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Title: Reactor Safety Gap Evaluation of Accident Tolerant Components and Severe Accident Analysis

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).
Authors:
 [1] ;  [2] ;  [3] ;  [4] ;  [1] ;  [5] ;  [6] ;  [7] ;  [8] ;  [7] ;  [9] ;  [7] ;  [7] ;  [10] ;  [11] ;  [1] ;  [12]
  1. Argonne National Lab. (ANL), Argonne, IL (United States)
  2. Southern Nuclear, Atlanta, GA (United States)
  3. Univ. of Wisconsin, Madison, WI (United States)
  4. GE Power and Water, Duluth, GA (United States)
  5. Erin Engineering, Walnut Creek, CA (United States)
  6. Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
  7. Fauske and Associates, Burr Ridge, IL (United States)
  8. Exelon Corp., Chicago, IL (United States)
  9. PWR Owners Group (PWROG)
  10. Idaho National Lab. (INL), Idaho Falls, ID (United States)
  11. Rempe and Associates LLC, Idaho Falls, ID (United States)
  12. Electric Power Research Inst. (EPRI), Knovville, TN (United States)
Publication Date:
OSTI Identifier:
1179777
Report Number(s):
ANL/NE--15/4
79578; TRN: US1500885
DOE Contract Number:
AC02-06CH11357
Resource Type:
Technical Report
Research Org:
Argonne National Laboratory (ANL), Argonne, IL (United States)
Sponsoring Org:
USDOE Office of Nuclear Energy (NE)
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; REACTOR SAFETY; REACTOR ACCIDENTS; WATER MODERATED REACTORS; EVALUATION; WATER COOLED REACTORS; INFORMATION NEEDS; FUKUSHIMA ACCIDENT ARCHIVE; REACTOR COMPONENTS; TOLERANCE