Best estimate plus uncertainty analysis of small break loss of coolant accidents with different break sizes for CPR1000-Reference-Cited by-同舟云学术

Best estimate plus uncertainty analysis of small break loss of coolant accidents with different break sizes for CPR1000

Published:2020-04 Issue: Volume:138 Page:107228
ISSN:0306-4549
Container-title:Annals of Nuclear Energy
language:en
Short-container-title:Annals of Nuclear Energy

Author:

Xiong Qingwen^ORCID,Gou Junli^ORCID,Shan Jianqiang

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference22 articles.

1. A comparative review of sensitivity and uncertainty analysis of large-scale systems—II: statistical methods;Cacuci;Nucl. Sci. Eng.,2004

2. Study on the algorithm for solving two-fluid seven-equation two-pressure model;Chao;Ann. Nucl. Energy,2018

3. Best-estimate calculation plus uncertainty analysis of SBLOCA transient for the scale-down passive test facility;Deng;Prog. Nucl. Energy,2019

4. Uncertainty and sensitivity analysis of a post-experiment calculation in thermal hydraulics;Glaeser;Reliab. Eng. Syst. Saf.,1994

5. IAEA, 2009. Deterministic Safety Analysis for Nuclear Power Plants, International Atomic Energy Agency, Vienna, IAEA Specific Safety Guide No. SSG-2.

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