SARAX: A new code for fast reactor analysis part II: Verification, validation and uncertainty quantification-Reference-Cited by-同舟云学术

SARAX: A new code for fast reactor analysis part II: Verification, validation and uncertainty quantification

Published:2018-05 Issue: Volume:331 Page:41-53
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Zheng Youqi^ORCID,Qiao Liang,Zhai Zi'an,Du Xianan,Xu Zhitao

Funder

National Natural Science Foundation of China

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

Reference21 articles.

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2. Benchmark problem book. ANL-7416;Argonne Code Center,1968

3. Du, X.N., Cao, L.Z., Zheng, Y.Q., et al., Developments of the sodium fast reactor analysis code SARAX: methods and verification. In: Proceeding of M&C2017, April 16–20, 2017 2017 Jeju Korea.

4. BN-600 Hybrid Core Benchmark Analyses, IAEA-TECDOC-1623;IAEA,2010

5. BN-600 MOX Core Benchmark Analyses, IAEA-TECDOC-1700;IAEA,2013

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