Consistent evaluation of modern nuclear data libraries for criticality safety analyses of thermal compound low-enriched-uranium systems

Author:

Kolbe Edwin,Vasiliev Alexander,Ferroukhi Hakim,Zimmermann Martin A.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference20 articles.

1. ANSI/ANS-8.1-1998;R2007, 1998. Nuclear Criticality Safety in Operations with Fissionable Materials Outside Reactors. American Nuclear Society, La Grange Park, Illinois.

2. ANSI/ANS-8.24-2007, 2007. Validation of Neutron Transport Methods for Nuclear Criticality Safety Calculations. American Nuclear Society, La Grange Park, Illinois.

3. ENDF/B-VII.0: next generation evaluated nuclear data library for nuclear science and technology;Chadwick;Nuclear Data Sheets,2006

4. Statistical Intervals: A Guide for Practitioners;Hahn,1991

5. Hendricks, J.S., et al., 2005. MCNPX EXTENSIONS, VERSION 2.5.0. Technical Report LA-UR-05-2675, Los Alamos National Laboratory.

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