科技报告详细信息
Reactor Safety Gap Evaluation of Accident Tolerant Components and Severe Accident Analysis
Farmer, Mitchell T.1  Bunt, R.2  Corradini, M.3  Ellison, Paul B.4  Francis, M.1  Gabor, John D.5  Gauntt, R.6  Henry, C.7  Linthicum, R.8  Luangdilok, W.7  Lutz, R.9  Paik, C.7  Plys, M.7  Rabiti, Cristian1,10  Rempe, J.1,11  Robb, K.1  Wachowiak, R.1,12 
[1] Argonne National Lab. (ANL), Argonne, IL (United States);Southern Nuclear, Atlanta, GA (United States);Univ. of Wisconsin, Madison, WI (United States);GE Power and Water, Duluth, GA (United States);Erin Engineering, Walnut Creek, CA (United States);Sandia National Lab. (SNL-NM), Albuquerque, NM (United States);Fauske and Associates, Burr Ridge, IL (United States);Exelon Corp., Chicago, IL (United States);PWR Owners Group (PWROG);Idaho National Lab. (INL), Idaho Falls, ID (United States);Rempe and Associates LLC, Idaho Falls, ID (United States);Electric Power Research Inst. (EPRI), Knovville, TN (United States)
关键词: REACTOR SAFETY;    REACTOR ACCIDENTS;    WATER MODERATED REACTORS;    EVALUATION;    WATER COOLED REACTORS;    INFORMATION NEEDS;    FUKUSHIMA ACCIDENT ARCHIVE;    REACTOR COMPONENTS;    TOLERANCE;   
DOI  :  10.2172/1179777
RP-ID  :  ANL/NE--15/4
PID  :  OSTI ID: 1179777
Others  :  Other: 79578
Others  :  TRN: US1500885
美国|英语
来源: SciTech Connect
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【 摘 要 】

The overall objective of this study was to conduct a technology gap evaluation on accident tolerant components and severe accident analysis methodologies with the goal of identifying any data and/or knowledge gaps that may exist, given the current state of light water reactor (LWR) severe accident research, and additionally augmented by insights obtained from the Fukushima accident. The ultimate benefit of this activity is that the results can be used to refine the Department of Energy???s (DOE) Reactor Safety Technology (RST) research and development (R&D) program plan to address key knowledge gaps in severe accident phenomena and analyses that affect reactor safety and that are not currently being addressed by the industry or the Nuclear Regulatory Commission (NRC).

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