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Title: Plutonium disposition study phase 1b final report

Abstract

This report provides the results of the Westinghouse activities performed as part of the Plutonium Disposition Study Phase 1b. These activities, which took place from May 16, 1993 to September 15, 1993, build upon the work completed in Phase 1a, which concluded on May 15, 1993. In Phase 1a, three Plutonium Disposal Reactor (PDR) options were developed for the disposal of excess weapons grade plutonium from returned and dismantled nuclear weapons. This report documents the results of several tasks that were performed to further knowledge in specific areas leading up to Phase 2 of the PDR Study. The Westinghouse activities for Phase 1b are summarized as follows: (1) resolved technical issues concerning reactor physics including equilibrium cycle calculations, use of gadolinium, moderator temperature coefficient, and others as documented in Section 2.0; (2) analyzed large Westinghouse commercial plants for plutonium disposal; (3) reactor safety issues including the steam line break were resolved, and are included in Section 2.0; (4) several tasks related to the PDR Fuel Cycle were examined; (5) cost and deployment options were examined to determine optimal configuration for both plutonium disposal and tritium production; (6) response to questions from DOE and National Academy of Scientists (NAS) reviewers concerningmore » the PDR Phase 1a report are included in Appendix A.« less

Publication Date:
Research Org.:
Westinghouse Electric Corp., Pittsburgh, PA (United States)
Sponsoring Org.:
USDOE Assistant Secretary for Nuclear Energy, Washington, DC (United States); USDOE Office of Fissile Materials Disposition, Washington, DC (United States)
OSTI Identifier:
595654
Report Number(s):
DOE/SF/19683-2
ON: DE98004814; TRN: 98:004807
DOE Contract Number:
AC03-93SF19683
Resource Type:
Technical Report
Resource Relation:
Other Information: PBD: 15 Sep 1993
Country of Publication:
United States
Language:
English
Subject:
05 NUCLEAR FUELS; 21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; PLUTONIUM; NUCLEAR MATERIALS MANAGEMENT; ACTINIDE BURNER REACTORS; PROGRESS REPORT; FUEL CYCLE; NUCLEAR WEAPONS DISMANTLEMENT; PWR TYPE REACTORS; MIXED OXIDE FUELS

Citation Formats

NONE. Plutonium disposition study phase 1b final report. United States: N. p., 1993. Web. doi:10.2172/595654.
NONE. Plutonium disposition study phase 1b final report. United States. doi:10.2172/595654.
NONE. Wed . "Plutonium disposition study phase 1b final report". United States. doi:10.2172/595654. https://www.osti.gov/servlets/purl/595654.
@article{osti_595654,
title = {Plutonium disposition study phase 1b final report},
author = {NONE},
abstractNote = {This report provides the results of the Westinghouse activities performed as part of the Plutonium Disposition Study Phase 1b. These activities, which took place from May 16, 1993 to September 15, 1993, build upon the work completed in Phase 1a, which concluded on May 15, 1993. In Phase 1a, three Plutonium Disposal Reactor (PDR) options were developed for the disposal of excess weapons grade plutonium from returned and dismantled nuclear weapons. This report documents the results of several tasks that were performed to further knowledge in specific areas leading up to Phase 2 of the PDR Study. The Westinghouse activities for Phase 1b are summarized as follows: (1) resolved technical issues concerning reactor physics including equilibrium cycle calculations, use of gadolinium, moderator temperature coefficient, and others as documented in Section 2.0; (2) analyzed large Westinghouse commercial plants for plutonium disposal; (3) reactor safety issues including the steam line break were resolved, and are included in Section 2.0; (4) several tasks related to the PDR Fuel Cycle were examined; (5) cost and deployment options were examined to determine optimal configuration for both plutonium disposal and tritium production; (6) response to questions from DOE and National Academy of Scientists (NAS) reviewers concerning the PDR Phase 1a report are included in Appendix A.},
doi = {10.2172/595654},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Wed Sep 15 00:00:00 EDT 1993},
month = {Wed Sep 15 00:00:00 EDT 1993}
}

Technical Report:

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  • Core reactivity and basic fuel management calculations were conducted on the selected reactors (with emphasis on the System 80 units as being the most desirable choice). Methods used were identical to those reported in the Evolutionary Reactor Report. From these calculations, the basic mission capability was assessed. The selected reactors were studied for modification, such as the addition of control rod nozzles to increase rod worth, and internals and control system modifications that might also be needed. Other system modifications studied included the use of enriched boric acid as soluble poison, and examination of the fuel pool capacities. The basicmore » geometry and mechanical characteristics, materials and fabrication techniques of the fuel assemblies for the selected existing reactors are the same as for System 80+. There will be some differences in plutonium loading, according to the ability of the reactors to load MOX fuel. These differences are not expected to affect licensability or EPA requirements. Therefore, the fuel technology and fuel qualification sections provided in the Evolutionary Reactor Report apply to the existing reactors. An additional factor, in that the existing reactor availability presupposes the use of that reactor for the irradiation of Lead Test Assemblies, is discussed. The reactor operating and facility licenses for the operating plants were reviewed. Licensing strategies for each selected reactor were identified. The spent fuel pool for the selected reactors (Palo Verde) was reviewed for capacity and upgrade requirements. Reactor waste streams were identified and assessed in comparison to uranium fuel operations. Cost assessments and schedules for converting to plutonium disposition were estimated for some of the major modification items. Economic factors (incremental costs associated with using weapons plutonium) were listed and where possible under the scope of work, estimates were made.« less
  • Since early 1994, the Department of Energy has been sponsoring studies aimed at evaluating the merits of disposing of surplus US weapons plutonium as Mixed Oxide (MOX) fuel in existing commercial Canadian Pressurized Heavy Water reactors, known as CANDU`s. The first report, submitted to DOE in July, 1994 (the 1994 Executive Summary is attached), identified practical and safe options for the consumption of 50 to 100 tons of plutonium in 25 years in some of the existing CANDU reactors operating the Bruce A generating station, on Lake Huron, about 300 km north east of Detroit. By designing the fuel andmore » nuclear performance to operate within existing experience and operating/performance envelope, and by utilizing existing fuel fabrication and transportation facilities and methods, a low cost, low risk method for long term plutonium disposition was developed. In December, 1995, in response to evolving Mission Requirements, the DOE requested a further study of the CANDU option with emphasis on more rapid disposition of the plutonium, and retaining the early start and low risk features of the earlier work. This report is the result of that additional work.« less
  • The Department of Energy (DOE) has contracted with Asea Brown Boveri-Combustion Engineering (ABB-CE) to provide information on the capability of ABB-CE`s System 80 + Advanced Light Water Reactor (ALWR) to transform, through reactor burnup, 100 metric tonnes (MT) of weapons grade plutonium (Pu) into a form which is not readily useable in weapons. This information is being developed as part of DOE`s Plutonium Disposition Study, initiated by DOE in response to Congressional action. This document, Volume 1, presents a technical description of the various elements of the System 80 + Standard Plant Design upon which the Plutonium Disposition Study wasmore » based. The System 80 + Standard Design is fully developed and directly suited to meeting the mission objectives for plutonium disposal. The bass U0{sub 2} plant design is discussed here.« less
  • The Department of Energy (DOE) has contracted with Asea Brown Boveri-Combustion Engineering (ABB-CE) to provide information on the capability of ABB-CE`s System 80 + Advanced Light Water Reactor (ALWR) to transform, through reactor burnup, 100 metric tonnes (MT) of weapons grade plutonium (Pu) into a form which is not readily useable in weapons. This information is being developed as part of DOE`s Plutonium Disposition Study, initiated by DOE in response to Congressional action. This document Volume 2, provides a discussion of: Plutonium Fuel Cycle; Technology Needs; Regulatory Considerations; Cost and Schedule Estimates; and Deployment Strategy.
  • The planning and design of additions to the ERDA East Mesa Geothermal Component Test Facility is emphasized. This project is supplemental to the US Bureau of Reclamation Phase 1A project which expanded their water desalination operations to accommodate limited-scale geothermal component testing. When construction is completed to the designs reported herein, the East Mesa Geothermal Component Test Facility will provide moderate temperature/low salinity fluids to facilitate comprehansive testing of conversion systems and components under realistic field conditions. The project objectives included: (1) development of designs of new wells and modifications to existing wells to improve definitive reservoir evaluations and (2)more » design of additional test facilities integrated with the limited-scale Phase 1A facilities to accomodate diverse commercial utilization technology experiments. A reservoir utilization evaluation was conducted to establish locations and design drilling programs for three new wells and modifications to existing wells to improve reservoir definition and provide a comprehensive inventory of geothermal well fluids for testing.« less