The role of the PIRT process in experiments, code development and code applications associated with reactor safety analysis

Author:

Wilson Gary E.,Boyack Brent E.

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference17 articles.

1. Boyack, B.E., 1995. AP600 LBLOCA phenomena identification and ranking tabulation. LA-UR-95-2718, Los Alamos National Laboratory, (distribution at the discretion of the USNRC).

2. Glaeser, H., Hofer, E., Kloos, M., Skorek, T., 1993. Uncertainty and sensitivity analysis of a post-experiment calculation in thermal hydraulics. SMIRT-12, Post Conf. Sem. No. 15, Heidelberg, Germany.

3. Development of a PIRT for a postulated double-ended guillotine break in a production reactor;Hanson;Nucl. Eng. Des.,1992

4. Hoffer, E., 1990. The GRS programme package for uncertainty and sensitivity analysis. Proc. Sem. on Methods and Codes for Assessing the Off-Site Consequences of Nuclear Accidents. EUR 13013, Commission of the European Communities, Athens, Greece.

5. Holmstrom, H., Glaeser, H., Wickett, A., Wilson, G., 1994. Status of code uncertainty evaluation methodologies, Proc. Int. Conf. on New Trends in Nuclear System Thermohydraulics. Pisa, Italy.

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