A fission matrix based validation protocol for computed power distributions in the advanced test reactor-Reference-Cited by-同舟云学术

A fission matrix based validation protocol for computed power distributions in the advanced test reactor

Published:2015-12 Issue: Volume:295 Page:615-624
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Nielsen Joseph W.,Nigg David W.,LaPorta Anthony W.

Funder

U.S. Department of Energy

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.

1. Standard guide for application of neutron spectrum adjustment methods in reactor surveillance;ASTM (American Society for Testing and Materials),2008

2. Sensitivity- and uncertainty-based criticality safety validation techniques;Broadhead;Nucl. Sci. Eng.,2004

3. Fission matrix capability for MCNP Monte Carlo;Carney;Trans. Am. Nucl. Soc.,2012

4. Source convergence in Monte Carlo calculations;Carter;Nucl. Sci. Eng.,1969

5. Advancements in generalized-geometry discrete ordinates transport for lattice physics calculations;DeHart,2006

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