Uncertainty analysis in Monte Carlo criticality computations-Reference-Cited by-同舟云学术

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Uncertainty analysis in Monte Carlo criticality computations

Published:2011-12 Issue:12 Volume:241 Page:4697-4703
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Ao Qi

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

Reference23 articles.

1. Validation of Neutron Transport Methods for Nuclear Criticality Safety Calculations. ANS/ANSI-8.24-2007;ANS,2007

2. A statistical methodology for validating criticality analysis codes;Ao,2007

3. USLSA – a statistical tool for criticality analysis code validation;Ao;Trans. Am. Nucl. Soc.,2007

4. keff uncertainty due to uncertainties in non-isotopic parameters of fissionable systems;Ao,2009

5. Uncertainty analysis in nuclear criticality safety computations;Ao,2010

Cited by 2 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Performance evaluation and validation of OpenMC code for criticality analysis of an MTR-type research reactor;Annals of Nuclear Energy;2024-10

2. Propagation of Uncertainty in System Parameters of a LWR Model by Sampling MCNPX Calculations – Burnup Analysis;SNA + MC 2013 - Joint International Conference on Supercomputing in Nuclear Applications + Monte Carlo;2014

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