Probability distribution of ex-vessel steam explosion loads considering influences of water level and trigger timing-Reference-Cited by-同舟云学术

Probability distribution of ex-vessel steam explosion loads considering influences of water level and trigger timing

Published:2015-11 Issue: Volume:293 Page:292-303
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Moriyama Kiyofumi,Park Hyun Sun

Funder

Korean government's Nuclear Safety and Security Commission

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

Reference26 articles.

1. The plant-specific uncertainty analysis for an ex-vessel steam explosion-induced pressure load using a TEXAS-SAUNA coupled system;Ahn;Nucl. Eng. Des.,2012

2. FARO test L-14 on fuel-coolant interaction and quenching- comparison report, volume I: Analysis of the results - OECD/CSNI international standard problem 39. NEA/CSNI/R(97)31/Part I, OECD/NEA/CSNI;Annunziato,1998

3. Applied Multiple Regression/Correlation Analysis for the Behavioral Sciences;Cohen,2003

4. Fuel fragmentation model advances using TEXAS-V.;Corradini,1997

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3. Analysis of the dynamic pressure from ex-vessel steam explosion for pressurized water reactor;Progress in Nuclear Energy;2017-09

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