Thermal–hydraulics system codes uncertainty assessment: A review of the methodologies

Author:

Pourgol-Mohammad Mohammad

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference46 articles.

1. Uncertainty characterization of data for probabilistic risk assessment;Bari;Reliability Engineering and System Safety,1989

2. Quantifying reactor safety margins part 1: an overview of the code scaling, applicability, and uncertainty evaluation methodology;Boyack;Nuclear Engineering and Design,1990

3. Boyack, B.E., et al., 2001. Phenomenon Identification and Ranking Tables (PIRTs) for Loss-of-Coolant Accidents in Pressurized and Boiling Water Reactors Containing High Burnup Fuel. NUREG/CR-6744 LA-UR-00-5079, 2001.

4. 10 CFR Part 50, (2003), Licensing Requirements for the Independent Storage of Spent Nuclear Fuel and High-Level Radioactive Waste. US Government Printing Office, Washington, DC.

5. Chang, Y.H., Almenas, K., Pourgol-Mohamad, M., Mosleh, A., 2006. Thermal–Hydraulics Uncertainty Assessment Relative to PTS for Oconee Nuclear Power Plant. Prepared in Center for Technology Risk Studies, University of Maryland, Report to USNRC.

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