste Management Complex (RWMC) of the Idaho National Engineering Laboratory (INEL). Beginning with top-level thermal treatment concepts and requirements identified in a previous Preliminary Systems Design Study (SDS), a more detailed consideration of the waste materials thermal processing problem is provided. Anticipated waste stream elements and problem characteristics are identified and considered. Final waste form performance criteria, requirements, and options are examined within the context of providing a high-integrity, low-leachability glass/ceramic, final waste form material. Thermal processing conditions required and capability of key systems components (equipment) to provide these material process conditions are considered. Information from closely related companion study reports on melter technology development needs assessment and INEL Iron-Enriched Basalt (IEB) research are considered. Five potentially practicable thermal process system design configuration concepts are defined and compared. A scenario for thermal processing of a mixed waste and soils stream with essentially no complex presorting and using a series process of incineration and high temperature melting is recommended. Recommendations for applied research and development necessary to further detail and demonstrate the final waste form, required thermal processes, and melter process equipment are provided.

Eddy, T.L.; Kong, P.C.; Raivo, B.D.; Anderson, G.L.

1992-02-01T23:59:59.000Z

185

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

ScienceCinema (OSTI)

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

None

2014-10-28T23:59:59.000Z

186

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

SciTech Connect (OSTI)

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

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

1980-07-01T23:59:59.000Z

187

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

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

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

188

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

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

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

189

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

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

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

190

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

SciTech Connect (OSTI)

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

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

1985-03-01T23:59:59.000Z

191

Waste Processing Annual Technology Development Report 2007 |...  

Office of Environmental Management (EM)

Waste Processing Annual Technology Development Report 2007 Waste Processing Annual Technology Development Report 2007 Waste Processing Annual Technology Development Report 2007...

192

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

SciTech Connect (OSTI)

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

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

1984-04-01T23:59:59.000Z

193

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

SciTech Connect (OSTI)

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

Smith-Fewell, M.A., Westinghouse Hanford

1996-05-17T23:59:59.000Z

194

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

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

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

195

Hydrothermal Processing of Wet Wastes  

Broader source: Energy.gov [DOE]

Breakout Session 3AConversion Technologies III: Energy from Our WasteWill we Be Rich in Fuel or Knee Deep in Trash by 2025? Hydrothermal Processing of Wet Wastes James R. Oyler, President, Genifuel Corporation

196

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

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

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

197

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

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

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

198

Idaho Site Taps Old World Process to Treat Nuclear Waste | Department of  

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

Idaho Site Taps Old World Process to Treat Nuclear Waste Idaho Site Taps Old World Process to Treat Nuclear Waste Idaho Site Taps Old World Process to Treat Nuclear Waste September 9, 2013 - 12:00pm Addthis The Idaho site's sodium distillation system. The Idaho site's sodium distillation system. The top of a sodium distillation vessel, where waste enters the system. The top of a sodium distillation vessel, where waste enters the system. The Idaho site's sodium distillation system. The top of a sodium distillation vessel, where waste enters the system. 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. Developed in the first century and perfected by moonshiners in the 19th century, distillation will be used at the Idaho Nuclear Technology and

199

Radioactive waste processing apparatus  

DOE Patents [OSTI]

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

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

1985-08-30T23:59:59.000Z

200

Process for preparing liquid wastes  

DOE Patents [OSTI]

A process for preparing radioactive and other hazardous liquid wastes for treatment by the method of vitrification or melting is provided for.

Oden, Laurance L. (Albany, OR); Turner, Paul C. (Albany, OR); O'Connor, William K. (Lebanon, OR); Hansen, Jeffrey S. (Corvallis, OR)

1997-01-01T23:59:59.000Z

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


201

Tank Waste and Waste Processing | Department of Energy  

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

Tank Waste and Waste Processing Tank Waste and Waste Processing Tank Waste and Waste Processing Tank Waste and Waste Processing The Defense Waste Processing Facility set a record by producing 267 canisters filled with glassified waste in a year. New bubbler technology and other enhancements will increase canister production in the future. The Defense Waste Processing Facility set a record by producing 267 canisters filled with glassified waste in a year. New bubbler technology and other enhancements will increase canister production in the future. A Savannah River Remediation employee uses a manipulator located inside a shielded enclosure at the Defense Waste Processing Facility where the melter is pouring molten glass inside a canister. A Savannah River Remediation employee uses a manipulator located inside a

202

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

SciTech Connect (OSTI)

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

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

2013-07-01T23:59:59.000Z

203

Process Waste Assessment, Mechanics Shop  

SciTech Connect (OSTI)

This Process Waste Assessment was conducted to evaluate hazardous wastes generated in the Mechanics Shop. The Mechanics Shop maintains and repairs motorized vehicles and equipment on the SNL/California site, to include motorized carts, backhoes, street sweepers, trash truck, portable emergency generators, trencher, portable crane, and man lifts. The major hazardous waste streams routinely generated by the Mechanics Shop are used oil, spent off filters, oily rags, and spent batteries. The used off and spent off filters make up a significant portion of the overall hazardous waste stream. Waste oil and spent batteries are sent off-site for recycling. The rags and spent on filters are not recycled. They are disposed of as hazardous waste. Mechanics Shop personnel continuously look for opportunities to minimize hazardous wastes.

Phillips, N.M.

1993-05-01T23:59:59.000Z

204

Los Alamos National Laboratory opens new waste repackaging facility  

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

to increase its capability to process nuclear waste for permanent disposal. March 7, 2013 A view of the new box line facility where transuranic waste will be repackaged at Los...

205

Method for processing aqueous wastes  

DOE Patents [OSTI]

A method for treating waste water such as that from an industrial processing facility comprising the separation of the waste water into a dilute waste stream and a concentrated waste stream. The concentrated waste stream is treated chemically to enhance precipitation and then allowed to separate into a sludge and a supernate. The supernate is skimmed or filtered from the sludge and blended with the dilute waste stream to form a second dilute waste stream. The sludge remaining is mixed with cementitious material, rinsed to dissolve soluble components, then pressed to remove excess water and dissolved solids before being allowed to cure. The dilute waste stream is also chemically treated to decompose carbonate complexes and metal ions and then mixed with cationic polymer to cause the precipitated solids to flocculate. Filtration of the flocculant removes sufficient solids to allow the waste water to be discharged to the surface of a stream. The filtered material is added to the sludge of the concentrated waste stream. The method is also applicable to the treatment and removal of soluble uranium from aqueous streams, such that the treated stream may be used as a potable water supply.

Pickett, John B. (3922 Wood Valley Dr., Aiken, SC 29803); Martin, Hollis L. (Rt. 1, Box 188KB, McCormick, SC 29835); Langton, Christine A. (455 Sumter St. SE., Aiken, SC 29801); Harley, Willie W. (110 Fairchild St., Batesburg, SC 29006)

1993-01-01T23:59:59.000Z

206

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

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

TRU Waste Processing Center TRU Waste Processing Center ORNL TRU Waste Processing Center Tank Waste Processing Supernate (SN) Processing System Presented by Don F. Gagel Vice President and Chief Technology Officer EnergX LLC ORNL TRU Waste Processing Center 1/21/09 2 SRS Technology Transfer, ORNL SN Process Overview SN Process Facility ORNL TRU Waste Processing Center 3 Waste Concentration Using Evaporator Evaporator Concentrates Waste Vapor stream superheated and HEPA-filtered Vapor stream exhausted to main ventilation system Supernate Pump and Evaporator Discharge Pump circulate waste between selected tank and evaporator during concentration. Evaporator Discharge Pump Supernate Pump Supernate Tank Evaporator Exhaust Blower ORNL TRU Waste Processing Center 4 Tank Sampling/ Transfer To Dryer Tank

207

Independent Oversight Assessment, Salt Waste Processing Facility...  

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

Salt Waste Processing Facility Project - January 2013 January 2013 Assessment of Nuclear Safety Culture at the Salt Waste Processing Facility Project The U.S. Department of Energy...

208

DOE/EIS-0305-D; Draft Environmental Impact Statement for Treating Transuranic/Alpha Low-Level Waste at the Oak Ridge National Laboratory Oak Ridge, Tennessee (February 2000)  

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

05-D 05-D DRAFT ENVIRONMENTAL IMPACT STATEMENT (DEIS) FOR TREATING TRANSURANIC (TRU)/ALPHA LOW-LEVEL WASTE AT THE OAK RIDGE NATIONAL LABORATORY OAK RIDGE, TENNESSEE February 2000 TRU Waste Treatment Project, DRAFT Environmental Impact Statement COVER SHEET RESPONSIBLE AGENCY: U.S. Department of Energy (DOE) TITLE: Draft Environmental Impact Statement (EIS) for Treating Transuranic (TRU)/Alpha Low-Level Waste at the Oak Ridge National Laboratory, Oak Ridge, Tennessee CONTACT: For further information on this document, write or call: Dr. Clayton Gist, Waste Management Integration Team Leader U.S. Department of Energy Oak Ridge Operations 55 Jefferson Avenue P. O. Box 2001 Oak Ridge, TN 37831 Telephone: (865) 241-3498 * Facsimile: (865) 576-5333 * E-Mail: gistcs@oro.doe.gov

209

An evaluation of neutralization for processing sodium-bearing liquid waste  

SciTech Connect (OSTI)

This report addresses an alternative concept for potentially managing the sodium-bearing liquid waste generated at the Idaho Chemical Processing Plant from the current method of calcining a blend of sodium waste and high-level liquid waste. The concept is based on removing the radioactive components from sodium-bearing waste by neutralization and grouting the resulting low-level waste for on-site near-surface disposal. Solidifying the sodium waste as a remote-handled transuranic waste is not considered to be practical because of excessive costs and inability to dispose of the waste in a timely fashion. Although neutralization can remove most radioactive components to provide feed for a solidified low-level waste, and can reduce liquid inventories four to nine years more rapidly than the current practice of blending sodium-bearing liquid waste with first-cycle raffinite, the alternative will require major new facilities and will generate large volumes of low-level waste. Additional facility and operating costs are estimated to be at least $500 million above the current practice of blending and calcining. On-site, low-level waste disposal may be technically difficult and conflict which national and state policies. Therefore, it is recommended that the current practice of calcining a blend of sodium-bearing liquid waste and high-level liquid waste be continued to minimize overall cost and process complexities. 17 refs., 4 figs., 16 tabs.

Chipman, N.A.; Engelgau, G.O.; Berreth, J.R.

1989-01-01T23:59:59.000Z

210

The Ceramic Waste Form Process at Idaho National Laboratory  

SciTech Connect (OSTI)

The treatment of spent nuclear fuel for disposition using an electrometallurgical technique results in two high-level waste forms: a ceramic waste form (CWF) and a metal waste form. Reactive metal fuel constituents, including all the transuranic metals and the majority of the fission products remain in the salt as chlorides and are processed into the CWF. The solidified salt is containerized and transferred to the CWF process where it is ground in an argon atmosphere. Zeolite 4A is ground and then dried in a mechanically-fluidized dryer. The salt and zeolite are mixed in a V-mixer and heated to 500C to occlude the salt into the structure of the zeolite. The salt-loaded zeolite is cooled, mixed with borosilicate glass frit, and transferred to a crucible, which is placed in a furnace and heated to 925C. During this process, known as pressureless consolidation, the zeolite is converted to the final sodalite form and the glass thoroughly encapsulates the sodalite, producing a dense, leach-resistant final waste form.

Stephen Priebe

2007-05-01T23:59:59.000Z

211

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

SciTech Connect (OSTI)

This report presents supplemental information to support the human health risk assessment conducted for the transportation of transuranic waste (TRUW) in support of the US Department of Energy Waste Management Programmatic Environmental Impact Statement (WM PEIS). Detailed descriptions of the transportation health risk assessment method and results of the assessment are presented in Appendix E of the WM PEIS and are not repeated in this report. This report presents additional information that is not presented in Appendix E but is necessary to conduct the transportation risk assessment for Waste Management (WM) contact- and remote-handed (CH and RH) TRUW. Included are definitions of the TRUW alternatives considered in the WM PEIS, data related to the inventory and to the physical and radiological characteristics of CH and RH TRUW, and detailed results of the assessment for each WM TRUW case considered.

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

1996-12-01T23:59:59.000Z

212

Transuranic waste inventory, characteristics, generation, and facility assessment for treatment, storage, and disposal alternatives considered in the U.S. Department of Energy Waste Management Programmatic Environmental Impact Statement  

SciTech Connect (OSTI)

Transuranic waste (TRUW) loads and potential contaminant releases at and en route to treatment, storage, and disposal sites in the US Department of Energy (DOE) complex are important considerations in DOE`s Waste Management Programmatic Environmental Impact Statement (WM PEIS). Waste loads are determined in part by the level of treatment the waste has undergone and the complex-wide configuration of origination, treatment, storage, and disposal sites selected for TRUW management. Other elements that impact waste loads are treatment volumes, waste characteristics, and the unit operation parameters of the treatment technologies. Treatment levels and site configurations have been combined into six TRUW management alternatives for study in the WM PEIS. This supplemental report to the WM PEIS gives the projected waste loads and contaminant release profiles for DOE treatment sites under each of the six TRUW management alternatives. It gives TRUW characteristics and inventories for current DOE generation and storage sites, describes the treatment technologies for three proposed levels of TRUW treatment, and presents the representative unit operation parameters of the treatment technologies. The data presented are primary inputs to developing the costs, health risks, and socioeconomic and environmental impacts of treating, packaging, and shipping TRUW for disposal.

Hong, K.; Kotek, T.; Folga, S.; Koebnick, B.; Wang, Y.; Kaicher, C.

1996-12-01T23:59:59.000Z

213

Waste Receiving and Processing (WRAP) Facility Final Safety Analysis Report (FSAR)  

SciTech Connect (OSTI)

The Waste Receiving and Processing Facility (WRAP), 2336W Building, on the Hanford Site is designed to receive, confirm, repackage, certify, treat, store, and ship contact-handled transuranic and low-level radioactive waste from past and present U.S. Department of Energy activities. The WRAP facility is comprised of three buildings: 2336W, the main processing facility (also referred to generically as WRAP); 2740W, an administrative support building; and 2620W, a maintenance support building. The support buildings are subject to the normal hazards associated with industrial buildings (no radiological materials are handled) and are not part of this analysis except as they are impacted by operations in the processing building, 2336W. WRAP is designed to provide safer, more efficient methods of handling the waste than currently exist on the Hanford Site and contributes to the achievement of as low as reasonably achievable goals for Hanford Site waste management.

TOMASZEWSKI, T.A.

2000-04-25T23:59:59.000Z

214

Bubblers Speed Nuclear Waste Processing at SRS  

ScienceCinema (OSTI)

At the Department of Energy's Savannah River Site, American Recovery and Reinvestment Act funding has supported installation of bubbler technology and related enhancements in the Defense Waste Processing Facility (DWPF). The improvements will accelerate the processing of radioactive waste into a safe, stable form for storage and permit expedited closure of underground waste tanks holding 37 million gallons of liquid nuclear waste.

None

2014-08-06T23:59:59.000Z

215

Bubblers Speed Nuclear Waste Processing at SRS  

SciTech Connect (OSTI)

At the Department of Energy's Savannah River Site, American Recovery and Reinvestment Act funding has supported installation of bubbler technology and related enhancements in the Defense Waste Processing Facility (DWPF). The improvements will accelerate the processing of radioactive waste into a safe, stable form for storage and permit expedited closure of underground waste tanks holding 37 million gallons of liquid nuclear waste.

None

2010-11-14T23:59:59.000Z

216

Waste minimization in semiconductor processing  

SciTech Connect (OSTI)

The US semiconductor industry uses 5--7 thousand pounds of arsine annually. Fifty to eighty percent of the arsine used becomes a waste product, which requires abatement. Traditional methods of abatement are reviewed with an emphasis on dry chemical scrubbing. A variety of dry chemical scrubbing materials were evaluated for arsine capacity, using activated carbon as the baseline for comparison. Of the available technologies, dry chemical scrubbing is the most effective means of minimizing arsenic containing waste generated from semiconductor effluents. A copper oxide based media has been identified which has high capacity, high efficiency and treats the spectrum of gases used in MOCVD processes. Reclaim and recovery of spent scrubber media has the potential to drastically reduce arsenic waste from semiconductor manufacturing.

Hardwick, S.J.; Mailloux, J.C. [Novapure Corp., Danbury, CT (United States)

1994-12-31T23:59:59.000Z

217

Concentration of remote-handled, transuranic, sodium nitrate-based sludge using agitated thin-film evaporators  

SciTech Connect (OSTI)

The Waste Handling and Packaging Plant (WHPP) is being designed at Oak Ridge National Laboratory (ORNL) to prepared transuranic waste for final disposal. Once operational, this facility will process, package, and certify remote-handled transuranic waste for ultimate shipment and disposal at the Waste Isolation Pilot Plant (WIPP) in Carlsbad, New Mexico. One of the wastes that will be handled at WHIPP is the transuranic sludge currently stored at ORNL in eight 50,000-gal underground tanks. The use of an Agitated Thin-Film Evaporator (ATFE) for concentration of this waste is being investigated. Tests have shown that the ATFE can be used to produce a thick slurry, a powder, or a fused salt. A computer model developed at the Savannah River Plant (SRP) to simulate the operation of ATFE's on their waste is being modified for use on the ORNL transuranic sludge. This paper summarizes the results of the test with the ATFEs to date, discusses the changes in the SRP model necessary to use this model with the ORNL waste, and compares the results of the model with the actual data taken from the operation of ATFEs at vendors' test facilities. 8 refs., 1 fig., 3 tabs.

Walker, J.F. Jr.; Youngblood, E.L.; Berry, J.B. (Oak Ridge National Lab., TN (USA)); Pen, Ben-Li (Institute of Nuclear Energy Research, Lung-Tan (Taiwan))

1991-01-01T23:59:59.000Z

218

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.

219

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

SciTech Connect (OSTI)

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

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

2007-07-01T23:59:59.000Z

220

An Investigation of the Use of Fully Ceramic Microencapsulated Fuel for Transuranic Waste Recycling in Pressurized Water Reactors  

SciTech Connect (OSTI)

An investigation of the utilization of TRistructural- ISOtropic (TRISO)-coated fuel particles for the burning of plutonium/neptunium (Pu/Np) isotopes in typical Westinghouse four-loop pressurized water reactors is presented. Though numerous studies have evaluated the burning of transuranic isotopes in light water reactors (LWRs), this work differentiates itself by employing Pu/Np-loaded TRISO particles embedded within a silicon carbide (SiC) matrix and formed into pellets, constituting the fully ceramic microencapsulated (FCM) fuel concept that can be loaded into standard LWR fuel element cladding. This approach provides the capability of Pu/Np burning and, by virtue of the multibarrier TRISO particle design and SiC matrix properties, will allow for greater burnup of Pu/Np material, plus improved fuel reliability and thermal performance. In this study, a variety of heterogeneous assembly layouts, which utilize a mix of FCM rods and typical UO2 rods, and core loading patterns were analyzed to demonstrate the neutronic feasibility of Pu/Np-loaded TRISO fuel. The assembly and core designs herein reported are not fully optimized and require fine-tuning to flatten power peaks; however, the progress achieved thus far strongly supports the conclusion that with further rod/assembly/core loading and placement optimization, Pu/Np-loaded TRISO fuel and core designs that are capable of balancing Pu/Np production and destruction can be designed within the standard constraints for thermal and reactivity performance in pressurized water reactors.

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

2014-01-01T23:59:59.000Z

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


221

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

Broader source: Energy.gov [DOE]

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

222

Management of salt waste from electrochemical processing of used nuclear fuel  

SciTech Connect (OSTI)

Electrochemical processing of used nuclear fuel involves operation of one or more cells containing molten salt electrolyte. Processing of the fuel results in contamination of the salt via accumulation of fission products and transuranic (TRU) actinides. Upon reaching contamination limits, the salt must be removed and either disposed or treated to remove the contaminants and recycled back to the process. During development of the Experimental Breeder Reactor-II spent fuel treatment process, waste salt from the electro-refiner was to be stabilized in a ceramic waste form and disposed of in a high-level waste repository. With the cancellation of the Yucca Mountain high-level waste repository, other options are now being considered. One approach that involves direct disposal of the salt in a geologic salt formation has been evaluated. While waste forms such as the ceramic provide near-term resistance to corrosion, they may not be necessary to ensure adequate performance of the repository. To improve the feasibility of direct disposal, recycling a substantial fraction of the useful salt back to the process equipment could minimize the volume of the waste. Experiments have been run in which a cold finger is used for this purpose to crystallize LiCl from LiCl/CsCl. If it is found to be unsuitable for transportation, the salt waste could also be immobilized in zeolite without conversion to the ceramic waste form. (authors)

Simpson, M.F.; Patterson, M.N. [Idaho National Laboratory, P.O. Box 1625, Idaho Falls, Idaho 83415 (United States); Lee, J.; Wang, Y. [Sandia National Laboratory, Albuquerque, NM (United States); Versey, J.; Phongikaroon, S. [University of Idaho, Idaho Falls, ID (United States)

2013-07-01T23:59:59.000Z

223

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

SciTech Connect (OSTI)

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

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

2003-02-27T23:59:59.000Z

224

Process removes Sr from nuclear wastes  

Science Journals Connector (OSTI)

Process removes Sr from nuclear wastes ... Scientists at Argonne National Laboratory have devised a chemical process for extracting and recovering strontium-90 from liquid nuclear wastes. ... Argonne chemist E. Philip Horwitz, head of the team, says it could be a significant aid in managing such radioactive wastes. ...

WARD WORTHY

1990-09-10T23:59:59.000Z

225

Letter: The Environmental Management SSABs Recommendations on Transuranic  

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

The Environmental Management SSABs Recommendations on The Environmental Management SSABs Recommendations on Transuranic Waste Management Letter: The Environmental Management SSABs Recommendations on Transuranic Waste Management From: Assistant Secretary, Jessie H. Roberson (EM-1) To: Mr. Monte Wilson, Chair, Idaho National Engineering Laboratory Citizens Advisory Board 1055 This letter is in response to a March 29, 2003, letter regarding the recommendations on transuranic (TRLD waste management suggested by the Office of Environmental Management Site-Specific Advisory Boards (SSABs). Roberson Letter - June 2, 2003 More Documents & Publications Letter: Direction and Guidance for Implementing Direct DOE Relationship & Funding for EMSSABs Letter: Restructuring & Managing of the Procurement Mechanisms Supporting

226

The WIPP Hazardous Waste Facility Permit Improvements--2007 Update  

SciTech Connect (OSTI)

The most significant changes to the Waste Isolation Pilot Plant Hazardous Waste Facility Permit to date were completed during the past year with the implementation of significant revisions to the Waste Analysis Plan and the authorization to dispose of remote-handled transuranic waste. The modified Permit removes the requirement for reporting headspace gas sampling and analysis results for every container of transuranic mixed waste and provides for the use of radiography and visual examination to confirm a statistically representative subpopulation of the waste stream in each waste shipment as well as other changes that streamline the analytical data management process. Implementation began on November 17, 2006. (authors)

Kehrman, R.; Most, W. [Washington Regulatory and Environmental Services, Carlsbad, NM (United States)

2007-07-01T23:59:59.000Z

227

Zone Freezing Study for Pyrochemical Process Waste Minimization  

SciTech Connect (OSTI)

Pyroprocessing technology is a non-aqueous separation process for treatment of used nuclear fuel. At the heart of pyroprocessing lies the electrorefiner, which electrochemically dissolves uranium from the used fuel at the anode and deposits it onto a cathode. During this operation, sodium, transuranics, and fission product chlorides accumulate in the electrolyte salt (LiCl-KCl). These contaminates change the characteristics of the salt overtime and as a result, large volumes of contaminated salt are being removed, reprocessed and stored as radioactive waste. To reduce the storage volumes and improve recycling process for cost minimization, a salt purification method called zone freezing has been proposed at Korea Atomic Energy Research Institute (KAERI). Zone freezing is melt crystallization process similar to the vertical Bridgeman method. In this process, the eutectic salt is slowly cooled axially from top to bottom. As solidification occurs, the fission products are rejected from the solid interface and forced into the liquid phase. The resulting product is a grown crystal with the bulk of the fission products near the bottom of the salt ingot, where they can be easily be sectioned and removed. Despite successful feasibility report from KAERI on this process, there were many unexplored parameters to help understanding and improving its operational routines. Thus, this becomes the main motivation of this proposed study. The majority of this work has been focused on the CsCl-LiCl-KCl ternary salt. CeCl3-LiCl-KCl was also investigated to check whether or not this process is feasible for the trivalent speciessurrogate for rare-earths and transuranics. For the main part of the work, several parameters were varied, they are: (1) the retort advancement rate1.8, 3.2, and 5.0 mm/hr, (2) the crucible lid configurationslid versus no-lid, (3) the amount or size of mixture50 and 400 g, (4) the composition of CsCl in the salt1, 3, and 5 wt%, and (5) the temperature differences between the high and low furnace zones200 and 300 ?C. During each experiment, the temperatures at selected locations around the crucible were measured and recorded to provide temperature profiles. Following each experiment, samples were collected and elemental analysis was done to determine the composition of iii the salt. Several modelsnon-mixed, well-mixed, Favier, and hybridwere explored to describe the zone freezing process. For CsCl-LiCl-KCl system, experimental results indicate that through this process up to 90% of the used salt can be recycled, effectively reducing waste volume by a factor of ten. The optimal configuration was found to be a 5.0 mm/hr rate with a lid configuration and a ?T of 200C. The larger 400 g mixtures had recycle percentages similar to the 50 g mixtures; however, the throughput per time was greater for the 400 g case. As a result, the 400 g case is recommended. For the CeCl3-LiCl-KCl system, the result implies that it is possible to use this process to separate the rare-earth and transuranics chlorides. Different models were applied to only CsCl ternary system. The best fit model was the hybrid model as a result of a solute transport transition from non- mixed to well-mixed throughout the growing process.

Ammon Williams

2012-05-01T23:59:59.000Z

228

Process for remediation of plastic waste  

DOE Patents [OSTI]

A single step process for degrading plastic waste by converting the plastic waste into carbonaceous products via thermal decomposition of the plastic waste by placing the plastic waste into a reactor, heating the plastic waste under an inert or air atmosphere until the temperature of about 700.degree. C. is achieved, allowing the reactor to cool down, and recovering the resulting decomposition products therefrom. The decomposition products that this process yields are carbonaceous materials, and more specifically carbon nanotubes having a partially filled core (encapsulated) adjacent to one end of the nanotube. Additionally, in the presence of a transition metal compound, this thermal decomposition process produces multi-walled carbon nanotubes.

Pol, Vilas G; Thiyagarajan, Pappannan

2013-11-12T23:59:59.000Z

229

Process for remediation of plastic waste  

DOE Patents [OSTI]

A single step process for degrading plastic waste by converting the plastic waste into carbonaceous products via thermal decomposition of the plastic waste by placing the plastic waste into a reactor, heating the plastic waste under an inert or air atmosphere until the temperature of 700.degree. C. is achieved, allowing the reactor to cool down, and recovering the resulting decomposition products therefrom. The decomposition products that this process yields are carbonaceous materials, and more specifically egg-shaped and spherical-shaped solid carbons. Additionally, in the presence of a transition metal compound, this thermal decomposition process produces multi-walled carbon nanotubes.

Pol, Vilas G. (Westmont, IL); Thiyagarajan, Pappannan (Germantown, MD)

2012-04-10T23:59:59.000Z

230

Evaluation of the WIPP Project`s compliance with the EPA radiation protection standards for disposal of transuranic waste  

SciTech Connect (OSTI)

The US Environmental Protection Agency`s (EPA) proposed rule to certify that the Waste Isolation Pilot Plant (WIPP) meets compliance with the long-term radiation protection standards for geologic repositories (40CFR191 Subparts B and C), is one of the most significant milestones to date for the WIPP project in particular, and for the nuclear waste issue in general. The Environmental Evaluation Group (EEG) has provided an independent technical oversight for the WIPP project since 1978, and is responsible for many improvements in the location, design, and testing of various aspects of the project, including participation in the development of the EPA standards since the early 1980s. The EEG reviewed the development of documentation for assessing the WIPP`s compliance by the Sandia National Laboratories following the 1985 promulgation by EPA, and provided many written and verbal comments on various aspects of this effort, culminating in the overall review of the 1992 performance assessment. For the US Department of Energy`s (DOE) compliance certification application (CCA), the EEG provided detailed comments on the draft CCA in March, 1996, and additional comments through unpublished letters in 1997 (included as Appendices 8.1 and 8.2 in this report). Since the October 30, 1997, publication of the EPA`s proposed rule to certify WIPP, the EEG gave presentations on important issues to the EPA on December 10, 1997, and sent a December 31, 1997 letter with attachments to clarify those issues (Appendix 8.3). The EEG has raised a number of questions that may have an impact on compliance. In spite of the best efforts by the EEG, the EPA reaction to reviews and suggestions has been slow and apparently driven by legal considerations. This report discusses in detail the questions that have been raised about containment requirements. Also discussed are assurance requirements, groundwater protection, individual protection, and an evaluation of EPA`s responses to EEG`s comments.

Neill, R.H.; Chaturvedi, L.; Rucker, D.F.; Silva, M.K.; Walker, B.A.; Channell, J.K.; Clemo, T.M. [Environmental Evaluation Group, Albuquerque, NM (United States)] [Environmental Evaluation Group, Albuquerque, NM (United States); [Environmental Evaluation Group, Carlsbad, NM (United States)

1998-03-01T23:59:59.000Z

231

The Ceramic Waste Form Process at the Idaho National Laboratory  

SciTech Connect (OSTI)

The treatment of spent nuclear fuel for disposition using an electrometallurgical technique results in two high-level waste forms: a ceramic waste form (CWF) and a metal waste form (MWF). The CWF is a composite of sodalite and glass, which stabilizes the active fission products (alkali, alkaline earths, and rare earths) and transuranic (TRU) elements. Reactive metal fuel constituents, including all the TRU metals and the majority of the fission products remain in the salt as chlorides and are processed into the CWF. The solidified salt is containerized and transferred to the CWF process where it is ground in an argon atmosphere. Zeolite 4A is dried in a mechanically-fluidized dryer to about 0.1 wt% moisture and ground to a particle-size range of 45 to 250. The salt and zeolite are mixed in a V-mixer and heated to 500C for about 18 hours. During this process, the salt occludes into the structure of the zeolite. The salt-loaded zeolite (SLZ) is cooled and then mixed with borosilicate glass frit with a comparable particle-size range. The SLZ/glass mixture is transferred to a crucible, which is placed in a furnace and heated to 925C. During this process, known as pressureless consolidation, the zeolite is converted to the final sodalite form and the glass thoroughly encapsulates the sodalite, producing a dense, leach-resistant final waste form. During the last several years, changes have occurred to the process, including: particle size of input materials and conversion from hot isostatic pressing to pressureless consolidation, This paper is intended to provide the current status of the CWF process focusing on the adaptation to pressureless consolidation. Discussions will include impacts of particle size on final waste form and the pressureless consolidation cycle. A model will be presented that shows the heating and cooling cycles and the effect of radioactive decay heat on the amount of fission products that can be incorporated into the CWF.

Ken Bateman; Stephen Priebe

2006-08-01T23:59:59.000Z

232

Summary of LLNL`s accomplishments for the FY93 Waste Processing Operations Program  

SciTech Connect (OSTI)

Under the US Department of Energy`s (DOE`s) Office of Technology Development (OTD)-Robotic Technology Development Program (RTDP), the Waste Processing Operations (WPO) Program was initiated in FY92 to address the development of automated material handling and automated chemical and physical processing systems for mixed wastes. The Program`s mission was to develop a strategy for the treatment of all DOE mixed, low-level, and transuranic wastes. As part of this mission, DOE`s Mixed Waste Integrated Program (MWIP) was charged with the development of innovative waste treatment technologies to surmount shortcomings of existing baseline systems. Current technology advancements and applications results from cooperation of private industry, educational institutions, and several national laboratories operated for DOE. This summary document presents the LLNL Environmental Restoration and Waste Management (ER and WM) Automation and Robotics Section`s contributions in support of DOE`s FY93 WPO Program. This document further describes the technological developments that were integrated in the 1993 Mixed Waste Operations (MWO) Demonstration held at SRTC in November 1993.

Grasz, E.; Domning, E.; Heggins, D.; Huber, L.; Hurd, R.; Martz, H.; Roberson, P.; Wilhelmsen, K.

1994-04-01T23:59:59.000Z

233

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

SciTech Connect (OSTI)

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

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

2012-07-01T23:59:59.000Z

234

Hydrothermal Processing of Wet Wastes  

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

Mill Waste, Plastic Bottles Aquatic Water Hyacinths, Kelp (Marine), Red Algae (Marine), Green Algae (Brackish), Green Algae (Marine), Green Algae (Fresh), Diatoms, Cyanobacteria...

235

Waste Processing Annual Technology Development Report 2007  

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

Processing Processing Annual Technology Development Report 2007 SRNS-STI-2008-00040 United States Department of Energy Waste Processing Annual Technology Development Report 2007 Prepared and edited by S. R. Bush EM Technical Integration Office Savannah River National Laboratory Reviewed by Dr. W. R. Wilmarth, Manager EM Technical Integration Office Savannah River National Laboratory Approved by Dr. S. L. Krahn, Director EM-21 Office of Waste Processing U. S. Department of Energy APPROVED for Release for Unlimited (Release to Public) (Signed 08/13/2008) (Signed 08/13/2008) (Signed 08/13/2008) EM-21 Waste Processing Annual Report for Calendar Year 2007 2/74

236

Office of Environmental Management Taps Small Business for Waste Isolation  

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

Environmental Management Taps Small Business for Waste Environmental Management Taps Small Business for Waste Isolation Pilot Plant Contract Office of Environmental Management Taps Small Business for Waste Isolation Pilot Plant Contract August 29, 2012 - 4:54pm Addthis A stratigraph of the Waste Isolation Pilot Plant's underground layers, where Transuranic waste is safely stored. A stratigraph of the Waste Isolation Pilot Plant's underground layers, where Transuranic waste is safely stored. John Hale III John Hale III Director, Office of Small and Disadvantaged Business Utilization This week, Celeritex, LLC landed a contract worth up to $17.8 million with the Office of Environmental Management, having demonstrated through a competetive process that this small business is up to the task of securing and isolating defense-generated Transuranic waste.

237

Section 08: Approval Process for Waste Shipment From Waste Generator...  

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

Assay Box Counter NTS Nevada Test Site ORNL Oak Ridge National Laboratory QA quality assurance RFETS Rocky Flats Environmental Technology Site RH-TRU remote-handled transuranic RL...

238

Salt Waste Processing Facility Fact Sheet | Department of Energy  

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

Services » Waste Management » Tank Waste and Waste Processing » Services » Waste Management » Tank Waste and Waste Processing » Salt Waste Processing Facility Fact Sheet Salt Waste Processing Facility Fact Sheet Nuclear material production operations at SRS resulted in the generation of liquid radioactive waste that is being stored, on an interim basis, in 49 underground waste storage tanks in the F- and H-Area Tank Farms. SWPF Fact Sheet More Documents & Publications EIS-0082-S2: Amended Record of Decision Savannah River Site Salt Waste Processing Facility Technology Readiness Assessment Report EIS-0082-S2: Record of Decision Waste Management Nuclear Materials & Waste Tank Waste and Waste Processing Waste Disposition Packaging and Transportation Site & Facility Restoration Deactivation & Decommissioning (D&D)

239

Performance Assessment for Transuranic Waste  

National Nuclear Security Administration (NNSA)

Sims et al. 1978a, b; Gholz 1982; Law and Waring 1994; Hansen et al. 2000; Knapp and Smith 2001). Selected grassland communities were limited to those with MAT from 8 to 12C...

240

Revision to the Record of Decision for the Department of Energy's Waste Management Program: Treatment and Storage of Transuranic Waste 9/6/02)  

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

989 989 Federal Register / Vol. 67, No. 173 / Friday, September 6, 2002 / Notices 1 The only exception to this decision was the Sandia National Laboratory in New Mexico, which will ship its TRU waste to the Los Alamos National Laboratory for disposal preparation and storage before disposal at WIPP. SANDEL, E. A. MS. SAUL, E. L. MR. SCHAEFER, J. C. MR. SCHAEFER JR, W. J. MR. SCHNEIDER, P. A. MR. SCHREGARDOUS, D. R. MR. SCHUBERT, D. CAPT SHEA, R. M. MAJGEN SHECK, E. E. MR. SHEPHARD, M. R. MS. SIMON, E. A. MR. SOMOROFF, A. R. DR. STELLOH-GARNER, C. MS. STOREY, R. C. MR. STUSSIE, W. A. MR. SULLIVAN, P. E. RADML TAMBURRINO, P. M. MR. TARRANT, N. J. MS. TESCH, T. G. MR. THOMAS, J. R. BGEN THOMAS, R. O. MR. THOMPSON, R. C. MR. THROCKMORTON JR., E. L. MR. TOWNSEND, D. K. MS.

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


241

Management of Transuranic Contaminated Material  

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

To establish guidelines for the generation, treatment, packaging, storage, transportation, and disposal of transuranic (TRU) contaminated material.

1982-09-30T23:59:59.000Z

242

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

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

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

243

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

SciTech Connect (OSTI)

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

Not Available

1993-03-01T23:59:59.000Z

244

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

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

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

245

Transuranic Contamination in Sediment and Groundwater at the U.S. DOE Hanford Site  

SciTech Connect (OSTI)

A review of transuranic radionuclide contamination in sediments and groundwater at the DOEs Hanford Site was conducted. The review focused primarily on plutonium-239/240 and americium-241; however, other transuranic nuclides were discussed as well, including neptunium-237, plutonium-238, and plutonium-241. The scope of the review included liquid process wastes intentionally disposed to constructed waste disposal facilities such as trenches and cribs, burial grounds, and unplanned releases to the ground surface. The review did not include liquid wastes disposed to tanks or solid wastes disposed to burial grounds. It is estimated that over 11,800 Ci of plutonium-239, 28,700 Ci of americium-241, and 55 Ci of neptunium-237 have been disposed as liquid waste to the near surface environment at the Hanford Site. Despite the very large quantities of transuranic contaminants disposed to the vadose zone at Hanford, only minuscule amounts have entered the groundwater. Currently, no wells onsite exceed the DOE derived concentration guide for plutonium-239/240 (30 pCi/L) or any other transuranic contaminant in filtered samples. The DOE derived concentration guide was exceeded by a small fraction in unfiltered samples from one well (299-E28-23) in recent years (35.4 and 40.4 pCi/L in FY 2006). The primary reason that disposal of these large quantities of transuranic radionuclides directly to the vadose zone at the Hanford Site has not resulted in widespread groundwater contamination is that under the typical oxidizing and neutral to slightly alkaline pH conditions of the Hanford vadose zone, transuranic radionuclides (plutonium and americium in particular) have a very low solubility and high affinity for surface adsorption to mineral surfaces common within the Hanford vadose zone. Other important factors are the fact that the vadose zone is typically very thick (hundreds of feet) and the net infiltration rate is very low due to the desert climate. In some cases where transuranic radionuclides have been co-disposed with acidic liquid waste, transport through the vadose zone for considerable distances has occurred. For example, at the 216-Z-9 Crib, plutonium-239 and americium-241 have moved to depths in excess of 36 m (118 ft) bgs. Acidic conditions increase the solubility of these contaminants and reduce adsorption to mineral surfaces. Subsequent neutralization of the acidity by naturally occurring calcite in the vadose zone (particularly in the Cold Creek unit) appears to have effectively stopped further migration. The vast majority of transuranic contaminants disposed to the vadose zone on the Hanford Site (10,200 Ci [86%] of plutonium-239; 27,900 Ci [97%] of americium-241; and 41.8 Ci [78%] of neptunium-237) were disposed in sites within the PFP Closure Zone. This closure zone is located within the 200 West Area (see Figures 1.1 and 3.1). Other closure zones with notably high quantities of transuranic contaminant disposal include the T Farm Zone with 408 Ci (3.5%) plutonium-239, the PUREX Zone with 330 Ci (2.8%) plutonium-239, 200-W Ponds Zone with 324 Ci (2.8%) plutonium-239, B Farm Zone with 183 Ci (1.6%) plutonium-239, and the REDOX Zone with 164 Ci (1.4%) plutonium 239. Characterization studies for most of the sites reviewed in the document are generally limited. The most prevalent characterization methods used were geophysical logging methods. Characterization of a number of sites included laboratory analysis of borehole sediment samples specifically for radionuclides and other contaminants, and geologic and hydrologic properties. In some instances, more detailed research level studies were conducted. Results of these studies were summarized in the document.

Cantrell, Kirk J.

2009-08-20T23:59:59.000Z

246

Acceptable Knowledge Summary Report for Waste Stream: SR-T001-221F-HET/Drums  

SciTech Connect (OSTI)

Since beginning operations in 1954, the Savannah River Site FB-Line produced Weapons Grade Plutonium for the United States National Defense Program. The facility mission was mainly to process dilute plutonium solution received from the 221-F Canyon into highly purified plutonium metal. As a result of various activities (maintenance, repair, clean up, etc.) in support of the mission, the facility generated a transuranic heterogeneous debris waste stream. Prior to January 25, 1990, the waste stream was considered suspect mixed transuranic waste (based on potential for inclusion of F-Listed solvent rags/wipes) and is not included in this characterization. Beginning January 25, 1990, Savannah River Site began segregation of rags and wipes containing F-Listed solvents thus creating a mixed transuranic waste stream and a non-mixed transuranic waste stream. This characterization addresses the non-mixed transuranic waste stream packaged in 55-gallon drums after January 25, 1990.Characterization of the waste stream was achieved using knowledge of process operations, facility safety basis documentation, facility specific waste management procedures and storage / disposal records. The report is fully responsive to the requirements of Section 4.0 "Acceptable Knowledge" from the WIPP Transuranic Waste Characterization Quality Assurance Plan, CAO-94-1010, and provides a sound, (and auditable) characterization that satisfies the WIPP criteria for Acceptable Knowledge.

Lunsford, G.F.

1998-10-26T23:59:59.000Z

247

Process for treating alkaline wastes for vitrification  

DOE Patents [OSTI]

According to its major aspects and broadly stated, the present invention is a process for treating alkaline waste materials, including high level radioactive wastes, for vitrification. The process involves adjusting the pH of the wastes with nitric acid, adding formic acid (or a process stream containing formic acid) to reduce mercury compounds to elemental mercury and MnO{sub 2} to the Mn(II) ion, and mixing with class formers to produce a melter feed. The process minimizes production of hydrogen due to noble metal-catalyzed formic acid decomposition during, treatment, while producing a redox-balanced feed for effective melter operation and a quality glass product. An important feature of the present invention is the use of different acidifying and reducing, agents to treat the wastes. The nitric acid acidifies the wastes to improve yield stress and supplies acid for various reactions; then the formic acid reduces mercury compounds to elemental mercury and MnO{sub 2}) to the Mn(II) ion. When the pH of the waste is lower, reduction of mercury compounds and MnO{sub 2}) is faster and less formic acid is needed, and the production of hydrogen caused by catalytically-active noble metals is decreased.

Hsu, Chia-lin W.

1994-01-01T23:59:59.000Z

248

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

Science Journals Connector (OSTI)

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

R. Burcl

2013-01-01T23:59:59.000Z

249

Waste Isolation Pilot Plant | Department of Energy  

Office of Environmental Management (EM)

Waste Isolation Pilot Plant Waste Isolation Pilot Plant Operators prepare drums of contact-handled transuranic waste for loading into transportation containers Operators prepare...

250

Revision to the Record of Decision for the Department of Energy's Waste Management Program: Treatment and Storage of Transuranic Waste (DOE/EIS-0200) (12/29/00)  

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

985 985 Federal Register / Vol. 65, No. 251 / Friday, December 29, 2000 / Notices collection; and (6) Reporting and/or Recordkeeping burden. OMB invites public comment. The Department of Education is especially interested in public comment addressing the following issues: (1) Is this collection necessary to the proper functions of the Department; (2) will this information be processed and used in a timely manner; (3) is the estimate of burden accurate; (4) how might the Department enhance the quality, utility, and clarity of the information to be collected; and (5) how might the Department minimize the burden of this collection on the respondents, including through the use of information technology. Dated: December 22, 2000. John Tressler, Leader, Regulatory Information Management,

251

Revision to the Record of Decision for the Department of Energy's Waste Management Program: Treatment and Storage of Transuranic Waste (07/25/01)  

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

46 46 Federal Register / Vol. 66, No. 143 / Wednesday, July 25, 2001 / Notices the Director of OMB provide interested Federal agencies and the public an early opportunity to comment on information collection requests. The Office of Management and Budget (OMB) may amend or waive the requirement for public consultation to the extent that public participation in the approval process would defeat the purpose of the information collection, violate State or Federal law, or substantially interfere with any agency's ability to perform its statutory obligations. The Leader, Information Management Group, Office of the Chief Information Officer, publishes this notice containing proposed information collection requests at the beginning of the Departmental review of the information collection. Each proposed information

252

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

SciTech Connect (OSTI)

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

N /A

2000-06-30T23:59:59.000Z

253

Waste Heat Management Options for Improving Industrial Process...  

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

of waste heat streams, and options for recovery including Combined Heat and Power. Waste Heat Management Options for Improving Industrial Process Heating Systems...

254

Waste Heat Management Options for Improving Industrial Process Heating Systems  

Broader source: Energy.gov [DOE]

This presentation covers typical sources of waste heat from process heating equipment, characteristics of waste heat streams, and options for recovery including Combined Heat and Power.

255

Office of Waste Processing Technical Exchange  

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

Event Media Links Event Media Links Session 1: Technical Exchange Opening Topic Speaker PDF Podcast S01-01 Welcome T. Michalske, SRNL N/A Podcast S01-03 Introductions G. Flowers, SRNS N/A Podcast S01-04 Opening Remarks I. Triay, DOE-EM Presentation PDF Podcast S01-05 Status of Waste Processing Technology Development S. Schneider, DOE-EM Presentation PDF Podcast S01-06 Hanford/SRS Tank Waste Path Forward K. Subramanian/ T. Sams, SRR/WRPS Presentation PDF Podcast S01-07 Fluidized Bed Steam Reformer Overview B. Mason, TTT Presentation PDF Podcast S01-08 Next Generation Cesium Solvent B.Moyer/S. Fink/M. Geeting, ORNL/SRNL/SRR Presentation PDF Podcast S01-09 Rotary Microfilter Development/Small Column Ion Exchange D. Herman/ R. Edwards, SRNL/SRR Presentation PDF Podcast Session 2: Increased Waste Loading - Improved Current Processing

256

1987 Oak Ridge model conference: Proceedings: Volume I, Part 3, Waste Management  

SciTech Connect (OSTI)

A conference sponsored by the United States Department of Energy (DOE), was held on waste management. Topics of discussion were transuranic waste management, chemical and physical treatment technologies, waste minimization, land disposal technology and characterization and analysis. Individual projects are processed separately for the data bases. (CBS)

Not Available

1987-01-01T23:59:59.000Z

257

Office of Waste Processing Technical Exchange  

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

EM Waste Processing Technical Exchange 2010 Agenda EM Waste Processing Technical Exchange 2010 Agenda (Sponsored by EM Office of Waste Processing) November 16 - 18, 2010; Loews Hotel, Atlanta, GA 11/2/2010 Monday, November 15, 2010 5:00 - 7:00 pm Early Registration and Speaker Check-in *Light Refreshments Tuesday Morning, November 16, 2010 Session 1: Technical Exchange Opening (Chair: W. Wilmarth); Salon D Live Webcast Click the video icon to view Session 1 Live Webcast Submit Question Click the Question icon to submit a question. Time Topic Speaker 7:00 am Registration and Check-in 8:00 am S01-01 Welcome T. Michalske, SRNL 8:05 am S01-02 Opening Comments Y. Collazo, DOE-EM 8:15 am S01-03 Introductions G. Flowers, SRNS 8:20 am S01-04 Opening Remarks I. Triay, DOE-EM 8:45 am S01-05 Status of Waste Processing Technology Development

258

Use of a CO{sub 2} pellet non-destructive cleaning system to decontaminate radiological waste and equipment in shielded hot cells at the Bettis Atomic Power Laboratory  

SciTech Connect (OSTI)

This paper details how the Bettis Atomic Power Laboratory modified and utilized a commercially available, solid carbon dioxide (CO{sub 2}) pellet, non-destructive cleaning system to support the disposition and disposal of radioactive waste from shielded hot cells. Some waste materials and equipment accumulated in the shielded hot cells cannot be disposed directly because they are contaminated with transuranic materials (elements with atomic numbers greater than that of uranium) above waste disposal site regulatory limits. A commercially available CO{sub 2} pellet non-destructive cleaning system was extensively modified for remote operation inside a shielded hot cell to remove the transuranic contaminants from the waste and equipment without generating any secondary waste in the process. The removed transuranic contaminants are simultaneously captured, consolidated, and retained for later disposal at a transuranic waste facility.

Bench, T.R.

1997-05-01T23:59:59.000Z

259

Apply process integration to waste minimization  

SciTech Connect (OSTI)

This article presents a systematic method for identifying process modifications to minimize waste generation. It is based on the hierarchical decision procedure, which provides a framework for identifying process improvement options and evaluating heat and mass integration opportunities. The article deals specifically with an adaptation of the hierarchical decision approach for use in pollution abatement applications. The article also illustrates the use of the technique by applying it to the fluid catalytic cracking unit at Amoco Oil Co.'s Yorktown, VA, refinery.

Rossiter, A.P.; Spriggs, H.D. (Linnhoff March, Inc., Leesburg, VA (United States)); Klee, H. Jr. (Amoco Corp., Chicago, IL (United States))

1993-01-01T23:59:59.000Z

260

Process for treating alkaline wastes for vitrification  

DOE Patents [OSTI]

A process for treating alkaline wastes for vitrification. The process involves acidifying the wastes with an oxidizing agent such as nitric acid, then adding formic acid as a reducing agent, and then mixing with glass formers to produce a melter feed. The nitric acid contributes nitrates that act as an oxidant to balance the redox of the melter feed, prevent reduction of certain species to produce conducting metals, and lower the pH of the wastes to a suitable level for melter operation. The formic acid reduces mercury compounds to elemental mercury for removal by steam stripping, and MnO.sub.2 to the Mn(II) ion to prevent foaming of the glass melt. The optimum amounts of nitric acid and formic acid are determined in relation to the composition of the wastes, including the concentrations of mercury (II) and MnO.sub.2, noble metal compounds, nitrates, formates and so forth. The process minimizes the amount of hydrogen generated during treatment, while producing a redox-balanced feed for effective melter operation and a quality glass product.

Hsu, Chia-lin W. (Augusta, GA)

1995-01-01T23:59:59.000Z

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


261

Process for treating alkaline wastes for vitrification  

DOE Patents [OSTI]

A process is described for treating alkaline wastes for vitrification. The process involves acidifying the wastes with an oxidizing agent such as nitric acid, then adding formic acid as a reducing agent, and then mixing with glass formers to produce a melter feed. The nitric acid contributes nitrates that act as an oxidant to balance the redox of the melter feed, prevent reduction of certain species to produce conducting metals, and lower the pH of the wastes to a suitable level for melter operation. The formic acid reduces mercury compounds to elemental mercury for removal by steam stripping, and MnO{sub 2} to the Mn(II) ion to prevent foaming of the glass melt. The optimum amounts of nitric acid and formic acid are determined in relation to the composition of the wastes, including the concentrations of mercury (II) and MnO{sub 2}, noble metal compounds, nitrates, formates and so forth. The process minimizes the amount of hydrogen generated during treatment, while producing a redox-balanced feed for effective melter operation and a quality glass product. 4 figs.

Hsu, C.L.W.

1995-07-25T23:59:59.000Z

262

Land treatment for seafood processing waste  

SciTech Connect (OSTI)

The purpose of this paper is twofold. The first is to describe selected waste water parameters at two small seafood processing plants in the eastern part of North Carolina. The second is to describe the land treatment system serving these industries and to characterize the quality of the shallow ground water exiting these systems. One of the seafood processing plants is a flounder fileting operation and the other processes crabs. Both plants employ between 10 and 40 individuals, and the processing operation is done mostly by hand.

Rubin, A.R.; McClease, J.D.; Morgan, C.B.

1983-12-01T23:59:59.000Z

263

Transuranic radionuclides from resuspension in the environment, a bibliography  

SciTech Connect (OSTI)

The purpose of this project was to compile a bibliography of references containing environmental transuranic radionuclide data. Our intent was to identify those parameters affecting transuranic radionuclide transport that may be generic and those that may be dependent on chemical form and/or environmental conditions. An understanding of the unique characteristics and similarities between source terms and environmental conditions relative to transuranic radionuclide transport and cycling will provide the ability to assess and predict the long term impact on man and the environment. An additional goal of our literature review, was to extract the ranges of environmental transuranic radionuclide data from the identified references for inclusion in a data base. Related to source term, these ranges of data can be used to calculate the dose to man from the radionuclides, and to perform uncertainty analyses on these dose assessments. On the basis of our reviews, we have arbitrarily outlined five general source terms. These are fallout, fuel cycle waste, accidents, disposal sites and resuspension. Resuspension of the transuranic radionuclides is an unique source term, in that the radionuclides can originate from any of the other source terms. If these transuranic radionuclides become resuspended into the air, they then become important as a source of inhaled radionuclides. This bibliography is a compilation of the references containing studies of plutonium and americium in the environment as a result of resuspension.

Stoker, A.C.; Shinn, J.H.; Noshkin, V.E. [and others

1994-04-01T23:59:59.000Z

264

Transuranic radionuclides dispersed into the aquatic environment, a bibliography  

SciTech Connect (OSTI)

The purpose of this project was to compile a bibliography of references containing environmental transuranic radionuclide data. Our intent was to identify those parameters affecting transuranic radionuclide transport that may be generic and those that may be dependent on chemical form and/or environmental conditions (i.e., site specific) in terrestrial, aquatic and atmospheric environments An understanding of the unique characteristics and similarities between source terms and environmental conditions relative to transuranic radionuclide transport and cycling will provide the ability to assess and predict the long term impact on man and the environment. An additional goal of our literature review, was to extract the ranges of environmental transuranic radionuclide data from the identified references for inclusion in a data base. Related to source term, these ranges of data can be used to calculate the dose to man from the radionuclides, and to perform uncertainty analyses on these dose assessments. On the basis of our reviews, we have arbitrarily outlined five general source terms. These are fallout, fuel cycle waste, accidents, disposal sites and resuspension. Resuspension of the transuranic radionuclides is a unique source term, in that the radionuclides can originate from any of the other source terms. If these transuranic radionuclides become resuspended into the air, they then become important as a source of inhaled radionuclides.

Noshkin, V.E.; Stoker, A.C.; Wong, Kai M. [and others

1994-04-01T23:59:59.000Z

265

Office of Waste Processing Technical Exchange  

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

Agenda Hotel Register Contacts Event Media Speaker Information Home Agenda Hotel Register Contacts Event Media Speaker Information Home Environmental Management Waste Processing Technical Exchange 2010 in Atlanta, GA, November 16 - 18. Over the past eight years, personnel from the three sites, Savannah River/Hanford/Idaho along with others receiving funding from the Environmental Management Office of Waste Processing have met to exchange recent results of on-going field operations and technology development. The purpose of this exchange is to provide a forum for discussion of each Site's efforts to accelerate cleanup operations. Keys to success and lessons learned are openly exchanged in a manner to allow for open discussion between operations, engineering and scientists to accelerate transition of technologies from concepts to field implementation.

266

Waste minimization at a plutonium processing facility  

SciTech Connect (OSTI)

As part of Los Alamos National Laboratory`s (LANL) mission to reduce the nuclear danger throughout the world, the plutonium processing facility at LANL maintains expertise and skills in nuclear weapons technologies as well as leadership in all peaceful applications of plutonium technologies, including fuel fabrication for terrestrial and space reactors and heat sources and thermoelectric generators for space missions. Another near-term challenge resulted from two safety assessments performed by the Defense Nuclear Facilities Safety Board and the U.S. Department of Energy during the past two years. These assessments have necessitated the processing and stabilization of plutonium contained in tons of residues so that they can be stored safely for an indefinite period. This report describes waste streams and approaches to waste reduction of plutonium management.

Pillay, K.K.S. [Los Alamos National Laboratory, NM (United States)

1995-12-31T23:59:59.000Z

267

An approach for sampling solid heterogeneous waste at the Hanford Site waste receiving and processing and solid waste projects  

SciTech Connect (OSTI)

This paper addresses the problem of obtaining meaningful data from samples of solid heterogeneous waste while maintaining sample rates as low as practical. The Waste Receiving and Processing Facility, Module 1, at the Hanford Site in south-central Washington State will process mostly heterogeneous solid wastes. The presence of hazardous materials is documented for some packages and unknown for others. Waste characterization is needed to segregate the waste, meet waste acceptance and shipping requirements, and meet facility permitting requirements. Sampling and analysis are expensive, and no amount of sampling will produce absolute certainty of waste contents. A sampling strategy is proposed that provides acceptable confidence with achievable sampling rates.

Sexton, R.A.

1993-03-01T23:59:59.000Z

268

Section 24: Waste Characterization  

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

Energy (DOE). 1995b. Transuranic Waste Baseline Inventory Report (Revision 2, December). DOECAO-95-1121. ERMS 531643. Carlsbad Area Office, Carlsbad, NM. PDF Author U.S....

269

Savannah River Site Marks Waste Processing Milestone with Melter's  

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

Savannah River Site Marks Waste Processing Milestone with Savannah River Site Marks Waste Processing Milestone with Melter's 2,000th Waste Canister Savannah River Site Marks Waste Processing Milestone with Melter's 2,000th Waste Canister February 1, 2012 - 12:00pm Addthis A Savannah River Remediation employee uses a manipulator located inside a shielded enclosure at the Defense Waste Processing Facility, where a melter pours molten glass into a canister. A Savannah River Remediation employee uses a manipulator located inside a shielded enclosure at the Defense Waste Processing Facility, where a melter pours molten glass into a canister. AIKEN, S.C. - The second melter to operate in the 16-year history of the nation's largest radioactive waste glassification plant shows no signs of slowing after recently pouring its 2,000 canister of glass-formed hazardous

270

Savannah River Site Marks Waste Processing Milestone with Melter's  

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

Marks Waste Processing Milestone with Marks Waste Processing Milestone with Melter's 2,000th Waste Canister Savannah River Site Marks Waste Processing Milestone with Melter's 2,000th Waste Canister February 1, 2012 - 12:00pm Addthis A Savannah River Remediation employee uses a manipulator located inside a shielded enclosure at the Defense Waste Processing Facility, where a melter pours molten glass into a canister. A Savannah River Remediation employee uses a manipulator located inside a shielded enclosure at the Defense Waste Processing Facility, where a melter pours molten glass into a canister. AIKEN, S.C. - The second melter to operate in the 16-year history of the nation's largest radioactive waste glassification plant shows no signs of slowing after recently pouring its 2,000 canister of glass-formed hazardous

271

November 8, 1983: Defense Waste Processing Facility | Department of Energy  

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

November 8, 1983: Defense Waste Processing Facility November 8, 1983: Defense Waste Processing Facility November 8, 1983: Defense Waste Processing Facility November 8, 1983: Defense Waste Processing Facility November 8, 1983 The Department begins construction of the Defense Waste Processing Facility (DWPF) at the Savannah River Plant in South Carolina. DWPF is designed to make high-level nuclear waste into a glass-like substance, which will then be shipped to a repository. DWPF will mix borosilicate glass with the waste, heat it to 2000 degrees F, and pour the mixture into stainless steel canisters. The mixture will cool into solid glass that can be permanently stored. DWPF will immobilize the more than 34 million gallons of liquid high-level waste that have accumulated from producing defense-related nuclear materials

272

WIPP Receives Waste Characterized With Mobile System  

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

For Immediate Release WIPP Receives Waste Characterized With Mobile System CARLSBAD, N.M., April 12, 2002 - The first shipment of transuranic waste characterized by the Central...

273

Savannah River Site- Salt Waste Processing Facility: Briefing on the Salt Waste Processing Facility Independent Technical Review  

Broader source: Energy.gov [DOE]

This is a presentation outlining the Salt Waste Processing Facility process, major risks, approach for conducting reviews, discussion of the findings, and conclusions.

274

EPA Citizens Guide to Hazardous Waste Permitting Process | Open...  

Open Energy Info (EERE)

Citizens Guide to Hazardous Waste Permitting Process Jump to: navigation, search OpenEI Reference LibraryAdd to library Web Site: EPA Citizens Guide to Hazardous Waste Permitting...

275

Buried waste integrated demonstration technology integration process  

SciTech Connect (OSTI)

A Technology integration Process was developed for the Idaho National Energy Laboratories (INEL) Buried Waste Integrated Demonstration (BWID) Program to facilitate the transfer of technology and knowledge from industry, universities, and other Federal agencies into the BWID; to successfully transfer demonstrated technology and knowledge from the BWID to industry, universities, and other Federal agencies; and to share demonstrated technologies and knowledge between Integrated Demonstrations and other Department of Energy (DOE) spread throughout the DOE Complex. This document also details specific methods and tools for integrating and transferring technologies into or out of the BWID program. The document provides background on the BWID program and technology development needs, demonstrates the direction of technology transfer, illustrates current processes for this transfer, and lists points of contact for prospective participants in the BWID technology transfer efforts. The Technology Integration Process was prepared to ensure compliance with the requirements of DOE`s Office of Technology Development (OTD).

Ferguson, J.S.; Ferguson, J.E.

1992-04-01T23:59:59.000Z

276

Buried waste integrated demonstration technology integration process  

SciTech Connect (OSTI)

A Technology integration Process was developed for the Idaho National Energy Laboratories (INEL) Buried Waste Integrated Demonstration (BWID) Program to facilitate the transfer of technology and knowledge from industry, universities, and other Federal agencies into the BWID; to successfully transfer demonstrated technology and knowledge from the BWID to industry, universities, and other Federal agencies; and to share demonstrated technologies and knowledge between Integrated Demonstrations and other Department of Energy (DOE) spread throughout the DOE Complex. This document also details specific methods and tools for integrating and transferring technologies into or out of the BWID program. The document provides background on the BWID program and technology development needs, demonstrates the direction of technology transfer, illustrates current processes for this transfer, and lists points of contact for prospective participants in the BWID technology transfer efforts. The Technology Integration Process was prepared to ensure compliance with the requirements of DOE's Office of Technology Development (OTD).

Ferguson, J.S.; Ferguson, J.E.

1992-04-01T23:59:59.000Z

277

GEOTECHNICAL/GEOCHEMICAL CHARACTERIZATION OF ADVANCED COAL PROCESS WASTE STREAMS  

SciTech Connect (OSTI)

Thirteen solid wastes, six coals and one unreacted sorbent produced from seven advanced coal utilization processes were characterized for task three of this project. The advanced processes from which samples were obtained included a gas-reburning sorbent injection process, a pressurized fluidized-bed coal combustion process, a coal-reburning process, a SO{sub x}, NO{sub x}, RO{sub x}, BOX process, an advanced flue desulfurization process, and an advanced coal cleaning process. The waste samples ranged from coarse materials, such as bottom ashes and spent bed materials, to fine materials such as fly ashes and cyclone ashes. Based on the results of the waste characterizations, an analysis of appropriate waste management practices for the advanced process wastes was done. The analysis indicated that using conventional waste management technology should be possible for disposal of all the advanced process wastes studied for task three. However, some wastes did possess properties that could present special problems for conventional waste management systems. Several task three wastes were self-hardening materials and one was self-heating. Self-hardening is caused by cementitious and pozzolanic reactions that occur when water is added to the waste. All of the self-hardening wastes setup slowly (in a matter of hours or days rather than minutes). Thus these wastes can still be handled with conventional management systems if care is taken not to allow them to setup in storage bins or transport vehicles. Waste self-heating is caused by the exothermic hydration of lime when the waste is mixed with conditioning water. If enough lime is present, the temperature of the waste will rise until steam is produced. It is recommended that self-heating wastes be conditioned in a controlled manner so that the heat will be safely dissipated before the material is transported to an ultimate disposal site. Waste utilization is important because an advanced process waste will not require ultimate disposal when it is put to use. Each task three waste was evaluated for utilization potential based on its physical properties, bulk chemical composition, and mineral composition. Only one of the thirteen materials studied might be suitable for use as a pozzolanic concrete additive. However, many wastes appeared to be suitable for other high-volume uses such as blasting grit, fine aggregate for asphalt concrete, road deicer, structural fill material, soil stabilization additives, waste stabilization additives, landfill cover material, and pavement base course construction.

Edwin S. Olson; Charles J. Moretti

1999-11-01T23:59:59.000Z

278

Microsoft Word - Tran Waste final report 2-8-05.doc  

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

Transuranic Waste Management at Transuranic Waste Management at Los Alamos National Laboratory DOE/IG-0673 February 2005 REPORT ON TRANSURANIC WASTE MANAGEMENT AT LOS ALAMOS NATIONAL LABORATORY TABLE OF CONTENTS Legacy Transuranic Waste Disposal Details of Finding 1 Recommendations and Comments 4 Appendices 1. Objective, Scope, and Methodology 6 2. Transuranic Waste Storage 8 3. Prior Audit Reports 10 4. Management Comments 11 Legacy Transuranic Waste Disposal Page 1 Details of Finding Background Los Alamos National Laboratory (Los Alamos) has been involved in the development, production, and maintenance of the Nation's nuclear weapons stockpile for over six decades. Research, development, and fabrication of weapons components produced a

279

Nondestructive radioassay for waste management: an assessment  

SciTech Connect (OSTI)

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

Lehmkuhl, G.D.

1981-06-01T23:59:59.000Z

280

Remote-handled transuranic system assessment. Volume 1  

SciTech Connect (OSTI)

This document identifies the necessary actions for addressing current questions concerning the safe and efficient disposal of remote-handled transuranic wastes that have been generated through Department of Energy activities. In addition, this document presents summaries of existing information and analyses regarding the potential alternatives for disposing of remote-handled (RH) transuranic (TRU) waste at the Department of Energy (DOE) Waste Isolation Pilot Plant (WIPP). A further discussion of DOE`s approach for addressing RH-TRU issues is contained in the document, Waste Isolation Pilot Plant Remote-Handled Transuranic Waste Disposal Strategy, DOE/WIPP-95-1090 (DOE, 1995a). Of this stored and projected inventory, approximately 30% can be characterized with current technology and subsequently certified to meet the waste acceptance criteria for disposal at WIPP; characterization of the remaining 70% will require the use of alternative techniques. At most of the generator sites, characterization equipment and facilities need to be procured in order for the sites to certify waste for shipment either to WIPP or to an interim site. If surface dose rates are too high, the use of non-invasive techniques such as non-destructive examination (NDE) and non-destructive assay (NDA) may be precluded. Characterization methods using NDA can be effectively used on RH-TRU wastes with surface dose rates of less than 1.0 rem/hr (neutron); NDE methods are effective on waste with surface dose rates of less than 10 rem/hr (gamma). The ability to use current NDE technology on waste with surface dose rates above 10 rem/hr will need to be demonstrated. Alternate characterization techniques, such as examination within a hot cell, could be used for the remaining waste; however, such techniques are labor intensive and would require additional effort to gather assay data. Improvements in characterization capabilities are being pursued through future technology development initiatives.

NONE

1995-11-01T23:59:59.000Z

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


281

Independent Oversight Assessment, Salt Waste Processing Facility Project -  

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

Salt Waste Processing Facility Salt Waste Processing Facility Project - January 2013 Independent Oversight Assessment, Salt Waste Processing Facility Project - January 2013 January 2013 Assessment of Nuclear Safety Culture at the Salt Waste Processing Facility Project The U.S. Department of Energy (DOE) Office of Enforcement and Oversight (Independent Oversight), within the Office of Health, Safety and Security (HSS), conducted an independent assessment of nuclear safety culture at the Salt Waste Processing Facility (SWPF) Project. The primary objective of the evaluation was to provide information regarding the status of the safety culture at the SWPF Project. The data collection phase of the assessment occurred during August - September 2012. Independent Oversight Assessment, Salt Waste Processing Facility Project -

282

Environmentally-friendly organochlorine waste processing and recycling  

E-Print Network [OSTI]

; 5) purification of VCM; 6) burning organochlorine waste (OCW) (Lakshmanan et al., 1999). In additionEnvironmentally-friendly organochlorine waste processing and recycling Sergei A. Kurta a , Alex A in revised form 12 May 2013 Accepted 12 May 2013 Available online 20 May 2013 Keywords: Organochlorine waste

Volinsky, Alex A.

283

EIS-0082: Defense Waste Processing Facility, Savannah River Plant  

Broader source: Energy.gov [DOE]

The Office of Defense Waste and Byproducts Management developed this EIS to provide environmental input into both the selection of an appropriate strategy for the permanent disposal of the high-level radioactive waste currently stored at the Savannah River Plant (SRP) and the subsequent decision to construct and operate a Defense Waste Processing Facility at the SRP site.

284

Effects of biodrying process on municipal solid waste properties  

Science Journals Connector (OSTI)

In this paper, the effect of biodrying process on municipal solid waste (MSW) properties was studied. The results obtained indicated that after 14d, biodrying reduced the water content of waste, allowing the production of biodried waste with a net heating value (NHV) of 16,7792,074kJkg?1 wet weight, i.e. 41% higher than that of untreated waste. The low moisture content of the biodried material reduced, also, the potential impacts of the waste, i.e. potential self-ignition and potential odors production. Low waste impacts suggest to landfill the biodried material obtaining energy via biogas production by waste re-moistening, i.e. bioreactor. Nevertheless, results of this work indicate that biodrying process because of the partial degradation of the organic fraction contained in the waste (losses of 290gkg?1 VS), reduced of about 28% the total producible biogas.

F. Tambone; B. Scaglia; S. Scotti; F. Adani

2011-01-01T23:59:59.000Z

285

Characterization of industrial process waste heat and input heat streams  

SciTech Connect (OSTI)

The nature and extent of industrial waste heat associated with the manufacturing sector of the US economy are identified. Industry energy information is reviewed and the energy content in waste heat streams emanating from 108 energy-intensive industrial processes is estimated. Generic types of process equipment are identified and the energy content in gaseous, liquid, and steam waste streams emanating from this equipment is evaluated. Matchups between the energy content of waste heat streams and candidate uses are identified. The resultant matrix identifies 256 source/sink (waste heat/candidate input heat) temperature combinations. (MHR)

Wilfert, G.L.; Huber, H.B.; Dodge, R.E.; Garrett-Price, B.A.; Fassbender, L.L.; Griffin, E.A.; Brown, D.R.; Moore, N.L.

1984-05-01T23:59:59.000Z

286

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

SciTech Connect (OSTI)

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

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

1995-09-01T23:59:59.000Z

287

Waste Analysis Plan for the Waste Receiving and Processing (WRAP) Facility  

SciTech Connect (OSTI)

The purpose of this waste analysis plan (WAP) is to document the waste acceptance process, sampling methodologies, analytical techniques, and overall processes that are undertaken for dangerous, mixed, and radioactive waste accepted for confirmation, nondestructive examination (NDE) and nondestructive assay (NDA), repackaging, certification, and/or storage at the Waste Receiving and Processing Facility (WRAP). Mixed and/or radioactive waste is treated at WRAP. WRAP is located in the 200 West Area of the Hanford Facility, Richland, Washington. Because dangerous waste does not include source, special nuclear, and by-product material components of mixed waste, radionuclides are not within the scope of this documentation. The information on radionuclides is provided only for general knowledge.

TRINER, G.C.

1999-11-01T23:59:59.000Z

288

An introduction to the mechanics of performance assessment using examples of calculations done for the Waste Isolation Pilot Plant between 1990 and 1992. Revision  

SciTech Connect (OSTI)

This document provides an overview of the processes used to access the performance of the Waste Isolation Pilot Plant (WIPP). The quantitative metrics used in the performance-assessment (PA) process are those put forward in the Environmental Protection Agency`s Environmental Standards for the Management and Disposal of Spent Nuclear Fuel, HIgh-LEvel and transuranic radioactive Wastes (40 CFR 191).

Rechard, R.P.

1996-06-01T23:59:59.000Z

289

Chapter 38 Hazardous Waste Permitting Process (Kentucky) | Department of  

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

8 Hazardous Waste Permitting Process (Kentucky) 8 Hazardous Waste Permitting Process (Kentucky) Chapter 38 Hazardous Waste Permitting Process (Kentucky) < Back Eligibility Agricultural Commercial Construction Developer Fed. Government Industrial Institutional Investor-Owned Utility Local Government Municipal/Public Utility Rural Electric Cooperative Schools State/Provincial Govt Transportation Tribal Government Utility Savings Category Alternative Fuel Vehicles Hydrogen & Fuel Cells Program Info State Kentucky Program Type Environmental Regulations Provider Department for Environmental Protection This administrative regulation establishes the general provisions for storage, treatment, recycling, or disposal of hazardous waste. It provides information about permits and specific requirements for containers, tanks,

290

Progress of the High Level Waste Program at the Defense Waste Processing Facility - 13178  

SciTech Connect (OSTI)

The Defense Waste Processing Facility at the Savannah River Site treats and immobilizes High Level Waste into a durable borosilicate glass for safe, permanent storage. The High Level Waste program significantly reduces environmental risks associated with the storage of radioactive waste from legacy efforts to separate fissionable nuclear material from irradiated targets and fuels. In an effort to support the disposition of radioactive waste and accelerate tank closure at the Savannah River Site, the Defense Waste Processing Facility recently implemented facility and flowsheet modifications to improve production by 25%. These improvements, while low in cost, translated to record facility production in fiscal years 2011 and 2012. In addition, significant progress has been accomplished on longer term projects aimed at simplifying and expanding the flexibility of the existing flowsheet in order to accommodate future processing needs and goals. (authors)

Bricker, Jonathan M.; Fellinger, Terri L.; Staub, Aaron V.; Ray, Jeff W.; Iaukea, John F. [Savannah River Remediation, Aiken, South Carolina, 29808 (United States)] [Savannah River Remediation, Aiken, South Carolina, 29808 (United States)

2013-07-01T23:59:59.000Z

291

Hanford Shipment Arrives Safely At Waste Isolation Pilot Plant  

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

63 shipments of transuranic waste. DOE has disposed of 41 shipments of waste from the Rocky Flats Environmental Technology Site (Boulder, Colorado), 17 shipments from Los...

292

Independent Oversight Review, Savannah River Site Salt Waste Processing  

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

Savannah River Site Salt Waste Savannah River Site Salt Waste Processing Facility - August 2013 Independent Oversight Review, Savannah River Site Salt Waste Processing Facility - August 2013 August 2013 Review of the Savannah River Site Salt Waste Processing Facility Safety Basis and Design Development. This report documents the results of an independent oversight review of the safety basis and design development for the Salt Waste Processing Facility (SWPF) at the U.S. Department of Energy (DOE) Savannah River Site. The review was performed February 12-14, 2013 by DOE's Office of Safety and Emergency Management Evaluations, which is within the DOE Office of Health, Safety and Security. The purpose of the review was to evaluate the safety basis, design, and the associated technical documents developed for

293

Independent Oversight Review, Savannah River Site Salt Waste Processing  

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

Savannah River Site Salt Waste Savannah River Site Salt Waste Processing Facility - August 2013 Independent Oversight Review, Savannah River Site Salt Waste Processing Facility - August 2013 August 2013 Review of the Savannah River Site Salt Waste Processing Facility Safety Basis and Design Development. This report documents the results of an independent oversight review of the safety basis and design development for the Salt Waste Processing Facility (SWPF) at the U.S. Department of Energy (DOE) Savannah River Site. The review was performed February 12-14, 2013 by DOE's Office of Safety and Emergency Management Evaluations, which is within the DOE Office of Health, Safety and Security. The purpose of the review was to evaluate the safety basis, design, and the associated technical documents developed for

294

Process for removing sulfate anions from waste water  

DOE Patents [OSTI]

A liquid emulsion membrane process for removing sulfate anions from waste water is disclosed. The liquid emulsion membrane process includes the steps of: (a) providing a liquid emulsion formed from an aqueous strip solution and an organic phase that contains an extractant capable of removing sulfate anions from waste water; (b) dispersing the liquid emulsion in globule form into a quantity of waste water containing sulfate anions to allow the organic phase in each globule of the emulsion to extract and absorb sulfate anions from the waste water and (c) separating the emulsion including its organic phase and absorbed sulfate anions from the waste water to provide waste water containing substantially no sulfate anions.

Nilsen, David N. (Lebanon, OR); Galvan, Gloria J. (Albany, OR); Hundley, Gary L. (Corvallis, OR); Wright, John B. (Albany, OR)

1997-01-01T23:59:59.000Z

295

Waste Heat Recovery from Industrial Process Heating Equipment -  

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

Waste Heat Recovery from Industrial Process Heating Equipment - Waste Heat Recovery from Industrial Process Heating Equipment - Cross-cutting Research and Development Priorities Speaker(s): Sachin Nimbalkar Date: January 17, 2013 - 11:00am Location: 90-2063 Seminar Host/Point of Contact: Aimee McKane Waste heat is generated from several industrial systems used in manufacturing. The waste heat sources are distributed throughout a plant. The largest source for most industries is exhaust / flue gases or heated air from heating systems. This includes the high temperature gases from burners in process heating, lower temperature gases from heat treat, dryers, and heaters, heat from heat exchangers, cooling liquids and gases etc. The previous studies and direct contact with the industry as well as equipment suppliers have shown that a large amount of waste heat is not

296

Solid Waste Management Plan. Revision 4  

SciTech Connect (OSTI)

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

NONE

1995-04-26T23:59:59.000Z

297

Co-processing of agricultural and biomass waste with coal  

SciTech Connect (OSTI)

A major thrust of our research program is the use of waste materials as co-liquefaction agents for the first-stage conversion of coal to liquid fuels. By fulfilling one or more of the roles of an expensive solvent in the direct coal liquefaction (DCL) process, the waste material is disposed off ex-landfill, and may improve the overall economics of DCL. Work in our group has concentrated on co-liquefaction with waste rubber tires, some results from which are presented elsewhere in these Preprints. In this paper, we report on preliminary results with agricultural and biomass-type waste as co-liquefaction agents.

Stiller, A.H.; Dadyburjor, D.B.; Wann, Ji-Perng [West Virginia Univ., Morgantown, WV (United States)] [and others

1995-12-31T23:59:59.000Z

298

Hanford's Simulated Low Activity Waste Cast Stone Processing  

SciTech Connect (OSTI)

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

Kim, Young

2013-08-20T23:59:59.000Z

299

Transfer Lines to Connect Liquid Waste Facilities and Salt Waste Processing Facility  

Broader source: Energy.gov [DOE]

AIKEN, S.C. Officials with the EM program at Savannah River Site (SRS) recently announced a key milestone in preparation for the startup of the Salt Waste Processing Facility (SWPF): workers installed more than 1,200 feet of new transfer lines that will eventually connect existing liquid waste facilities to SWPF.

300

Retrieval process development and enhancements waste simulant compositions and defensibility  

SciTech Connect (OSTI)

The purpose of this report is to document the physical waste simulant development efforts of the EM-50 Tanks Focus Area at the Hanford Site. Waste simulants are used in the testing and development of waste treatment and handling processes because performing such tests using actual tank waste is hazardous and prohibitively expensive. This document addresses the simulant development work that supports the testing of waste retrieval processes using simulants that mimic certain key physical properties of the tank waste. Development and testing of chemical simulants are described elsewhere. This work was funded through the EM-50 Tanks Focus Area as part of the Retrieval Process Development and Enhancements (RPD&E) Project at the Pacific Northwest National Laboratory (PNNL). The mission of RPD&E is to understand retrieval processes, including emerging and existing processes, gather performance data on those processes, and relate the data to specific tank problems to provide end users with the requisite technical bases to make retrieval and closure decisions. Physical simulants are prepared using relatively nonhazardous and inexpensive materials rather than the chemicals known to be in tank waste. Consequently, only some of the waste properties are matched by the simulant. Deciding which properties need to be matched and which do not requires a detailed knowledge of the physics of the process to be tested using the simulant. Developing this knowledge requires reviews of available literature, consultation with experts, and parametric tests. Once the relevant properties are identified, waste characterization data are reviewed to establish the target ranges for each property. Simulants are then developed that possess the desired ranges of properties.

Powell, M.R.; Golcar, G.R.; Geeting, J.G.H.

1997-09-01T23:59:59.000Z

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


301

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

DOE Patents [OSTI]

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

Herrmann, Steven Douglas

2014-05-27T23:59:59.000Z

302

Savannah River Site Waste Isolation Pilot Plant Disposal Program - Acceptable Knowledge Summary Report for Waste Stream: SR-T001-221-HET  

SciTech Connect (OSTI)

This document, along with referenced supporting documents provides a defensible and auditable record of acceptable knowledge for one of the waste streams from the FB-Line. This heterogeneous debris transuranic waste stream was generated after January 25, 1990 and before March 20, 1997. The waste was packaged in 55-gallon drums, then shipped to the transuranic waste storage facility in ''E'' area of the Savannah River Site. This acceptable knowledge report includes information relating to the facility's history, configuration, equipment, process operations and waste management practices. Information contained in this report was obtained from numerous sources including: facility safety basis documentation, historical document archives, generator and storage facility waste records and documents, and interviews with cognizant personnel.

Lunsford, G.F.

2001-01-24T23:59:59.000Z

303

Accelerator Production of Tritium project process waste assessment  

SciTech Connect (OSTI)

DOE has made a commitment to compliance with all applicable environmental regulatory requirements. In this respect, it is important to consider and design all tritium supply alternatives so that they can comply with these requirements. The management of waste is an integral part of this activity and it is therefore necessary to estimate the quantities and specific wastes that will be generated by all tritium supply alternatives. A thorough assessment of waste streams includes waste characterization, quantification, and the identification of treatment and disposal options. The waste assessment for APT has been covered in two reports. The first report was a process waste assessment (PWA) that identified and quantified waste streams associated with both target designs and fulfilled the requirements of APT Work Breakdown Structure (WBS) Item 5.5.2.1. This second report is an expanded version of the first that includes all of the data of the first report, plus an assessment of treatment and disposal options for each waste stream identified in the initial report. The latter information was initially planned to be issued as a separate Waste Treatment and Disposal Options Assessment Report (WBS Item 5.5.2.2).

Carson, S.D.; Peterson, P.K.

1995-09-01T23:59:59.000Z

304

Detecting low levels of transuranics with electron energy loss spectroscopy  

Science Journals Connector (OSTI)

With the second difference electron energy loss spectroscopy (EELS) technique, transuranic (TRU) and rare-earth (RE) elements have been detected at low concentration levels (< 200 ppm) in alteration phases formed during the laboratory corrosion of nuclear waste glass. Use of the high-energy M4,5 edges to detect TRU elements is the only method available to positively identify them because the weaker lower-energy N4,5 edges overlap with the more intense M4,5 edges of the trace levels of \\{REs\\} that may be present in the same alteration phases. The position and intensity of the M4,5 absorption edges of the TRU were confirmed with samples of transuranic contaminated soils and data from the literature. The M4 : M5 ratio for the actinide absorption edges was used, in combination with crystal chemical considerations to determine chemical state.

E.C. Buck; J.A. Fortner

1997-01-01T23:59:59.000Z

305

Reliability analysis of common hazardous waste treatment processes  

SciTech Connect (OSTI)

Five hazardous waste treatment processes are analyzed probabilistically using Monte Carlo simulation to elucidate the relationships between process safety factors and reliability levels. The treatment processes evaluated are packed tower aeration, reverse osmosis, activated sludge, upflow anaerobic sludge blanket, and activated carbon adsorption.

Waters, R.D. [Vanderbilt Univ., Nashville, TN (United States)

1993-05-01T23:59:59.000Z

306

Systematic Waste Minimization in Chemical Processes. 1. Methodology  

Science Journals Connector (OSTI)

22 In MFM, the functional structure of a system is described using a set of interrelated structures for mass, energy, and information flows. ... (1)?Dantus, M. M.; High, K. A. Economic Evaluation for the Retrofit of Chemical Processes through Waste Minimization and Process Integration. ... Price-Targeting Through Iterative Flowsheet Syntheses in Developing Novel Processing Equipment:? Pervaporation ...

Iskandar Halim; Rajagopalan Srinivasan

2002-01-16T23:59:59.000Z

307

Electromagnetic mixed waste processing system for asbestos decontamination  

SciTech Connect (OSTI)

DOE sites contain a broad spectrum of asbestos materials (cloth, pipe lagging, sprayed insulation and other substances) which are contaminated with a combination of hazardous and radioactive wastes due to its use during the development of the US nuclear weapons complex. These wastes consist of cutting oils, lubricants, solvents, PCBs, heavy metals and radioactive contaminants. The radioactive contaminants are the activation, decay, and fission products of DOE operations. To allow disposal, the asbestos must be converted chemically, followed by removing and separating the hazardous and radioactive materials to prevent the formation of mixed wastes and to allow for both sanitary disposal and effective decontamination. Currently, no technology exists that can meet these sanitary and other objectives. An attempt was made to apply techniques that have already proved successful in the mining, oil, and metals processing industries to the development of a multi-stage process to remove and separate hazardous chemical radioactive materials from asbestos. This process uses three methods: ABCOV chemicals which converts the asbestos to a sanitary waste; dielectric heating to volatilize the organic materials; and electrochemical processing for the removal of heavy metals, RCRA wastes and radionuclides. This process will result in the destruction of over 99% of the asbestos; limit radioactive metal contamination to 0.2 Bq alpha per gram and 1 Bq beta and gamma per gram; reduce hazardous organics to levels compatible with current EPA policy for RCRA delisting; and achieve TCLP limits for all solidified waste.

Kasevich, R.S.; Nocito, T.; Vaux, W.G.; Snyder, T.

1994-12-31T23:59:59.000Z

308

Waste Treatment Technology Process Development Plan For Hanford Waste Treatment Plant Low Activity Waste Recycle  

SciTech Connect (OSTI)

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

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

2013-08-29T23:59:59.000Z

309

DOE Office of Waste Processing Technical Exchange - Agenda  

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

June 1, 2009 June 1, 2009 Agenda Hotel Information Registration Presentation Guidelines Poster Guidelines Webcast Waiver Contacts Home Waste Processing Technical Exchange Agenda (Version 1.1) Pre-Registration: Monday, May 18, 5:00p - 7:00p Organizer/Session Chair: Blocker (early registration & speaker check-in) Day 1: Tuesday, May 19 Registration - 7:00a - 8:00a Session One - Opening Session Two - Waste Retrieval and Closure 1 Session Three - Waste Form Development Day 2: Wednesday, May 20 Session Four - Pretreatment 1 Session Five - Facility Readiness and Start-up Session Six - Pretreatment 2 Session Seven - Waste Retrieval and Closure 2 Session Eight - Poster Presentations Day 3: Thursday, May 21 Session Nine - Regulatory Activity and Performance Assessment Session Ten - Waste Storage and Tank Farm Operational Improvements

310

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

SciTech Connect (OSTI)

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

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

1993-12-01T23:59:59.000Z

311

Acceptable Knowledge Summary Report for Waste Stream: SR-T001-221F-HET/Drums  

SciTech Connect (OSTI)

Since beginning operations in 1954, the Department of Energy's Savannah River Site FB-Line conducted atomic energy defense activities consistent with the listing in Section 10101(3) of the Nuclear Waste Policy Act of 1982. The facility mission was to process and convert dilute plutonium solution into highly purified weapons grade plutonium metal. As a result of various activities conducted in support of the mission (e.g., operation, maintenance, repair, clean up, and facility modifications), the facility generated transuranic waste. This document, along with referenced supporting documents, provides a defensible and auditable record of acceptable knowledge for one of the waste streams from the FB-Line. The waste was packaged in 55-gallon drums, then shipped to the transuranic waste storage facility in ''E'' area of the Savannah River Site. This acceptable knowledge report includes information relating to the facility's history, configuration,equipment, process operations, and waste management practices.

Lunsford, G.F.

1999-08-23T23:59:59.000Z

312

EA-437; Environmental Assessment Process Equipment Waste and Process Waste Liquid Collection Systems Idaho Chemical Processing Plant Idaho National Engineering Laboratory  

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

437; Environmental Assessment Process Equipment Waste and 437; Environmental Assessment Process Equipment Waste and Process Waste Liquid Collection Systems Idaho Chemical Processing Plant Idaho National Engineering Laboratory TABLE OF CONTENTS Environmental Assessment Process Equipment Waste and Process Waste Liquid Collection Systems Idaho Chemical Processing Plant Idaho National Engineering Laboratory 1. INTRODUCTION 2. DESCRIPTION OF THE PROPOSED ACTION AND ALTERNATIVES 2.1 Purpose and Need of the Proposed Action 2.2 Description of the Affected Facilities 2.3 Description of Proposed Action 2.4 Alternatives to the Proposed Action 2.5 Separate But Related Actions 3. AFFECTED ENVIRONMENT 3.1 Introduction 3.2 Physical Environment 3.3 Biological Resources 3.4 Cultural Resources 3.5 Environmental Quality and Monitoring Programs

313

RECENT PROCESS AND EQUIPMENT IMPROVEMENTS TO INCREASE HIGH LEVEL WASTE THROUGHPUT AT THE DEFENSE WASTE PROCESSING FACILITY  

SciTech Connect (OSTI)

The Savannah River Site's (SRS) Defense Waste Processing Facility (DWPF) began stabilizing high level waste (HLW) in a glass matrix in 1996. Over the past few years, there have been several process and equipment improvements at the DWPF to increase the rate at which the high level waste can be stabilized. These improvements have either directly increased waste processing rates or have desensitized the process to upsets, thereby minimizing downtime and increasing production. Improvements due to optimization of waste throughput with increased HLW loading of the glass resulted in a 6% waste throughput increase based upon operational efficiencies. Improvements in canister production include the pour spout heated bellows liner (5%), glass surge (siphon) protection software (2%), melter feed pump software logic change to prevent spurious interlocks of the feed pump with subsequent dilution of feed stock (2%) and optimization of the steam atomized scrubber (SAS) operation to minimize downtime (3%) for a total increase in canister production of 12%. A number of process recovery efforts have allowed continued operation. These include the off gas system pluggage and restoration, slurry mix evaporator (SME) tank repair and replacement, remote cleaning of melter top head center nozzle, remote melter internal inspection, SAS pump J-Tube recovery, inadvertent pour scenario resolutions, dome heater transformer bus bar cooling water leak repair and new Infra-red camera for determination of glass height in the canister are discussed.

Odriscoll, R; Allan Barnes, A; Jim Coleman, J; Timothy Glover, T; Robert Hopkins, R; Dan Iverson, D; Jeff Leita, J

2008-01-15T23:59:59.000Z

314

Materials evaluation programs at the Defense Waste Processing Facility  

SciTech Connect (OSTI)

The Savannah River Site (SRS) has been operating a nuclear fuel cycle since the 1950s to produce nuclear materials in support of the national defense effort. About 83 million gallons of high-level waste produced since operations began has been consolidated by evaporation into 33 million gallons at the waste tank farm. The Department of Energy authorized the construction of the Defense Waste Processing Facility (DWPF), the function of which is to immobilize the waste as a durable borosilicate glass contained in stainless steel canisters prior to the placement of the canisters in a federal repository. The DWPF is now mechanically complete and is undergoing commissioning and run-in activities. A brief description of the DWPF process is provided.

Gee, J.T.; Iverson, D.C.; Bickford, D.F.

1992-01-01T23:59:59.000Z

315

Materials evaluation programs at the Defense Waste Processing Facility  

SciTech Connect (OSTI)

The Savannah River Site (SRS) has been operating a nuclear fuel cycle since the 1950s to produce nuclear materials in support of the national defense effort. About 83 million gallons of high-level waste produced since operations began has been consolidated by evaporation into 33 million gallons at the waste tank farm. The Department of Energy authorized the construction of the Defense Waste Processing Facility (DWPF), the function of which is to immobilize the waste as a durable borosilicate glass contained in stainless steel canisters prior to the placement of the canisters in a federal repository. The DWPF is now mechanically complete and is undergoing commissioning and run-in activities. A brief description of the DWPF process is provided.

Gee, J.T.; Iverson, D.C.; Bickford, D.F.

1992-12-31T23:59:59.000Z

316

Field study of disposed solid wastes from advanced coal processes  

SciTech Connect (OSTI)

Radian Corporation and the North Dakota Energy and Environmental Research Center (EERC) are funded to develop information to be used by private industry and government agencies for managing solid waste produced by advanced coal processes. This information will be developed by conducting several field studies on disposed wastes from these processes. Data will be collected to characterize these wastes and their interactions with the environments in which they are disposed. Three sites have been selected for the field studies: Colorado Ute's fluidized bed combustion (FBC) unit in Nucla, Colorado; Ohio Edison's limestone injection multistage burner (LIMB) retrofit in Lorain, Ohio; and Freeman United's site using waste from Midwest Grain's FBC unit in central Illinois. A fourth site is under consideration at the Dakota Gasification Company in North Dakota. The first two tasks of this project involved the development of test plans and obtaining site access.

Not Available

1990-01-01T23:59:59.000Z

317

The disposal of orphan wastes using the greater confinement disposal concept  

SciTech Connect (OSTI)

In the United States, radioactive wastes are conventionally classified as high-level wastes, transuranic wastes, or low-level wastes. Each of these types of wastes, by law, has a ``home`` for their final disposal; i.e., high-level wastes are destined for disposal at the proposed repository at Yucca Mountain, transuranic waste for the proposed Waste Isolation Pilot Plant, and low-level waste for shallow-land disposal sites. However, there are some radioactive wastes within the United States Department of Energy (DOE) complex that do not meet the criteria established for disposal of either high-level waste, transuranic waste, or low-level waste. The former are called ``special-case`` or ``orphan`` wastes. This paper describes an ongoing project sponsored by the DOE`s Nevada Operations Office for the disposal of orphan wastes at the Radioactive Waste Management Site at Area 5 of the Nevada Test Site using the greater confinement disposal (GCD) concept. The objectives of the GCD project are to evaluate the safety of the site for disposal of orphan wastes by assessing compliance with pertinent regulations through performance assessment, and to examine the feasibility of this disposal concept as a cost-effective, safe alternative for management of orphan wastes within the DOE complex. Decisions on the use of GCD or other alternate disposal concepts for orphan wastes can be expected to be addressed in a Programmatic Environmental Impact Statement being prepared by DOE. The ultimate decision to use GCD will require a Record of Decision through the National Environmental Policy Act (NEPA) process. 20 refs., 3 figs., 2 tabs.

Bonano, E.J.; Chu, M.S.Y.; Price, L.L.; Conrad, S.H. [Sandia National Labs., Albuquerque, NM (USA); Dickman, P.T. [Department of Energy, Las Vegas, NV (USA). Nevada Operations Office

1991-02-01T23:59:59.000Z

318

Independent Oversight Review, Savannah River Site Salt Waste Processing Facility- August 2013  

Broader source: Energy.gov [DOE]

Review of the Savannah River Site Salt Waste Processing Facility Safety Basis and Design Development.

319

Independent Oversight Review, Savannah River Site Salt Waste Processing Facility- April 2014  

Broader source: Energy.gov [DOE]

Review of the Savannah River Site Salt Waste Processing Facility Construction Quality and Fire Protection Systems

320

Savannah River Site Salt Waste Processing Facility Technology Readiness Assessment Report  

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

Salt Waste Processing Facility Salt Waste Processing Facility Technology Readiness Assessment Report Kurt D. Gerdes Harry D. Harmon Herbert G. Sutter Major C. Thompson John R. Shultz Sahid C. Smith July 13, 2009 Prepared by the U.S. Department of Energy Washington, D.C. SRS Salt Waste Processing Facility Technology Readiness Assessment July 13, 2009 ii This page intentionally left blank SRS Salt Waste Processing Facility Technology Readiness Assessment July 13, 2009 iii SRS Salt Waste Processing Facility Technology Readiness Assessment July 13, 2009 iii Signatures SRS Salt Waste Processing Facility Technology Readiness Assessment July 13, 2009 iv This page intentionally left blank SRS Salt Waste Processing Facility

Note: This page contains sample records for the topic "transuranic waste processing" from the National Library of EnergyBeta (NLEBeta).
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they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
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321

TECHNOLOGY SUMMARY ADVANCING TANK WASTE RETREIVAL AND PROCESSING  

SciTech Connect (OSTI)

This technology overview provides a high-level summary of technologies being investigated and developed by Washington River Protection Solutions (WRPS) to advance Hanford Site tank waste retrieval and processing. Technology solutions are outlined, along with processes and priorities for selecting and developing them.

SAMS TL

2010-07-07T23:59:59.000Z

322

Savannah River Site - Salt Waste Processing Facility Independent Technical Review  

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

SALT WASTE PROCESSING FACILITY SALT WASTE PROCESSING FACILITY INDEPENDENT TECHNICAL REVIEW November 22, 2006 Conducted by: Harry Harmon, Team Lead Civil/Structural Sub Team Facility Safety Sub Team Engineering Sub Team Peter Lowry, Lead James Langsted, Lead George Krauter, Lead Robert Kennedy Chuck Negin Art Etchells Les Youd Jerry Evatt Oliver Block Loring Wyllie Richard Stark Tim Adams Tom Anderson Todd LaPointe Stephen Gosselin Carl Costantino Norman Moreau Patrick Corcoran John Christian Ken Cooper Kari McDaniel _____________________________ Harry D. Harmon ITR Team Leader SPD-SWPF-217 SPD-SWPF-217: Salt Waste Processing Facility Independent Technical Review 11/22/2006 ACKNOWLEDGEMENT The ITR Team wishes to thank Shari Clifford of Pacific Northwest National Laboratory for

323

Prevention of Food-Processing Wastes  

Science Journals Connector (OSTI)

...beans 99.8 99.8 Corn on the cob 46.0...green beans, and corn on the cob. Tests...starch and glu by new, wet processing of wheat...food exist.) Dry milling and air classification...con-ventional wheat-milling equipment. rom Two...from the conventional wet process and the proposed...

Sam R. Hoover

1974-03-01T23:59:59.000Z

324

Lab sets new record for waste shipments  

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

New record for waste shipments New record for waste shipments Lab sets new record for waste shipments LANL completing its 132nd transuranic (TRU) waste shipment of fiscal year 2010 to the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. August 20, 2010 LANL's shipment of transuranic waste leaves Los Alamos. LANL's shipment of transuranic waste leaves Los Alamos. Contact Fred deSousa Communications Office (505) 500-5672 Email "Removing this waste from Los Alamos is crucial to our plans for overall cleanup." Each shipment moves LANL closer to cleanup LOS ALAMOS, New Mexico, August 20, 2010-Los Alamos National Laboratory set a new LANL record on Friday by completing its 132nd transuranic (TRU) waste shipment of fiscal year 2010 to the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. The shipment eclipsed last year's

325

Field test of the Rapid Transuranic Monitoring Laboratory  

SciTech Connect (OSTI)

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

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

1993-12-01T23:59:59.000Z

326

Waste Heat Management Options: Industrial Process Heating Systems  

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

Heat Management Options Heat Management Options Industrial Process Heating Systems By Dr. Arvind C. Thekdi E-mail: athekdi@e3minc.com E3M, Inc. August 20, 2009 2 Source of Waste Heat in Industries * Steam Generation * Fluid Heating * Calcining * Drying * Heat Treating * Metal Heating * Metal and Non-metal Melting * Smelting, agglomeration etc. * Curing and Forming * Other Heating Waste heat is everywhere! Arvind Thekdi, E3M Inc Arvind Thekdi, E3M Inc 3 Waste Heat Sources from Process Heating Equipment * Hot gases - combustion products - Temperature from 300 deg. F. to 3000 deg.F. * Radiation-Convection heat loss - From temperature source of 500 deg. F. to 2500 deg. F. * Sensible-latent heat in heated product - From temperature 400 deg. F. to 2200 deg. F. * Cooling water or other liquids - Temperature from 100 deg. F. to 180 deg. F.

327

Hanford Tank Waste Information Enclosure 1 Hanford Tank Waste Information  

E-Print Network [OSTI]

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

328

Savannah River Site - Salt Waste Processing Facility: Briefing on the Salt Waste Processing Facility Independent Technical Review  

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

Salt Waste Processing Facility Independent Technical Review Harry Harmon January 9, 2007 2 U.S. Department of Energy Outline * SWPF Process Overview * Major Risks * Approach for Conducting Review * Discussion of Findings * Conclusions 3 U.S. Department of Energy Salt Waste Processing Facility 4 U.S. Department of Energy SWPF Process Overview Alpha Finishing Process CSSX Alpha Strike Process MST/ Sludge Cs Strip Effluent DSS 5 U.S. Department of Energy BOTTOM LINE The SWPF Project is ready to move into final design. 6 U.S. Department of Energy Major Risks * Final geotechnical data potentially could result in redesign of the PC-3 CPA base mat and structure. * Cost and schedule impacts arising from the change from ISO-9001 to NQA-1 quality assurance requirements. * The "de-inventory, flush, and then hands-on

329

Sorbent Testing for the Solidification of Organic Process Waste streams from the Radiochemical Engineering Development Center at Oak Ridge National Laboratory  

SciTech Connect (OSTI)

The U.S. Department of Energy (DOE) has tasked MSE Technology Applications, Inc. (MSE) with evaluating various sorbents to solidify the radioactive liquid organic waste from the Radiochemical Engineering Development Center (REDC) at Oak Ridge National Laboratory (ORNL). REDC recovers and purifies heavy elements (berkelium, californium, einsteinium, and fermium) from irradiated targets for research and industrial applications. Both aqueous and organic waste streams are discharged from REDC. Organic waste is generated from the plutonium/uranium extraction (PUREX), Cleanex, and Pubex processes.1 The PUREX waste derives from an organic-aqueous isotope separation process for plutonium and uranium fission products, the Cleanex waste derives from the removal of fission products and other impurities from the americium/curium product, and the Pubex waste is derived from the separation process of plutonium from dissolved targets. An aqueous waste stream is also produced from these separation processes. MSE has been tasked to test a grouting formula for the aqueous waste stream that includes specially formulated radioactive shielding materials developed by Science and Technology Applications, LLC. This paper will focus on the sorbent testing work. Based on work performed at Savannah River Site (SRS) (Refs. 1, 2), ORNL tested and evaluated three sorbents capable of solidifying the PUREX, Pubex, and Cleanex waste streams and a composite of the three organic waste streams: Imbiber Beads{sup R} IMB230301 (Imbiber Beads), Nochar A610 Petro Bond, and Petroset II Granular{sup TM} (Petroset II-G). Surrogates of the PUREX, Pubex, Cleanex, and a composite organic waste were used for the bench-scale testing. Recommendations resulting from the ORNL testing included follow-on testing by MSE for two of the three sorbents: Nochar Petro Bond and Petroset II-G. MSE recommended that another clay sorbent, Organoclay BM-QT-199, be added to the test sequence. The sorbent/surrogate combinations were tested at bench scale, 19-liter (L) [5-gallon (gal)] bucket scale, and 208-L (55-gal) drum scale. The testing performed by MSE will help ORNL select the right solidification materials and wasteform generation methods for the design of a new treatment facility. The results could also be used to help demonstrate that ORNL could meet the waste acceptance criteria for the ultimate disposal site for the waste-forms. The organics will be solidified as transuranic waste for disposal at the Waste Isolation Pilot Plant, and the aqueous waste stream will be grouted and disposed of at the Nevada Test Site as low-level waste if real waste testing indicates similar results to the surrogate testing. The objective of this work was to identify a sorbent capable of solidifying PUREX, Pubex, and Cleanex organic wastes individually and a composite of the three organic waste streams. The sorbent and surrogate combinations must also be compatible with processing equipment and maintain stability under a variety of conditions that could occur during storage/shipment of the solidified wastes. (authors)

Bickford, J.; Foote, M. [MSE Technology Applications, Inc., Montana (United States); Taylor, P. [Oak Ridge National Laboratory, Oak Ridge, Tennessee (United States)

2008-07-01T23:59:59.000Z

330

Field study of disposed solid wastes from advanced coal processes  

SciTech Connect (OSTI)

Radian Corporation and the North Dakota Energy and Environmental Research Center (EERC) are funded to develop information to be used by private industry and government agencies for managing solid wastes produced by advanced coal combustion processes. This information will be developed by conducting several field studies on disposed wastes from these processes. Data will be collected to characterize these wastes and their interactions with the environments in which they are disposed. Three sites were selected for the field studies: Colorado Ute's fluidized bed combustion (FBC) unit in Nucla, Colorado; Ohio Edison's limestone injection multistage burner (LIMB) retrofit in Lorain, Ohio; and Freeman United's mine site in central Illinois with wastes supplied by the nearby Midwest Grain FBC unit. During the past year, field monitoring and sampling of the four landfill test cases constructed in 1989 and 1991 has continued. Option 1 of the contract was approved last year to add financing for the fifth test case at the Freeman United site. The construction of the Test Case 5 cells is scheduled to begin in November, 1992. Work during this past year has focused on obtaining data on the physical and chemical properties of the landfilled wastes, and on developing a conceptual framework for interpreting this information. Results to date indicate that hydration reactions within the landfilled wastes have had a major impact on the physical and chemical properties of the materials but these reactions largely ceased after the first year, and physical properties have changed little since then. Conditions in Colorado remained dry and no porewater samples were collected. In Ohio, hydration reactions and increases in the moisture content of the waste tied up much of the water initially infiltrating the test cells.

Not Available

1992-01-01T23:59:59.000Z

331

Direction of CRT waste glass processing: Electronics recycling industry communication  

SciTech Connect (OSTI)

Highlights: Black-Right-Pointing-Pointer Given a large flow rate of CRT glass {approx}10% of the panel glass stream will be leaded. Black-Right-Pointing-Pointer The supply of CRT waste glass exceeded demand in 2009. Black-Right-Pointing-Pointer Recyclers should use UV-light to detect lead oxide during the separation process. Black-Right-Pointing-Pointer Recycling market analysis techniques and results are given for CRT glass. Black-Right-Pointing-Pointer Academic initiatives and the necessary expansion of novel product markets are discussed. - Abstract: Cathode Ray Tube, CRT, waste glass recycling has plagued glass manufacturers, electronics recyclers and electronics waste policy makers for decades because the total supply of waste glass exceeds demand, and the formulations of CRT glass are ill suited for most reuse options. The solutions are to separate the undesirable components (e.g. lead oxide) in the waste and create demand for new products. Achieving this is no simple feat, however, as there are many obstacles: limited knowledge of waste glass composition; limited automation in the recycling process; transportation of recycled material; and a weak and underdeveloped market. Thus one of the main goals of this paper is to advise electronic glass recyclers on how to best manage a diverse supply of glass waste and successfully market to end users. Further, this paper offers future directions for academic and industry research. To develop the recommendations offered here, a combination of approaches were used: (1) a thorough study of historic trends in CRT glass chemistry; (2) bulk glass collection and analysis of cullet from a large-scale glass recycler; (3) conversations with industry members and a review of potential applications; and (4) evaluation of the economic viability of specific uses for recycled CRT glass. If academia and industry can solve these problems (for example by creating a database of composition organized by manufacturer and glass source) then the reuse of CRT glass can be increased.

Mueller, Julia R., E-mail: mueller.143@osu.edu [Ohio State University, William G. Lowrie Department of Chemical and Biomolecular Engineering, OH (United States) and University of Queensland, School of Chemical Engineering (Australia) and Ohio State University, Materials Science and Engineering, OH (United States); Boehm, Michael W. [University of Queensland, School of Chemical Engineering (Australia); Drummond, Charles [Ohio State University, Materials Science and Engineering, OH (United States)

2012-08-15T23:59:59.000Z

332

Prevention of Food-Processing Wastes  

Science Journals Connector (OSTI)

...continuously. Minor amounts of water lost by evaporation...re-placed. Because the water recycled from the resin...soapstock, and the water evap-orated in drying...the United States. Electrodialysis has been in com-mercial...processes constitute a treatment problem. Liquid whey...

Sam R. Hoover

1974-03-01T23:59:59.000Z

333

Waste Energy Analysis Recovery for a Typical Food Processing Plant  

E-Print Network [OSTI]

An energy analysis made for the Joan of Arc Food Processing Plant in St. Francisville, Louisiana indicated that a significant quantity of waste heat energy was being released to the atmosphere in the forms of low quality steam and hot flue gases...

Miller, P. H.; Mann, L., Jr.

1980-01-01T23:59:59.000Z

334

Waste Heat Recovery from Refrigeration in a Meat Processing Facility  

E-Print Network [OSTI]

A case study is reviewed on a heat recovery system installed in a meat processing facility to preheat water for the plant hot water supply. The system utilizes waste superheat from the facility's 1,350-ton ammonia refrigeration system. The heat...

Murphy, W. T.; Woods, B. E.; Gerdes, J. E.

1980-01-01T23:59:59.000Z

335

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

SciTech Connect (OSTI)

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

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

1998-03-01T23:59:59.000Z

336

Study on a regeneration process of LiCl-KCl eutectic based waste salt generated from the pyrochemical process  

SciTech Connect (OSTI)

A regeneration process of LiCl-KCl eutectic waste salt generated from the pyrochemical process of spent nuclear fuel has been studied. This regeneration process is composed of a chemical conversion process and a vacuum distillation process. Through the regeneration process, a high efficiency of renewable salt recovery can be obtained from the waste salt and rare earth nuclides in the waste salt can be separated as oxide or phosphate forms. Thus, the regeneration process can contribute greatly to a reduction of the waste volume and a creation of durable final waste forms. (authors)

Eun, H.C.; Cho, Y.Z.; Choi, J.H.; Kim, J.H.; Lee, T.K.; Park, H.S.; Kim, I.T.; Park, G.I. [Nuclear Fuel Cycle Waste Treatment Research Division, Korea Atomic Energy Research Institute, 989-111 Daedeok-Daero, Yuseong-Gu, Daejeon 3054-353 (Korea, Republic of)

2013-07-01T23:59:59.000Z

337

Process for recovery of palladium from nuclear fuel reprocessing wastes  

DOE Patents [OSTI]

Palladium is selectively removed from spent nuclear fuel reprocessing waste by adding sugar to a strong nitric acid solution of the waste to partially denitrate the solution and cause formation of an insoluble palladium compound. The process includes the steps of: (a) adjusting the nitric acid content of the starting solution to about 10 M; (b) adding 50% sucrose solution in an amount sufficient to effect the precipitation of the palladium compound; (c) heating the solution at reflux temperature until precipitation is complete; and (d) centrifuging the solution to separate the precipitated palladium compound from the supernatant liquid.

Campbell, D.O.; Buxton, S.R.

1980-06-16T23:59:59.000Z

338

Design of electrochemical processes for treatment of unusual waste streams  

SciTech Connect (OSTI)

UCRL- JC- 129438 PREPRINT This document was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor the University of California nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or the University of California. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or the University of California, and shall not be used for advertising or product endorsement purposes. Introduction. An overview of work done on the development of three electrochemical processes that meet the specific needs of low- level waste treatment is presented. These technologies include: mediated electrochemical oxidation [I- 4]; bipolar membrane electrodialysis [5]; and electrosorption of carbon aerogel electrodes [6- 9]. Design strategies are presented to assess the suitability of these electrochemical processes for Mediated electrochemical oxidation. Mixed wastes include both hazardous and radioactive components. It is desirable to reduce the overall volume of the waste before immobilization and disposal in repositories. While incineration is an attractive technique for the destruction of organic fractions of mixed wastes, such high-temperature thermal processes pose the threat of volatilizing various radionuclides. By destroying organics in the aqueous phase at low temperature and ambient pressure, the risk of volatilization can be reduced. One approach that is attractive is the use of eiectrochemically generated mediators such as Ag( ll), Co( Ill) and Fe( III). These oxidants react with organicsin Bipolar membrane electrodialysis. in the aqueous processing of nuclear materials, process steps arise that require the neutralization of an acidic stream with a strong base. Ultimately, these neutralized salt solutions become aqueous waste streams, requiring further treatment and disposal. By "splitting" such neutralized salt solutions into their acid and base components, the generation of aqueous mixed waste can be greatly reduced. At LLNL, a bipolar membrane electrodialysis cell has been used to separate neutral solutions of NaCl, NaNO1 and Na, SO, into product streams of NaOH, HCI, HNOj and H2S0,, which could be recycled. The eftlciency of this particular process will be discussed, as well as practical limitations of the technology. Basic principles of engineering design of such systems will be reviewed.

Farmer, J.C.

1998-01-01T23:59:59.000Z

339

Efficient separations & processing crosscutting program  

SciTech Connect (OSTI)

The Efficient Separations and Processing Crosscutting Program (ESP) was created in 1991 to identify, develop, and perfect chemical and physical separations technologies and chemical processes which treat wastes and address environmental problems throughout the DOE complex. The ESP funds several multiyear tasks that address high-priority waste remediation problems involving high-level, low-level, transuranic, hazardous, and mixed (radioactive and hazardous) wastes. The ESP supports applied research and development (R & D) leading to the demonstration or use of these separations technologies by other organizations within the Department of Energy (DOE), Office of Environmental Management.

NONE

1996-08-01T23:59:59.000Z

340

Processing of solid mixed waste containing radioactive and hazardous materials  

DOE Patents [OSTI]

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

Gotovchikov, V.T.; Ivanov, A.V.; Filippov, E.A.

1998-05-12T23:59:59.000Z

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


341

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

SciTech Connect (OSTI)

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

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

2003-02-25T23:59:59.000Z

342

Process for the recovery of curium-244 from nuclear waste  

SciTech Connect (OSTI)

A process has been designed for the recovery of curium from purex waste. Curium and americium are separated from the lanthanides by a TALSPEAK extraction process using differential extraction. Equations were derived for the estimation of the economically optimum conditions for the extraction using laboratory batch extraction data. The preparation of feed for the extraction involves the removal of nitric acid from the Purex waste by vaporization under reduced pressure, the leaching of soluble nitrates from the resulting cake, and the oxalate precipitation of a pure lanthanide-actinide fraction. Final separation of the curium from americium is done by ion-exchange. The steps of the process, except ion-exchange, were tested on a laboratory scale and workable conditions were determined.

Posey, J.C.

1980-10-01T23:59:59.000Z

343

Idaho's Advanced Mixed Waste Treatment Project Details 2013  

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

Idaho's Advanced Mixed Waste Treatment Project Details 2013 Idaho's Advanced Mixed Waste Treatment Project Details 2013 Accomplishments Idaho's Advanced Mixed Waste Treatment Project Details 2013 Accomplishments December 24, 2013 - 12:00pm Addthis IDAHO FALLS, Idaho - EM and its contractor, Idaho Treatment Group (ITG), safely and compliantly met all of their production and shipping targets in the Advanced Mixed Waste Treatment Project (AMWTP) at the Idaho site in 2013. AMWTP's purpose is to safely process and dispose of transuranic (TRU) and mixed low-level waste (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 largest shipper of contact-handled TRU waste to WIPP. In 2013, AMWTP sent 2,444.69 cubic

344

Idaho's Advanced Mixed Waste Treatment Project Details 2013  

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

Idaho's Advanced Mixed Waste Treatment Project Details 2013 Idaho's Advanced Mixed Waste Treatment Project Details 2013 Accomplishments Idaho's Advanced Mixed Waste Treatment Project Details 2013 Accomplishments December 24, 2013 - 12:00pm Addthis IDAHO FALLS, Idaho - EM and its contractor, Idaho Treatment Group (ITG), safely and compliantly met all of their production and shipping targets in the Advanced Mixed Waste Treatment Project (AMWTP) at the Idaho site in 2013. AMWTP's purpose is to safely process and dispose of transuranic (TRU) and mixed low-level waste (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 largest shipper of contact-handled TRU waste to WIPP. In 2013, AMWTP sent 2,444.69 cubic

345

Office of Environmental Management Taps Small Business for Waste...  

Energy Savers [EERE]

team. As Celeritex, the joint venture will be providing support services for the Mobile Loading Unit, loading Transuranic waste containers into packaging that's been approved...

346

Summary - SRS Salt Waste Processing Facility  

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

SRS Co SRS Co DOE S Proces concen actinid in a se remov adjustm sorben sorben solutio passed separa stream extract sufficie separa (with S vitrifica (DWP Sr/acti federa assure and ha Critica The te (CTE) descrip Readin The Ele Site: S roject: S F Report Date: J ited States Why DOE omposite High Lev Savannah Rive ssing Facility (S ntrate targeted des) from High eries of unit ope ved by contactin ment) with a m nt in a batch m nt (containing S on by cross flow d to a solvent e ated to an aque m. The bulk so tion process, w ently low levels ated high activi Sr and actinide ation in the Def F). Provisions inides adsorpti al project direct e that the plann ave been matu al Decision-3 ap What th eam identified e of the SWPF w ption. All CTE ness Level of 6 To view the full T http://www.em.doe. objective of a Tech ements (CTEs), usin

347

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...

348

WASTE DISPOSITION PROJECT MAKES GREAT STRIDES AT THE IDAHO SITE |  

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

WASTE DISPOSITION PROJECT MAKES GREAT STRIDES AT THE IDAHO SITE 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 the Snake River Plain Aquifer and keeping the Office of Environmental Management's commitment to environmental clean up. In 2007, the first shipment of RH TRU waste left the gates of the Idaho Site, headed to the Waste Isolation Pilot Plant (WIPP) for disposal. In the three years since, devoted individuals on the CH2M-WG, Idaho's (CWI)

349

WASTE DISPOSITION PROJECT MAKES GREAT STRIDES AT THE IDAHO SITE |  

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

WASTE DISPOSITION PROJECT MAKES GREAT STRIDES AT THE IDAHO SITE 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 the Snake River Plain Aquifer and keeping the Office of Environmental Management's commitment to environmental clean up. In 2007, the first shipment of RH TRU waste left the gates of the Idaho Site, headed to the Waste Isolation Pilot Plant (WIPP) for disposal. In the three years since, devoted individuals on the CH2M-WG, Idaho's (CWI)

350

Step-By-Step Guide for Waste Handling at WIPP - Fact Sheet  

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

the nation's nuclear waste disposal problem Step-By-Step Guide for Waste Handling at WIPP The handling and disposal of contact-handled transuranic waste at the Waste Isolation...

351

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

SciTech Connect (OSTI)

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

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

1998-06-01T23:59:59.000Z

352

Pioneering Nuclear Waste Disposal  

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

2 2 3 T he journey to the WIPP began nearly 60 years before the first barrels of transuranic waste arrived at the repository. The United States produced the world's first sig- nificant quantities of transuranic material during the Manhattan Project of World War II in the early 1940s. The government idled its plutonium- producing reactors and warhead manu- facturing plants at the end of the Cold War and scheduled most of them for dismantlement. However, the DOE will generate more transuranic waste as it cleans up these former nuclear weapons facilities. The WIPP is a cor- nerstone of the effort to clean up these facilities by providing a safe repository to isolate transuranic waste in disposal rooms mined out of ancient salt beds, located 2,150 feet below ground. The need for the WIPP

353

Process modeling of hydrogen production from municipal solid waste  

SciTech Connect (OSTI)

The ASPEN PLUS commercial simulation software has been used to develop a process model for a conceptual process to convert municipal solid waste (MSW) to hydrogen. The process consists of hydrothermal treatment of the MSW in water to create a slurry suitable as feedstock for an oxygen blown Texaco gasifier. A method of reducing the complicated MSW feed material to a manageable set of components is outlined along with a framework for modeling the stoichiometric changes associated with the hydrothermal treatment process. Model results indicate that 0.672 kmol/s of hydrogen can be produced from the processing of 30 kg/s (2600 tonne/day) of raw MSW. A number of variations on the basic processing parameters are explored and indicate that there is a clear incentive to reduce the inert fraction in the processed slurry feed and that cofeeding a low value heavy oil may be economically attractive.

Thorsness, C.B.

1995-01-01T23:59:59.000Z

354

LANL reaches waste shipment milestone  

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

LANL reaches waste shipment milestone LANL reaches waste shipment milestone LANL reaches waste shipment milestone The Lab surpassed 100,000 plutonium-equivalent curies of TRU waste shipped to WIPP, about one-third of the Lab's total. May 31, 2011 A shipment of transuranic waste on its way to the WIPP repository A shipment of transuranic waste on its way to the WIPP repository. Contact Fred deSousa Communicatons Office (505) 665-3430 Email LOS ALAMOS, New Mexico, May 31, 2011 - Los Alamos National Laboratory has reached an important milestone in its campaign to ship transuranic (TRU) waste from Cold War-era nuclear operations to the U.S. Department of Energy's Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. This month, the Lab surpassed 100,000 plutonium-equivalent curies of TRU waste shipped to WIPP, about one-third of the Lab's total.

355

Defense Waste Processing Facility (DWPF), Modular CSSX Unit (CSSX), and Waste Transfer Line System of Salt Processing Program (U)  

SciTech Connect (OSTI)

All of the waste streams from ARP, MCU, and SWPF processes will be sent to DWPF for vitrification. The impact these new waste streams will have on DWPF's ability to meet its canister production goal and its ability to support the Salt Processing Program (ARP, MCU, and SWPF) throughput needed to be evaluated. DWPF Engineering and Operations requested OBU Systems Engineering to evaluate DWPF operations and determine how the process could be optimized. The ultimate goal will be to evaluate all of the Liquid Radioactive Waste (LRW) System by developing process modules to cover all facilities/projects which are relevant to the LRW Program and to link the modules together to: (1) study the interfaces issues, (2) identify bottlenecks, and (3) determine the most cost effective way to eliminate them. The results from the evaluation can be used to assist DWPF in identifying improvement opportunities, to assist CBU in LRW strategic planning/tank space management, and to determine the project completion date for the Salt Processing Program.

CHANG, ROBERT

2006-02-02T23:59:59.000Z

356

THE USE OF POLYMERS IN RADIOACTIVE WASTE PROCESSING SYSTEMS  

SciTech Connect (OSTI)

The Savannah River Site (SRS), one of the largest U.S. Department of Energy (DOE) sites, has operated since the early 1950s. The early mission of the site was to produce critical nuclear materials for national defense. Many facilities have been constructed at the SRS over the years to process, stabilize and/or store radioactive waste and related materials. The primary materials of construction used in such facilities are inorganic (metals, concrete), but polymeric materials are inevitably used in various applications. The effects of aging, radiation, chemicals, heat and other environmental variables must therefore be understood to maximize service life of polymeric components. In particular, the potential for dose rate effects and synergistic effects on polymeric materials in multivariable environments can complicate compatibility reviews and life predictions. The selection and performance of polymeric materials in radioactive waste processing systems at the SRS are discussed.

Skidmore, E.; Fondeur, F.

2013-04-15T23:59:59.000Z

357

The U. S. Department of Energy (DOE) has submitted a planned change request to use shielded containers for emplacement of selected remote-handled (RH) transuranic  

E-Print Network [OSTI]

that the use of shielded canisters for these waste streams has an insignificant impact on long-term performance the disruptions from in-the-wall emplacement of RH TRU waste canisters while providing additional storage shielded containers for emplacement of selected remote-handled (RH) transuranic (TRU) waste streams

358

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

SciTech Connect (OSTI)

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

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

1998-04-01T23:59:59.000Z

359

Basic TRUEX process for Rocky Flats Plant  

SciTech Connect (OSTI)

The Generic TRUEX Model was used to develop a TRUEX process flowsheet for recovering the transuranics (Pu, Am) from a nitrate waste stream at Rocky Flats Plant. The process was designed so that it is relatively insensitive to changes in process feed concentrations and flow rates. Related issues are considered, including solvent losses, feed analysis requirements, safety, and interaction with an evaporator system for nitric acid recycle.

Leonard, R.A.; Chamberlain, D.B.; Dow, J.A.; Farley, S.E.; Nunez, L.; Regalbuto, M.C.; Vandegrift, G.F.

1994-08-01T23:59:59.000Z

360

Multi-discipline Waste Acceptance Process at the Nevada National Security Site - 13573  

SciTech Connect (OSTI)

The Nevada National Security Site low-level radioactive waste disposal facility acceptance process requires multiple disciplines to ensure the protection of workers, the public, and the environment. These disciplines, which include waste acceptance, nuclear criticality, safety, permitting, operations, and performance assessment, combine into the overall waste acceptance process to assess low-level radioactive waste streams for disposal at the Area 5 Radioactive Waste Management Site. Four waste streams recently highlighted the integration of these disciplines: the Oak Ridge Radioisotope Thermoelectric Generators and Consolidated Edison Uranium Solidification Project material, West Valley Melter, and classified waste. (authors)

Carilli, Jhon T. [US Department Of Energy, Nevada Site Office, P. O. Box 98518, Las Vegas, Nevada 89193-8518 (United States)] [US Department Of Energy, Nevada Site Office, P. O. Box 98518, Las Vegas, Nevada 89193-8518 (United States); Krenzien, Susan K. [Navarro-Intera, LLC, P. O. Box 98952, Las Vegas, Nevada 89193-8952 (United States)] [Navarro-Intera, LLC, P. O. Box 98952, Las Vegas, Nevada 89193-8952 (United States)

2013-07-01T23:59:59.000Z

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


361

GRR/Section 18-ID-b - Hazardous Waste Permit Process | Open Energy  

Open Energy Info (EERE)

GRR/Section 18-ID-b - Hazardous Waste Permit Process GRR/Section 18-ID-b - Hazardous Waste Permit Process < GRR Jump to: navigation, search GRR-logo.png GEOTHERMAL REGULATORY ROADMAP Roadmap Home Roadmap Help List of Sections Section 18-ID-b - Hazardous Waste Permit Process 18IDBHazardousWastePermitProcess.pdf Click to View Fullscreen Contact Agencies Idaho Department of Environmental Quality Regulations & Policies Idaho Hazardous Waste Management Act IDAPA 58.01.05 Rules and Standards for Hazardous Waste 40 CFR 124.31 Pre-application public meeting and notice 40 CRF 124.10 Public notice of permit actions and public comment period 40 CFR 124.12 Public hearings 40 CFR 270.13 Contents of Part A of the permit application Triggers None specified Click "Edit With Form" above to add content 18IDBHazardousWastePermitProcess.pdf 18IDBHazardousWastePermitProcess.pdf

362

GRR/Section 18-CO-b - Hazardous Waste Permit Process | Open Energy  

Open Energy Info (EERE)

GRR/Section 18-CO-b - Hazardous Waste Permit Process GRR/Section 18-CO-b - Hazardous Waste Permit Process < GRR Jump to: navigation, search GRR-logo.png GEOTHERMAL REGULATORY ROADMAP Roadmap Home Roadmap Help List of Sections Section 18-CO-b - Hazardous Waste Permit Process 18COBHazardousWastePermitProcess.pdf Click to View Fullscreen Contact Agencies Colorado Department of Public Health and Environment Regulations & Policies Colorado Hazardous Waste Regulations Part 260 Triggers None specified Click "Edit With Form" above to add content 18COBHazardousWastePermitProcess.pdf 18COBHazardousWastePermitProcess.pdf Error creating thumbnail: Page number not in range. Error creating thumbnail: Page number not in range. Flowchart Narrative Hazardous waste is a regulated substance and facilities that treat, store

363

Characterization of the MVST waste tanks located at ORNL  

SciTech Connect (OSTI)

During the fall of 1996 there was a major effort to sample and analyze the Active Liquid Low-Level Waste (LLLW) tanks at ORNL which include the Melton Valley Storage Tanks (MVST) and the Bethel Valley Evaporator Service Tanks (BVEST). The characterization data summarized in this report was needed to address waste processing options, address concerns of the performance assessment (PA) data for the Waste Isolation Pilot Plant (WIPP), evaluate the 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 only discusses the analytical characterization data for the MVST waste tanks. The isotopic data presented in this report support the position that fissile isotopes of uranium and plutonium were ``denatured`` as required by administrative controls. In general, MVST sludge was found to be both hazardous by RCRA characteristics and the transuranic alpha activity was well about the limit for TRU waste. The characteristics of the MVST 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 requirements for disposal of the waste in WIPP.

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

1996-12-01T23:59:59.000Z

364

Waste-heat recovery in batch processes using heat storage  

SciTech Connect (OSTI)

The waste-heat recovery in batch processes has been studied using the pinch-point method. The aim of the work has been to investigate theoretical and practical approaches to the design of heat-exchanger networks, including heat storage, for waste-heat recovery in batch processes. The study is limited to the incorporation of energy-storage systems based on fixed-temperature variable-mass stores. The background for preferring this to the alternatives (variable-temperature fixed-mass and constant-mass constant-temperature (latent-heat) stores) is given. It is shown that the maximum energy-saving targets as calculated by the pinch-point method (time average model, TAM) can be achieved by locating energy stores at either end of each process stream. This theoretically large number of heat-storage tanks (twice the number of process streams) can be reduced to just a few tanks. A simple procedure for determining a number of heat-storage tanks sufficient to achieve the maximum energy-saving targets as calculated by the pinch-point method is described. This procedure relies on combinatorial considerations, and could therefore be labeled the combinatorial method for incorporation of heat storage in heat-exchanger networks. Qualitative arguments justifying the procedure are presented. For simple systems, waste-heat recovery systems with only three heat-storage temperatures (a hot storage, a cold storage, and a heat store at the pinch temperature) often can achieve the maximum energy-saving targets. Through case studies, six of which are presented, it is found that a theoretically large number of heat-storage tanks (twice the number of process streams) can be reduced to just a few tanks. The description of these six cases is intended to be sufficiently detailed to serve as benchmark cases for development of alternative methods.

Stoltze, S.; Mikkelsen, J.; Lorentzen, B.; Petersen, P.M.; Qvale, B. [Technical Univ. of Denmark, Lyngby (Denmark). Lab. for Energetics

1995-06-01T23:59:59.000Z

365

Radioactive Waste Management Manual  

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

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

1999-07-09T23:59:59.000Z

366

Sodium-Bearing Waste Treatment Alternatives Implementation Study  

SciTech Connect (OSTI)

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

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

2004-07-01T23:59:59.000Z

367

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

SciTech Connect (OSTI)

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

COZZI, ALEX

2004-02-18T23:59:59.000Z

368

DOCKET NO: A-93-02 (CERTIFICATION RULEMAKING) 40 CFR 191 COMPLIANCE DETERMINATION FOR THE WASTE ISOLATION  

E-Print Network [OSTI]

/4/96 DOE Rpt, DOE/CAO-95-1121: Transuranic Waste Baseline Inventory Report (Revision 2) 12/95 II-A-21 6/1/96 DOE Study -- DOE/CAO-95-3102, Radioactive Waste Processing And Volume Reduction Technology Study 10" a Report Relevant to Actinide Solubility Studies at the WIPP Site 6/12/95 II-A-19 4/30/96 DOE Report, DOE/CAO

369

Reevaluation of Vitrified High-Level Waste Form Criteria for Potential Cost Savings at the Defense Waste Processing Facility - 13598  

SciTech Connect (OSTI)

At the Savannah River Site (SRS) the Defense Waste Processing Facility (DWPF) has been immobilizing SRS's radioactive high level waste (HLW) sludge into a durable borosilicate glass since 1996. Currently the DWPF has poured over 3,500 canisters, all of which are compliant with the U. S. Department of Energy's (DOE) Waste Acceptance Product Specifications for Vitrified High-Level Waste Forms (WAPS) and therefore ready to be shipped to a federal geologic repository for permanent disposal. Due to DOE petitioning to withdraw the Yucca Mountain License Application (LA) from the Nuclear Regulatory Commission (NRC) in 2010 and thus no clear disposal path for SRS canistered waste forms, there are opportunities for cost savings with future canister production at DWPF and other DOE producer sites by reevaluating high-level waste form requirements and compliance strategies and reducing/eliminating those that will not negatively impact the quality of the canistered waste form. (authors)

Ray, J.W. [Savannah River Remediation (United States)] [Savannah River Remediation (United States); Marra, S.L.; Herman, C.C. [Savannah River National Laboratory, Savannah River Site, Aiken, SC 29808 (United States)] [Savannah River National Laboratory, Savannah River Site, Aiken, SC 29808 (United States)

2013-07-01T23:59:59.000Z

370

Reevaluation Of Vitrified High-Level Waste Form Criteria For Potential Cost Savings At The Defense Waste Processing Facility  

SciTech Connect (OSTI)

At the Savannah River Site (SRS) the Defense Waste Processing Facility (DWPF) has been immobilizing SRS's radioactive high level waste (HLW) sludge into a durable borosilicate glass since 1996. Currently the DWPF has poured over 3,500 canisters, all of which are compliant with the U. S. Department of Energy's (DOE) Waste Acceptance Product Specifications for Vitrified High-Level Waste Forms (WAPS) and therefore ready to be shipped to a federal geologic repository for permanent disposal. Due to DOE petitioning to withdraw the Yucca Mountain License Application (LA) from the Nuclear Regulatory Commission (NRC) in 2010 and thus no clear disposal path for SRS canistered waste forms, there are opportunities for cost savings with future canister production at DWPF and other DOE producer sites by reevaluating high-level waste form requirements and compliance strategies and reducing/eliminating those that will not negatively impact the quality of the canistered waste form.

Ray, J. W.; Marra, S. L.; Herman, C. C.

2013-01-09T23:59:59.000Z

371

Waste inspection tomography (WIT)  

SciTech Connect (OSTI)

The WIT program will provide an inspection system that offers the nuclear waste evaluator a unique combination of tools for regulatory-driven characterization of low-level waste (LLW), transuranic waste (TRU), and mixed waste drums. WIT provides nondestructive, noninvasive, and environmentally safe inspections using X-ray and gamma ray technologies, with reasonable cost and throughput. Two emission imaging techniques will be employed for characterizing materials in waste containers. The first of these is gamma emission tomography, commonly called single-photon emission computed tomography (SPECT). Rather than using an external radiation source, SPECT uses the emission of radioactive materials within the object of interest for imaging. In this case, emission from actual nuclear waste within a container will provide a three-dimensional image of the radioactive substances in the container. The second emission technique will use high-purity germanium detectors for gamma ray spectroscopy. This technique, called nondestructive assay (NDA), can identify the emitting isotopic species and strength. Work in emission tomography and assay of nuclear waste has been undertaken at Lawrence Livermore National Laboratory using a technique called Passive Tomography. Results from a process development unit are presented.

Bernardi, R.T.; Han, K.S.

1994-12-31T23:59:59.000Z

372

Overview of Fiscal Year 2002 Research and Development for Savannah River Site's Salt Waste Processing Facility  

SciTech Connect (OSTI)

The Department of Energy's (DOE) Savannah River Site (SRS) high-level waste program is responsible for storage, treatment, and immobilization of high-level waste for disposal. The Salt Processing Program (SPP) is the salt (soluble) waste treatment portion of the SRS high-level waste effort. The overall SPP encompasses the selection, design, construction and operation of treatment technologies to prepare the salt waste feed material for the site's grout facility (Saltstone) and vitrification facility (Defense Waste Processing Facility). Major constituents that must be removed from the salt waste and sent as feed to Defense Waste Processing Facility include actinides, strontium, cesium, and entrained sludge. In fiscal year 2002 (FY02), research and development (R&D) on the actinide and strontium removal and Caustic-Side Solvent Extraction (CSSX) processes transitioned from technology development for baseline process selection to providing input for conceptual design of the Salt Waste Processing Facility. The SPP R&D focused on advancing the technical maturity, risk reduction, engineering development, and design support for DOE's engineering, procurement, and construction (EPC) contractors for the Salt Waste Processing Facility. Thus, R&D in FY02 addressed the areas of actual waste performance, process chemistry, engineering tests of equipment, and chemical and physical properties relevant to safety. All of the testing, studies, and reports were summarized and provided to the DOE to support the Salt Waste Processing Facility, which began conceptual design in September 2002.

H. D. Harmon, R. Leugemors, PNNL; S. Fink, M. Thompson, D. Walker, WSRC; P. Suggs, W. D. Clark, Jr

2003-02-26T23:59:59.000Z

373

GRR/Section 18-UT-b - Hazardous Waste Permit Process | Open Energy  

Open Energy Info (EERE)

UT-b - Hazardous Waste Permit Process UT-b - Hazardous Waste Permit Process < GRR Jump to: navigation, search GRR-logo.png GEOTHERMAL REGULATORY ROADMAP Roadmap Home Roadmap Help List of Sections Section 18-UT-b - Hazardous Waste Permit Process 18UTBHazardousWastePermitProcess (1).pdf Click to View Fullscreen Contact Agencies Utah Department of Environmental Quality Regulations & Policies Hazardous Waste Rules R315-1 et seq Triggers None specified Click "Edit With Form" above to add content 18UTBHazardousWastePermitProcess (1).pdf Error creating thumbnail: Page number not in range. Error creating thumbnail: Page number not in range. Error creating thumbnail: Page number not in range. Flowchart Narrative A hazardous waste is specifically listed by the Utah Solid and Hazardous Waste Rules or exhibits a characteristic such as ignitability, corrosivity,

374

Summary - Salt Waste Processing Facility Design at the Savannah River Site  

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

Salt Waste Processing Facility Salt Waste Processing Facility ETR Report Date: November 2006 ETR-4 United States Department of Energy Office of Environmental Management (DOE-EM) External Technical Review of the Salt Waste Processing Facility Design at the Savannah River Site (SRS) Why DOE-EM Did This Review The Salt Waste Processing Facility (SWPF) is intended to remove and concentrate the radioactive strontium (Sr), actinides, and cesium (Cs) from the bulk salt waste solutions in the SRS high-level waste tanks. The sludge and strip effluent from the SWPF that contain concentrated Sr, actinide, and Cs wastes will be sent to the SRS Defense Waste Processing Facility (DWPF), where they will be vitrified. The decontaminated salt solution (DSS) that is left after removal of the highly

375

DEVELOPMENT AND DEMONSTRATION OF POLYMER MICROENCAPSULATION OF MIXED WASTE USING KINETIC MIXER PROCESSING  

SciTech Connect (OSTI)

Thermokinetic mixing was investigated as an alternative processing method for polyethylene microencapsulation, a technology well demonstrated for treatment of hazardous, low-level radioactive and low-level mixed wastes. Polyethylene encapsulation by extrusion has been previously shown to be applicable to a wide range of waste types but often pretreatment of the wastes is necessary due to process limitations regarding the maximum waste moisture content and particle size distribution. Development testing was conducted with kinetic mixing in order to demonstrate technology viability and show improved process applicability in these areas. Testing to establish process capabilities and relevant operating parameters was performed with waste surrogates including an aqueous evaporator concentrate and soil. Using a pilot-scale kinetic mixer which was installed and modified for this program, the maximum waste moisture content and particle size was determined. Following process development with surrogate wastes, the technology was successfully demonstrated at BNL using actual mixed waste.

LAGERAAEN,P.R.; KALB,P.D.; MILIAN,L.W.; ADAMS,J.W.

1997-11-01T23:59:59.000Z

376

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 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 Plant in southeastern New Mexico. Contact Fred deSousa Communications Office (505) 665-3430 Email "We've made significant progress removing waste stored above ground at Area G, and we made this progress while maintaining an excellent safety record," said Jeff Mousseau, associate director of Environmental Programs

377

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 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 Plant in southeastern New Mexico. Contact Fred deSousa Communications Office (505) 665-3430 Email "We've made significant progress removing waste stored above ground at Area G, and we made this progress while maintaining an excellent safety record," said Jeff Mousseau, associate director of Environmental Programs

378

1993 Solid Waste Reference Forecast Summary  

SciTech Connect (OSTI)

This report, which updates WHC-EP-0567, 1992 Solid Waste Reference Forecast Summary, (WHC 1992) forecasts the volumes of solid wastes to be generated or received at the US Department of Energy Hanford Site during the 30-year period from FY 1993 through FY 2022. The data used in this document were collected from Westinghouse Hanford Company forecasts as well as from surveys of waste generators at other US Department of Energy sites who are now shipping or plan to ship solid wastes to the Hanford Site for disposal. These wastes include low-level and low-level mixed waste, transuranic and transuranic mixed waste, and nonradioactive hazardous waste.

Valero, O.J.; Blackburn, C.L. [Westinghouse Hanford Co., Richland, WA (United States); Kaae, P.S.; Armacost, L.L.; Garrett, S.M.K. [Pacific Northwest Lab., Richland, WA (United States)

1993-08-01T23:59:59.000Z

379

Process for treating waste water having low concentrations of metallic contaminants  

DOE Patents [OSTI]

A process for treating waste water having a low level of metallic contaminants by reducing the toxicity level of metallic contaminants to an acceptable level and subsequently discharging the treated waste water into the environment without removing the treated contaminants.

Looney, Brian B; Millings, Margaret R; Nichols, Ralph L; Payne, William L

2014-12-16T23:59:59.000Z

380

Waste reduction assistance program (WRAP) on-site consultation audit report: Seafood processing plant  

SciTech Connect (OSTI)

The waste audit study was conducted at a seafood processing plant in Alaska. The report discusses process descriptions, waste types and quantities, current waste and materials management practices, and waste reduction alternatives. The company's current practices include use of fish waste, burning of used oil and solvents, and water conservation. Additional opportunities include microfiltration of solvents and oils, recycling of used batteries, inventory control and formation of a waste reduction team. Appendices include a summary of state regulations, a fact sheet on used oil, and a list of vendors and services.

Not Available

1989-07-29T23:59:59.000Z

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


381

Method for co-processing waste rubber and carbonaceous material  

SciTech Connect (OSTI)

In a process for the co-processing of waste rubber and carbonaceous material to form a useful liquid product, the rubber and the carbonaceous material are combined and heated to the depolymerization temperature of the rubber in the presence of a source of hydrogen. The deploymerized rubber acts as a liquefying solvent for the carbonaceous material while a beneficial catalytic effect is obtained from the carbon black released on deploymerization the reinforced rubber. The reaction is carried out at liquefaction conditions of 380--600{degrees}C and 70--280 atmospheres hydrogen pressure. The resulting liquid is separated from residual solids and further processed such as by distillation or solvent extraction to provide a carbonaceous liquid useful for fuels and other purposes.

Farcasiu, M.; Smith, C.M.

1990-10-09T23:59:59.000Z

382

Co-processing of agriculture and biomass waste with coal  

SciTech Connect (OSTI)

Biomass and bio-processed waste are potential candidates for co-liquefaction with coal. Specific materials used here include sawdust and poultry manure. Liquefaction experiments were run on each of these materials, separately and with coal, using tetralin as solvent at 350{degrees}C and 1000 psi(cold) hydrogen pressure for 1h. Total conversion was monitored, as well as conversion to asphaltenes, oils and gases. All the biomass samples are converted to oils and gases under the reaction conditions. Poultry manure seems to convert coal more completely, and to produce more oils and gases, than conventional liquefaction.

Stiller, A.H.; Dadyburjor, D.B.; Wann, J.P. [West Virginia Univ., Morgantown, WV (United States)

1995-12-01T23:59:59.000Z

383

Device Assembly Facility (DAF) Glovebox Radioactive Waste Characterization  

SciTech Connect (OSTI)

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

Dominick, J L

2001-12-18T23:59:59.000Z

384

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

SciTech Connect (OSTI)

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)

D'Amico, E. L [Washington TRU Solutions (United States); Edmiston, D. R. [John Hart and Associates (United States); O'Leary, G. A. [CH2M-WG Idaho, LLC (United States); Rivera, M. A. [Aspen Resources Ltd., Inc. (United States); Steward, D. M. [Boulder Research Enterprises, LLC (United States)

2006-07-01T23:59:59.000Z

385

Geotechnical/geochemical characterization of advanced coal process waste streams: Task 2  

SciTech Connect (OSTI)

Successful disposal practices for solid wastes produced from advanced coal combustion and coal conversion processes must provide for efficient management of relatively large volumes of wastes in a cost-effective and environmentally safe manner. At present, most coal-utilization solid wastes are disposed of using various types of land-based systems, and it is probable that this disposal mode will continue to be widely used in the future for advanced process wastes. Proper design and operation of land-based disposal systems for coal combustion wastes normally require appropriate waste transfer, storage, and conditioning subsystems at the plant to prepare the waste for transport to an ultimate disposal site. Further, the overall waste management plan should include a by-product marketing program to minimize the amount of waste that will require disposal. In order to properly design and operate waste management systems for advanced coal-utilization processes, a fundamental understanding of the physical properties, chemical and mineral compositions, and leaching behaviors of the wastes is required. In order to gain information about the wastes produced by advanced coal-utilization processes, 55 waste samples from 16 different coal gasification, fluidized-bed coal combustion (FBC), and advanced flue gas scrubbing processes were collected. Thirty-four of these wastes were analyzed for their bulk chemical and mineral compositions and tested for a detailed set of disposal-related physical properties. The results of these waste characterizations are presented in this report. In addition to the waste characterization data, this report contains a discussion of potentially useful waste management practices for advanced coal utilization processes.

Moretti, C.J.; Olson, E.S.

1992-09-01T23:59:59.000Z

386

WRAP Module 1 sampling strategy and waste characterization alternatives study  

SciTech Connect (OSTI)

The Waste Receiving and Processing Module 1 Facility is designed to examine, process, certify, and ship drums and boxes of solid wastes that have a surface dose equivalent of less than 200 mrem/h. These wastes will include low-level and transuranic wastes that are retrievably stored in the 200 Area burial grounds and facilities in addition to newly generated wastes. Certification of retrievably stored wastes processing in WRAP 1 is required to meet the waste acceptance criteria for onsite treatment and disposal of low-level waste and mixed low-level waste and the Waste Isolation Pilot Plant Waste Acceptance Criteria for the disposal of TRU waste. In addition, these wastes will need to be certified for packaging in TRUPACT-II shipping containers. Characterization of the retrievably stored waste is needed to support the certification process. Characterization data will be obtained from historical records, process knowledge, nondestructive examination nondestructive assay, visual inspection of the waste, head-gas sampling, and analysis of samples taken from the waste containers. Sample characterization refers to the method or methods that are used to test waste samples for specific analytes. The focus of this study is the sample characterization needed to accurately identify the hazardous and radioactive constituents present in the retrieved wastes that will be processed in WRAP 1. In addition, some sampling and characterization will be required to support NDA calculations and to provide an over-check for the characterization of newly generated wastes. This study results in the baseline definition of WRAP 1 sampling and analysis requirements and identifies alternative methods to meet these requirements in an efficient and economical manner.

Bergeson, C.L.

1994-09-30T23:59:59.000Z

387

Electromagnetic mixed-waste processing system for asbestos decontamination  

SciTech Connect (OSTI)

The first phase of a program to develop and demonstrate a cost-effective, integrated process for remediation of asbestos-containing material that is contaminated with organics, heavy metals, and radioactive compounds was successfully completed. Laboratory scale tests were performed to demonstrate initial process viability for asbestos conversion, organics removal, and radionuclide and heavy metal removal. All success criteria for the laboratory tests were met. (1) Ohio DSI demonstrated greater than 99% asbestos conversion to amorphous solids using their commercial process. (2) KAI demonstrated 90% removal of organics from the asbestos suspension. (3) Westinghouse STC achieved the required metals removal criteria on a laboratory scale (e.g., 92% removal of uranium from solution, resin loadings of 0.6 equivalents per liter, and greater than 50% regeneration of resin in a batch test.) Using the information gained in the laboratory tests, the process was reconfigured to provide the basis for the mixed waste remediation system. An integrated process is conceptually developed, and a Phase 2 program plan is proposed to provide the bench-scale development needed in order to refine the design basis for a pilot processing system.

NONE

1995-04-01T23:59:59.000Z

388

Tank waste remediation system process engineering instruction manual  

SciTech Connect (OSTI)

The purpose of the Tank Waste Remediation System (TWRS) Process Engineering Instruction Manual is to provide guidance and direction to TWRS Process Engineering staff regarding conduct of business. The objective is to establish a disciplined and consistent approach to business such that the work processes within TWRS Process Engineering are safe, high quality, disciplined, efficient, and consistent with Lockheed Martin Hanford Corporation Policies and Procedures. The sections within this manual are of two types: for compliance and for guidance. For compliance sections are intended to be followed per-the-letter until such time as they are formally changed per Section 2.0 of this manual. For guidance sections are intended to be used by the staff for guidance in the conduct of work where technical judgment and discernment are required. The guidance sections shall also be changed per Section 2.0 of this manual. The required header for each manual section is illustrated in Section 2.0, Manual Change Control procedure. It is intended that this manual be used as a training and indoctrination resource for employees of the TWRS Process Engineering organization. The manual shall be required reading for all TWRS Process Engineering staff, matrixed, and subcontracted employees.

ADAMS, M.R.

1998-11-04T23:59:59.000Z

389

DOE Waste Isolation Pilot Plant Receives EPA Recertification | Department  

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

Waste Isolation Pilot Plant Receives EPA Recertification Waste Isolation Pilot Plant Receives EPA Recertification DOE Waste Isolation Pilot Plant Receives EPA Recertification March 29, 2006 - 9:42am Addthis CARLSBAD, NM - The U.S. Department of Energy's (DOE) Carlsbad Field Office today reached a significant milestone when its Waste Isolation Pilot Plant (WIPP) was recertified by the U.S. Environmental Protection Agency (EPA). This decision indicates that after a thorough evaluation of the physical state and performance of the facility, the WIPP meets EPA regulatory requirements for facilities that dispose of transuranic waste. The waste facility recertification process occurs every five years and is directed by Congress in the WIPP Land Withdrawal Act (LWA). "EPA's recertification reinforces the important mission of WIPP to safely

390

1993 baseline solid waste management system description  

SciTech Connect (OSTI)

Pacific Northwest Laboratory has prepared this report under the direction of Westinghouse Hanford Company. The report provides an integrated description of the system planned for managing Hanford`s solid low-level waste, low-level mixed waste, transuranic waste, and transuranic mixed waste. The primary purpose of this document is to illustrate a collective view of the key functions planned at the Hanford Site to handle existing waste inventories, as well as solid wastes that will be generated in the future. By viewing this system as a whole rather than as individual projects, key facility interactions and requirements are identified and a better understanding of the overall system may be gained. The system is described so as to form a basis for modeling the system at various levels of detail. Model results provide insight into issues such as facility capacity requirements, alternative system operating strategies, and impacts of system changes (ie., startup dates). This description of the planned Hanford solid waste processing system: defines a baseline system configuration; identifies the entering waste streams to be managed within the system; identifies basic system functions and waste flows; and highlights system constraints. This system description will evolve and be revised as issues are resolved, planning decisions are made, additional data are collected, and assumptions are tested and changed. Out of necessity, this document will also be revised and updated so that a documented system description, which reflects current system planning, is always available for use by engineers and managers. It does not provide any results generated from the many alternatives that will be modeled in the course of analyzing solid waste disposal options; such results will be provided in separate documents.

Armacost, L.L.; Fowler, R.A.; Konynenbelt, H.S.

1994-02-01T23:59:59.000Z

391

Implications of Fast Reactor Transuranic Conversion Ratio  

SciTech Connect (OSTI)

Theoretically, the transuranic conversion ratio (CR), i.e. the transuranic production divided by transuranic destruction, in a fast reactor can range from near zero to about 1.9, which is the average neutron yield from Pu239 minus 1. In practice, the possible range will be somewhat less. We have studied the implications of transuranic conversion ratio of 0.0 to 1.7 using the fresh and discharge fuel compositions calculated elsewhere. The corresponding fissile breeding ratio ranges from 0.2 to 1.6. The cases below CR=1 (burners) do not have blankets; the cases above CR=1 (breeders) have breeding blankets. The burnup was allowed to float while holding the maximum fluence to the cladding constant. We graph the fuel burnup and composition change. As a function of transuranic conversion ratio, we calculate and graph the heat, gamma, and neutron emission of fresh fuel; whether the material is attractive for direct weapon use using published criteria; the uranium utilization and rate of consumption of natural uranium; and the long-term radiotoxicity after fuel discharge. For context, other cases and analyses are included, primarily once-through light water reactor (LWR) uranium oxide fuel at 51 MWth-day/kg-iHM burnup (UOX-51). For CR<1, the heat, gamma, and neutron emission increase as material is recycled. The uranium utilization is at or below 1%, just as it is in thermal reactors as both types of reactors require continuing fissile support. For CR>1, heat, gamma, and neutron emission decrease with recycling. The uranium utilization exceeds 1%, especially as all the transuranic elements are recycled. exceeds 1%, especially as all the transuranic elements are recycled. At the system equilibrium, heat and gamma vary by somewhat over an order of magnitude as a function of CR. Isotopes that dominate heat and gamma emission are scattered throughout the actinide chain, so the modest impact of CR is unsurprising. Neutron emitters are preferentially found among the higher actinides, so the neutron emission varies much stronger with CR, about three orders of magnitude.

Steven J. Piet; Edward A. Hoffman; Samuel E. Bays

2010-11-01T23:59:59.000Z

392

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

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

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

393

Preliminary evaluation of alternative waste form solidification processes. Volume II. Evaluation of the processes  

SciTech Connect (OSTI)

This Volume II presents engineering feasibility evaluations of the eleven processes for solidification of nuclear high-level liquid wastes (HHLW) described in Volume I of this report. Each evaluation was based in a systematic assessment of the process in respect to six principal evaluation criteria: complexity of process; state of development; safety; process requirements; development work required; and facility requirements. The principal criteria were further subdivided into a total of 22 subcriteria, each of which was assigned a weight. Each process was then assigned a figure of merit, on a scale of 1 to 10, for each of the subcriteria. A total rating was obtained for each process by summing the products of the subcriteria ratings and the subcriteria weights. The evaluations were based on the process descriptions presented in Volume I of this report, supplemented by information obtained from the literature, including publications by the originators of the various processes. Waste form properties were, in general, not evaluated. This document describes the approach which was taken, the developent and application of the rating criteria and subcriteria, and the evaluation results. A series of appendices set forth summary descriptions of the processes and the ratings, together with the complete numerical ratings assigned; two appendices present further technical details on the rating process.

Not Available

1980-08-01T23:59:59.000Z

394

Defense Waste Processing Facility wasteform and canister description: Revision 2  

SciTech Connect (OSTI)

This document describes the reference wasteform and canister for the Defense Waste Processing Facility (DWPF). The principal changes include revised feed and glass product compositions, an estimate of glass product characteristics as a function of time after the start of vitrification, and additional data on glass leaching performance. The feed and glass product composition data are identical to that described in the DWPF Basic Data Report, Revision 90/91. The DWPF facility is located at the Savannah River Plant in Aiken, SC, and it is scheduled for construction completion during December 1989. The wasteform is borosilicate glass containing approximately 28 wt % sludge oxides, with the balance consisting of glass-forming chemicals, primarily glass frit. Borosilicate glass was chosen because of its stability toward reaction with potential repository groundwaters, its relatively high ability to incorporate nuclides found in the sludge into the solid matrix, and its reasonably low melting temperature. The glass frit contains approximately 71% SiO/sub 2/, 12% B/sub 2/O/sub 3/, and 10% Na/sub 2/O. Tests to quantify the stability of DWPF waste glass have been performed under a wide variety of conditions, including simulations of potential repository environments. Based on these tests, DWPF waste glass should easily meet repository criteria. The canister is filled with about 3700 lb of glass which occupies 85% of the free canister volume. The filled canister will generate approximately 690 watts when filled with oxides from 5-year-old sludge and precipitate from 15-year-old supernate. The radionuclide activity of the canister is about 233,000 curies, with an estimated radiation level of 5600 rad/hour at the canister surface. 14 figs., 28 tabs.

Baxter, R.G.

1988-12-01T23:59:59.000Z

395

Composition and process for the encapsulation and stabilization of radioactive, hazardous and mixed wastes  

DOE Patents [OSTI]

The present invention provides a composition and process for disposal of radioactive, hazardous and mixed wastes. The present invention preferably includes a process for multibarrier encapsulation of radioactive, hazardous and mixed wastes by combining substantially simultaneously dry waste powder, a non-biodegradable thermoplastic polymer and an anhydrous additive in an extruder to form a homogenous molten matrix. The molten matrix may be directed in a "clean" polyethylene liner, allowed to cool, thus forming a monolithic waste form which provides a multibarrier to the dispersion of wastes into the environment.

Kalb, Paul D. (Wading River, NY); Colombo, Peter (Patchogue, NY)

1998-03-24T23:59:59.000Z

396

Composition and process for the encapsulation and stabilization of radioactive hazardous and mixed wastes  

DOE Patents [OSTI]

The present invention provides a composition and process for disposal of radioactive, hazardous and mixed wastes. The present invention preferably includes a process for multibarrier encapsulation of radioactive, hazardous and mixed wastes by combining substantially simultaneously dry waste powder, a non-biodegradable thermoplastic polymer and an anhydrous additive in an extruder to form a homogeneous molten matrix. The molten matrix may be directed in a ``clean`` polyethylene liner, allowed to cool, thus forming a monolithic waste form which provides a multibarrier to the dispersion of wastes into the environment. 2 figs.

Kalb, P.D.; Colombo, P.

1997-07-15T23:59:59.000Z

397

Composition and process for the encapsulation and stabilization of radioactive, hazardous and mixed wastes  

DOE Patents [OSTI]

The present invention provides a composition and process for disposal of radioactive, hazardous and mixed wastes. The present invention preferably includes a process for multibarrier encapsulation of radioactive, hazardous and mixed wastes by combining substantially simultaneously dry waste powder, a non-biodegradable thermoplastic polymer and an anhydrous additive in an extruder to form a homogeneous molten matrix. The molten matrix may be directed in a ``clean`` polyethylene liner, allowed to cool, thus forming a monolithic waste form which provides a multibarrier to the dispersion of wastes into the environment. 2 figs.

Kalb, P.D.; Colombo, P.

1998-03-24T23:59:59.000Z

398

Composition and process for the encapsulation and stabilization of radioactive, hazardous and mixed wastes  

DOE Patents [OSTI]

The present invention provides a composition and process for disposal of radioactive, hazardous and mixed wastes. The present invention preferably includes a process for multibarrier encapsulation of radioactive, hazardous and mixed wastes by combining substantially simultaneously dry waste powder, a non-biodegradable thermoplastic polymer and an anhydrous additive in an extruder to form a homogeneous molten matrix. The molten matrix may be directed in a clean'' polyethylene liner, allowed to cool, thus forming a monolithic waste form which provides a multibarrier to the dispersion of wastes into the environment. 2 figs.

Kalb, P.D.; Colombo, P.

1999-07-20T23:59:59.000Z

399

Composition and process for the encapsulation and stabilization of radioactive hazardous and mixed wastes  

DOE Patents [OSTI]

The present invention provides a composition and process for disposal of radioactive, hazardous and mixed wastes. The present invention preferably includes a process for multibarrier encapsulation of radioactive, hazardous and mixed wastes by combining substantially simultaneously dry waste powder, a non-biodegradable thermoplastic polymer and an anhydrous additive in an extruder to form a homogenous molten matrix. The molten matrix may be directed in a "clean" polyethylene liner, allowed to cool, thus forming a monolithic waste form which provides a multibarrier to the dispersion of wastes into the environment.

Kalb, Paul D. (21 Barnes Road, Wading River, NY 11792); Colombo, Peter (44 N. Pinelake Dr., Patchogue, NY 11772)

1997-01-01T23:59:59.000Z

400

Composition and process for the encapsulation and stabilization of radioactive, hazardous and mixed wastes  

DOE Patents [OSTI]

The present invention provides a composition and process for disposal of radioactive, hazardous and mixed wastes. The present invention preferably includes a process for multibarrier encapsulation of radioactive, hazardous and mixed wastes by combining substantially simultaneously dry waste powder, a non-biodegradable thermoplastic polymer and an anhydrous additive in an extruder to form a homogenous molten matrix. The molten matrix may be directed in a "clean" polyethylene liner, allowed to cool, thus forming a monolithic waste form which provides a multibarrier to the dispersion of wastes into the environment.

Kalb, Paul D. (Wading River, NY); Colombo, Peter (Patchogue, NY)

1999-07-20T23:59:59.000Z

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


401

Waste Receiving and Processing, Module 2A, feed specification: Revision 1  

SciTech Connect (OSTI)

Detailed descriptions of the various mixed low-level waste feed streams that will be processed in the Waste Receiving and Processing Facility, Module 2A (WRAP 2A) are provided. Feed stream descriptions are based on available reports, the solid waste information tracking system database, and the 1993 solid waste forecast data. Available chemical and physical attributes, radionuclide data, waste codes, and packaging information are shown for 15 feed streams. The information sources and methodology for obtaining projections for WRAP 2A expected feed stream volumes also are described.

Kruger, O.L.; Sheriff, M.L.

1994-11-14T23:59:59.000Z

402

Salt Waste Processing Facility Fact Sheet | Department of Energy  

Office of Environmental Management (EM)

waste that is being stored, on an interim basis, in 49 underground waste storage tanks in the F- and H-Area Tank Farms. SWPF Fact Sheet More Documents & Publications...

403

Waste Heat Management Options: Industrial Process Heating Systems  

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

itself * Waste heat recovery or auxiliary or adjoining systems within a plant * Waste heat to power conversion Recycle Copyrighted - E3M Inc. August 20, 2009 Arvind Thekdi, E3M...

404

Voluntary Protection Program Onsite Review, Salt Waste Processing Facility Construction Project- February 2013  

Broader source: Energy.gov [DOE]

Evaluation to determine whether Salt Waste Processing Facility Construction Project is continuing to perform at a level deserving DOE-VPP Star recognition.

405

GRR/Section 18 - Waste and Hazardous Material Assessment Process | Open  

Open Energy Info (EERE)

- Waste and Hazardous Material Assessment Process - Waste and Hazardous Material Assessment Process < GRR Jump to: navigation, search GRR-logo.png GEOTHERMAL REGULATORY ROADMAP Roadmap Home Roadmap Help List of Sections Section 18 - Waste and Hazardous Material Assessment Process 18 - WasteAndHazardousMaterialAssessmentProcess.pdf Click to View Fullscreen Contact Agencies Environmental Protection Agency Regulations & Policies RCRA CERCLA 40 CFR 261 Triggers None specified Click "Edit With Form" above to add content 18 - WasteAndHazardousMaterialAssessmentProcess.pdf Error creating thumbnail: Page number not in range. Error creating thumbnail: Page number not in range. Error creating thumbnail: Page number not in range. Flowchart Narrative The use of underground and above ground storage tanks, discovery of waste

406

GRR/Section 18-AK-c - Waste Disposal Permit Process | Open Energy  

Open Energy Info (EERE)

AK-c - Waste Disposal Permit Process AK-c - Waste Disposal Permit Process < GRR Jump to: navigation, search GRR-logo.png GEOTHERMAL REGULATORY ROADMAP Roadmap Home Roadmap Help List of Sections Section 18-AK-c - Waste Disposal Permit Process 18AKC - WasteDisposalPermitProcess (1).pdf Click to View Fullscreen Contact Agencies Alaska Department of Environmental Conservation Regulations & Policies AS 46.03.110 Waste Disposal Permit Regulations 18 AAC 60.200 et seq Triggers None specified Click "Edit With Form" above to add content 18AKC - WasteDisposalPermitProcess (1).pdf Error creating thumbnail: Page number not in range. Error creating thumbnail: Page number not in range. Error creating thumbnail: Page number not in range. Flowchart Narrative The Alaska Department of Environmental Conservation (DEC) is responsible

407

GRR/Section 18-OR-b - Hazardous Waste Permit Process | Open Energy  

Open Energy Info (EERE)

OR-b - Hazardous Waste Permit Process OR-b - Hazardous Waste Permit Process < GRR Jump to: navigation, search GRR-logo.png GEOTHERMAL REGULATORY ROADMAP Roadmap Home Roadmap Help List of Sections Section 18-OR-b - Hazardous Waste Permit Process 18ORBHazardousWastePermitProcess (1).pdf Click to View Fullscreen Contact Agencies United States Environmental Protection Agency Oregon Department of Environmental Quality Oregon Public Health Division Oregon Public Utility Commission Oregon Department of Fish and Wildlife Oregon Water Resources Department Regulations & Policies OAR 340-105: Management Facility Permits OAR 340-120: Hazardous Waste Management ORS 466: Storage, Treatment, and Disposal Triggers None specified Click "Edit With Form" above to add content 18ORBHazardousWastePermitProcess (1).pdf

408

Waste receiving and processing plant control system; system design description  

SciTech Connect (OSTI)

The Plant Control System (PCS) is a heterogeneous computer system composed of numerous sub-systems. The PCS represents every major computer system that is used to support operation of the Waste Receiving and Processing (WRAP) facility. This document, the System Design Description (PCS SDD), includes several chapters and appendices. Each chapter is devoted to a separate PCS sub-system. Typically, each chapter includes an overview description of the system, a list of associated documents related to operation of that system, and a detailed description of relevant system features. Each appendice provides configuration information for selected PCS sub-systems. The appendices are designed as separate sections to assist in maintaining this document due to frequent changes in system configurations. This document is intended to serve as the primary reference for configuration of PCS computer systems. The use of this document is further described in the WRAP System Configuration Management Plan, WMH-350, Section 4.1.

LANE, M.P.

1999-02-24T23:59:59.000Z

409

INVESTIGATION OF WASTE GLASS POURING PROCESS OVER A KNIFE EDGE  

SciTech Connect (OSTI)

Vitrification is the process of capturing radioactive waste in glass. The Savannah River Site's (SRS) Defense Waste Processing Facility (DWPF) is one of the facilities using the vitrification technology to treat and immobilize radioactive waste. The objective of the project is to investigate the pouring behavior of molten glass over a pour spout knife edge. Experiments are run using simulant glass containing the same chemical formulation as the radioactive sludge glass, but without radioactive contaminants. The purpose of these tests is to obtain actual glass data that, when combined with previous cold data from other fluids, will provide an overall understanding of the physics of liquids flowing over a pour spout and knife edge, A specific objective is to verify computational fluid dynamics (CFD) models with a range of liquid data with particular emphasis on glass so as to provide confidence in use of these CFD models for designing a new improved pour spout for the DWPF melter. The work to be performed at FIU-HCET includes assembling the melting and pouring system that mimics the DWPF melter and determining the key parameters that may influence wicking. Information from the FIU-HCET melter tests will lead to better operating guidelines for the DWPF melter so as to avoid wicking. During FY98, a bench-scale melter complete with pour spout and a knife edge was designed and assembled at FIU-HCET. Initially, the system was tested with glycerine. Subsequently, glass provided by SRS was used for experimentation. Flow visualization tests were performed with the melter in FY98 to investigate the pouring behavior of molten glass over a pour spout model simulating a DWPF pour spout of the original design. Simulant glass containing the same chemical formulation as sludge glass but without radioactive contaminants was used in the tests. All the tasks and milestones mentioned in the PTP for the project were accomplished. The project completed its second year, and this document reports the tasks and milestones that were accomplished during the 1998 fiscal year.

M.A. Ebadian, Ph.D.

1999-01-01T23:59:59.000Z

410

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

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

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

411

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

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

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

412

The waste isolation pilot plant regulatory compliance program  

SciTech Connect (OSTI)

The passage of the WIPP Land Withdrawal Act of 1992 (LWA) marked a turning point for the Waste Isolation Pilot Plant (WIPP) program. It established a Congressional ma