1 edition of Technical bases for estimating fission product behavior during LWR accidents found in the catalog.
Technical bases for estimating fission product behavior during LWR accidents
by Office of Nuclear Regulatory Research [and] Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission, National Technical Information Service [distributor] in Washington, D.C, Springfield, Va
Written in English
|Contributions||Battelle Memorial Institute. Columbus Laboratories, Oak Ridge National Laboratory, Sandia National Laboratories, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation|
|The Physical Object|
|Pagination||336 p. in various pagings :|
|Number of Pages||336|
Department of Nuclear Science and Engineering 3 Principal Design Functions Involving Reactor Physics • Core criticality and power distribution ¾Are space and time dependent because of fuel burnup and isotope production over the core life ¾Depend on core enrichment, moderator-to-fuel ratio, core geometry, location and type of reactivity control, fuel element designFile Size: KB. Aluminum-based spent nuclear fuel (Al-SNF) from foreign and domestic research reactors (FRR/DRR) is being shipped to the Savannah River Site. To enter the U.S., the cask with loaded fuel must be certified to comply with the requirements in the Title 10 of the U.S. Code of Federal Regulations, Part.
Relap5 represents the aggregate accumulation of experience in modeling reactor-core behavior during severe accidents, two-phase flow processes, and LWR systems. The code's development has benefited from extensive application and comparison to experimental data in the LOFT, PBF, Semiscale, ACRR, NRU, and other experimental programs. T.V. Delorme et al. 3 ⎯ Off-line analyses of reactor pool water at the end of a production week. A sample of the reactor pool water from a depth of approximately 3 m is taken at the end of a production week and analysed for I and I after one day for the decay of Na
The fission product transport in the primary circuit and in the containment was investigated in nuclear reactor severe accident conditions, where the reactor core is damaged and core materials are released from the reactor pressure vessel. The Nuclear Energy Advanced Modeling and Simulation (NEAMS) Program Keith S. Bradley National Technical Director. Presented at the 12th Annual Materials Modeling and .
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National Technical Report Library. Publication Date: Page Count: Abstract: The objective of this report is to provide the Nuclear Regulatory Commission and the public with a description of the best technical information currently available for estimating the release of radioactive material during postulated reactor accidents, and to identify where gaps exist in our knowledge.
Technical bases for estimating fission product behavior during LWR accidents [Anonymous.] on *FREE* shipping on qualifying offers. Technical bases for estimating fission product behavior during LWR accidentsAuthor. Anonymous. Technical bases for estimating fission product behavior during LWR accidents.
Washington, D.C.: Office of Nuclear Regulatory Research [and] Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission: Available from GPO Sales Program, Division of Technical Information and Document Control, U.S.
Nuclear Regulatory Commission. Technical Report () Conference Proceedings () Journal Article (). An analysis of fission product release during the Three Mile Island Unit 2 (TMI-2) accident has been initiated to provide an understanding of fission product behavior that is consistent with both the best estimate accident scenario and fission product results from the ongoing sample acquisition and examination efforts.
A method for calculating the fraction of rare gas fission products that diffuses out of a UO/sub 2/ fuel element under reactor conditions is outlined. The method is based on the values of the diffusion constant found in laboratory experiments, and assumes that these remain unaltered during the.
Fission Product Processes In Reactor Accidents (Proceedings of the International Centre for Heat and Mass Transfer) [Rogers, J. T.] on *FREE* shipping on qualifying offers. Fission Product Processes In Reactor Accidents (Proceedings of the International Centre for Heat and Mass Transfer).
In order to develop a domestic research roadmap for severe accidents, a special committee was established by the Korean Nuclear Society. One of the subcommittees discussed the characteristics and the relevant technical issues in the stages of fission product release and physical forms of radionuclide release and by: 3.
KEYWORDS: severe nuclear accident, fission product behavior, uncertainty analysis, MAAP code I. Introduction During a severe nuclear accident, an analysis of source term and relevant fission product (FP) behavior is an essential part for an accident management of nuclear power plants and an emergency planning.
Relating with the. Technical bases for estimating fission product behavior in LWR reactors. NUREG, United States Nuclear Regulatory Commission. Nuclear Safety Program Semiannual Progress Report for Period Ending. Characteristic features of the calculation of the yield of fission products from a destroyed core during serious accidents.
Bespalov, A. Karatov, P. Mikhailov, G. Momot & A. Khrulev Atomic Energy vol pages – ()Cite this articleCited by: 1. Technical Bases for Estimating Fission Product Behavior in LWR Reactors.
NUREG, United States Nuclear Regulatory commission. Probabilistic Safety Assessment of Research Reactor. Fission products behavior has been studied for a long time via comprehensive studies that resulted in a number of models developed to express and explain this behavior.
The DAB hypothesis (Ajlouni, ) is a new hypothesis introduced here to present a more developed criterion to explain FP behavior inside the reactor and in the environment.
session 4 NUCLEAR REACTOR SAFETY Journal of Nuclear Materials () North-Holland, Amsterdam VOLATILITY OF FISSION PRODUCTS DURING REACTOR ACCIDENTS J. PAQUETTE, D.F. TORGERSON, J.C.
WREN and D.J. WREN Atomic Energy of Canada Research Company, Whiteshell Nuclear Research Establishment, Pinawa, Manitoba, Canada ROE 1LO This Cited by: bulk, r - fission product range λ - decay constant of isotope i, β - formation yield of the intermediate gas of isotope i, f - fission rate, t - time, x - distance into the fuel from the sample surface, r - fission product range, Db - diffusion coefficient of bubbles, B - burn-up in MWd/tU, M - concentration of intermediateFile Size: KB.
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We apologize for any inconvenience this may have caused and are working to. 10 Coolant Case Study: S-CO 2 • Power Conversion System (PCS) work begat the neutronics work High efficiency Brayton cycle (%) e (33%) Allows for a direct cycle • Can provide better natural circulation capability than He • Can do it all at lower temperatures (oC) than Helium (oC) • Requires a higher pressure for Decay Heat Removal and.
TITLE AND SUBTITLE Technical Support of Standards for High-level Radioactive Waste Management, Volume B, Engineering Controls, 5. To help establish the technical bases for HLW standards, EPA has embarked on this technical support project.
At % of fuel plutonium and fission product content, fresh cladding wastes are contaminated with. Other Parts of the Index: Part 2 of 4 Part 3 of 4 Part 4 of 4. Periodicals and Special Collections Los Alamos Science-- magazine Dateline Los Alamos-- magazine Los Alamos Reflections-- monthly publication for employees and retirees Los Alamos: Beginning of an Era-- historical report (and Trinity color photo) Los Alamos 50 th Anniversary-- historical articles and photos.
Analysis of Fission Products-A Method for Verification of a CTBT During On-Site Inspections Li, Bino If under a Comprehensive Test Ban Treaty a suspicious event can be accurately located, it should be possible to sample possible fission products through an on-site inspection.
Technical terms 1 Long-lived fission products (LLFPs): Radioactive materials with long half-lives produced by nuclear fission. This study concerns the LLFPs selenium, zirconium, technetium.The code should describe fission product release from LWR fuels during thermal transients and severe reactor accidents and should be developed based on experimental results obtained from other NRC sponsored programs on the area of fission product release.
TITLE: POST TEST FUEL EXAM FY 85 FY 86 FY 87 CONTRACTOR: Argonne National BUDGET Full text of "Development of fission-products transport model in severe-accident scenarios for SCDAP/RELAPS" See other formats.