On the performance of ENDF/B-VII.0 data for fast neutron fluence calculations

Author:

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

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference13 articles.

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

2. Calculation and benchmarking of an azimuthal pressure vessel neutron fluence distribution using the BOXER code and scraping experiments;Holzgrewe;Nucl. Technol.,1995

3. OECD/NEA Data Bank Computer Program Services, 2003. ZZ FSXLIBJ33, MCNP Nuclear Data Library Based on JENDL-3.3, NEA-1424/04. Abstract available from: .

4. OECD/NEA Data Bank Computer Program Services, 2004. ZZ MCB-ENDF/B6.8, MCB Continuous-Energy Neutron Cross-section Libraries for Temperatures from 300 to 1800K, NEA-1669/03. Abstract available from: .

5. OECD/NEA Data Bank Computer Program Services, 2007a. ZZ MCJEFF3.1NEA, MCNP Neutron Cross Section Library based on JEFF3.1. Abstract available from: .

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