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Deterministic and risk-informed approaches for safety analysis of advanced reactors: Part II, Risk-informed approaches

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  • Kim, Inn Seock
  • Ahn, Sang Kyu
  • Oh, Kyu Myung

Abstract

Technical insights and findings from a critical review of deterministic approaches typically applied to ensure design safety of nuclear power plants were presented in the companion paper of Part I included in this issue. In this paper we discuss the risk-informed approaches that have been proposed to make a safety case for advanced reactors including Generation-IV reactors such as Modular High-Temperature Gas-cooled Reactor (MHTGR), Pebble Bed Modular Reactor (PBMR), or Sodium-cooled Fast Reactor (SFR). Also considered herein are a risk-informed safety analysis approach suggested by Westinghouse as a means to improve the conventional accident analysis, together with the Technology Neutral Framework recently developed by the US Nuclear Regulatory Commission as a high-level regulatory infrastructure for safety evaluation of any type of reactor design. The insights from a comparative review of various deterministic and risk-informed approaches could be usefully used in developing a new licensing architecture for enhanced safety of evolutionary or advanced plants.

Suggested Citation

  • Kim, Inn Seock & Ahn, Sang Kyu & Oh, Kyu Myung, 2010. "Deterministic and risk-informed approaches for safety analysis of advanced reactors: Part II, Risk-informed approaches," Reliability Engineering and System Safety, Elsevier, vol. 95(5), pages 459-468.
    • Handle: RePEc:eee:reensy:v:95:y:2010:i:5:p:459-468
    DOI: 10.1016/j.ress.2009.12.004
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    Cited by:

    1. Queral, Cesar & Fernández-Cosials, Kevin & Zugazagoitia, Eneko & Paris, Carlos & Magan, Javier & Mendizabal, Rafael & Posada, Jose, 2021. "Application of Expanded Event Trees combined with uncertainty analysis methodologies," Reliability Engineering and System Safety, Elsevier, vol. 205(C).
    2. Kowal, Karol & Torabi, Mina, 2021. "Failure mode and reliability study for Electrical Facility of the High Temperature Engineering Test Reactor," Reliability Engineering and System Safety, Elsevier, vol. 210(C).

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