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Title: Performance-based ECCS cladding acceptance criteria: A new simulation approach

The U. S. Nuclear Regulatory Commission is currently proposing rulemaking to revise the Loss Of Coolant Accident (LOCA) and therefore the Emergency Core Cooling System (ECCS) acceptance criteria, to include the effects of higher burnup on cladding performance as well as to address other technical issues. As motivated by the new rule, the need to use advanced cladding designs may be a result. A loss of operational margin may result due to the more restrictive cladding embrittlement criteria. Initial and future compliance with the rule may significantly increase vendor workload and licensee cost, as a spectrum of fuel rod initial burnup states may need to be analyzed to demonstrate compliance. Consequently, there will be an increased focus on licensee decision making related to LOCA analysis to minimize cost and impact, and to manage margin. The study here presented has been part of a big project used to investigate technical issues and approaches for future industrial applications within the Risk-Informed Safety Margin Characterization (RISMC) Pathway. Specifically, the primary aim of this study is to lay out a roadmap to demonstrate the application of the new methodology. Furthermore, the present analysis shows a simplified version of the methodology of an industrial applicationmore » on the Core Design and the Multi-Cycle Analysis.« less
Authors:
 [1] ;  [2] ;  [2] ;  [2] ;  [1] ;  [1]
  1. Univ. of Rome, Rome (Italy)
  2. Idaho National Lab. (INL), Idaho Falls, ID (United States)
Publication Date:
Report Number(s):
INL/JOU-16-40078
Journal ID: ISSN 0306-4549; PII: S0306454916308544
Grant/Contract Number:
AC07-05ID14517
Type:
Accepted Manuscript
Journal Name:
Annals of Nuclear Energy (Oxford)
Additional Journal Information:
Journal Name: Annals of Nuclear Energy (Oxford); Journal Volume: 100; Journal Issue: P2; Journal ID: ISSN 0306-4549
Publisher:
Elsevier
Research Org:
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Sponsoring Org:
USDOE Office of Nuclear Energy (NE)
Country of Publication:
United States
Language:
English
Subject:
97 MATHEMATICS AND COMPUTING; 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; 42 ENGINEERING; 99 GENERAL AND MISCELLANEOUS; Burn Up; CORE DESIGN; Depletion; PHISICS; Reactor Physics; Reactor Physics Method; RISMC; LOCA; ECCS; Acceptance criteria; Cladding design; RAVEN; RELAP5-3D
OSTI Identifier:
1402461
Alternate Identifier(s):
OSTI ID: 1410731