Comprehensive stainless steel neutron transport libraries validation

Author:

Schulc Martin,Košťál Michal,Czakoj Tomáš,Šimon Jan,Novák Evžen,Matěj Zdeněk

Funder

Ministerstvo Vnitra České Republiky

Ministerstvo Školství, Mládeže a Tělovýchovy

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference17 articles.

1. ENDF/B-VIII.0.0: The 8th major release of the nuclear reaction data library with CIELO-project cross sections, new standards and thermal scattering data;Brown;Nucl. Data Sheets,2018

2. INDEN - International Network of Nuclear Data Evaluators;Capote,2022

3. ENDF/B-VII.1: nuclear data for science and technology: cross sections, covariances, fission product yields and decay data;Chadwick;Nucl. Data Sheets,2011

4. Maximum likelihood estimation of a neutron spectrum and associated uncertainties Adv;Cvachovec;Mil. Technol.,2008

5. The updated version of Chinese Evaluated Nuclear Data Library (CENDL-3.1);Ge,2010

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