Research Reactor Core Conversion from the Use of Highly Enriched Uranium to the Use of Low Enriched Uranium Fuels PDF Download
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Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 253
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Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 253
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Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
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Author: International Atomic Energy Agency
Publisher:
ISBN:
Category : Experimental data
Languages : en
Pages : 253
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Author: International Atomic Energy Agency
Publisher:
ISBN:
Category :
Languages : en
Pages : 711
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Author: Russian Academy of Sciences
Publisher: National Academies Press
ISBN: 0309253209
Category : Science
Languages : en
Pages : 126
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Book Description
Highly enriched uranium (HEU) is used for two major civilian purposes: as fuel for research reactors and as targets for medical isotope production. This material can be dangerous in the wrong hands. Stolen or diverted HEU can be used-in conjunction with some knowledge of physics-to build nuclear explosive devices. Thus, the continued civilian use of HEU is of concern particularly because this material may not be uniformly well-protected. To address these concerns, the National Research Council (NRC) of the U.S. National Academies and the Russian Academy of Sciences (RAS) held a joint symposium on June 8-10, 2011. Progress, Challenges, and Opportunities for Converting U.S. and Russian Research Reactors summarizes the proceedings of this joint symposium. This report addresses: (1) recent progress on conversion of research reactors, with a focus on U.S.- and R.F.-origin reactors; (2) lessons learned for overcoming conversion challenges, increasing the effectiveness of research reactor use, and enabling new reactor missions; (3) future research reactor conversion plans, challenges, and opportunities; and (4) actions that could be taken by U.S. and Russian organizations to promote conversion. The agenda for the symposium is provided in Appendix A, biographical sketches of the committee members are provided in Appendix B, and the report concludes with the statement of task in Appendix C.
Author: United States. Congress. House. Committee on Science and Technology. Subcommittee on Energy Development and Applications
Publisher:
ISBN:
Category : Nuclear engineering
Languages : en
Pages : 1968
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Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 710
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Author: International Atomic Energy Agency
Publisher:
ISBN: 9789201018182
Category : Technology & Engineering
Languages : en
Pages : 0
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This publication was developed based on the results of an IAEA coordinated research project (CRP) and will serve as a reference to those potentially involved in conversion of research reactors from high enriched uranium (HEU) to low enriched uranium (LEU). The publication contains comprehensive design and safety analyses for the conversion of miniature neutron source reactors (MNSRs) and includes analyses that were performed by MNSR operating organizations participating in the CRP using data specific to their MNSR. The outcome of this CRP can therefore be used to provide best practice guidelines in preparation for conversion of research reactors by individual research reactor operating organizations, and as a procedural and methodological reference for regulatory bodies and other stakeholders involved in the conversion of research reactors.
Author: John E. Stoddard
Publisher:
ISBN:
Category : Nuclear fuels
Languages : en
Pages : 320
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Author: R. J. Ellis
Publisher:
ISBN:
Category :
Languages : en
Pages :
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A computational study will be initiated during fiscal year 2006 to examine the feasibility of converting the High Flux Isotope Reactor from highly enriched uranium fuel to low-enriched uranium. The study will be limited to steady-state, nominal operation, reactor physics and thermal-hydraulic analyses of a uranium-molybdenum alloy that would be substituted for the current fuel powder--U{sub 3}O{sub 8} mixed with aluminum. The purposes of this document are to (1) define the scope of studies to be conducted, (2) define the methodologies to be used to conduct the studies, (3) define the assumptions that serve as input to the methodologies, (4) provide an efficient means for communication with the Department of Energy and American research reactor operators, and (5) expedite review and commentary by those parties.
