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Title: Progress in reliability of fast reactor operation and new trends to increased inherent safety

The reasons for the renewed interest in fast reactors and an overview of the progress in sodium cooled fast reactor operation in the last ten years are given. The excellent operational performance of sodium cooled fast reactors in this period is highlighted as a sound basis for the development of new fast reactors. The operational performance of the BN-600 is compared and evaluated against the performance of German light water reactors to assess the reliability. The relevance of feedback effects for safe reactor design is described, and a new method for the enhancement of feedback effects in fast reactors is proposed. Experimental reactors demonstrating the inherent safety of advanced sodium cooled fast reactor designs are described and the potential safety improvements resulting from the use of fine distributed moderating material are discussed.
Authors:
 [1] ;  [2] ;  [3] ;  [4]
  1. Helmholtz-Zentrum Dresden-Rossendorf (HZDR), (Germany). Inst. for Resource Ecology
  2. Idaho National Lab. (INL), Idaho Falls, ID (United States)
  3. Indira Gandhi Centre for Atomic Research (IGCAR), Kalpakkam (India). Nuclear Science and Engineering Group
  4. Argonne National Lab. (ANL), Argonne, IL (United States)
Publication Date:
OSTI Identifier:
1188618
Report Number(s):
INL/JOU--15-35650
Journal ID: ISSN 0306-2619; TRN: US1500208
DOE Contract Number:
AC07-05ID14517
Resource Type:
Journal Article
Resource Relation:
Journal Name: Applied Energy; Journal Volume: 147; Journal Issue: C
Publisher:
Elsevier
Research Org:
Idaho National Laboratory (INL), Idaho Falls, ID (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; FAST REACTORS; SODIUM COOLED REACTORS; WATER MODERATED REACTORS; REACTOR SAFETY; BELOYARSK-3 REACTOR; EXPERIMENTAL REACTORS; OPERATION; PERFORMANCE; RELIABILITY; WATER COOLED REACTORS; COMPARATIVE EVALUATIONS; DESIGN; FEEDBACK; MODERATORS NUCLEAR; NUCLEAR REACTORS; ENHANCED FEEDBACK; INHERENT SAFETY