ADVANTG hybrid code application for the analysis of neutron field depression in uranium foils activated in the MARK III converter of the BR1 reactor-Reference-Cited by-同舟云学术

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ADVANTG hybrid code application for the analysis of neutron field depression in uranium foils activated in the MARK III converter of the BR1 reactor

Published:2020-02 Issue: Volume:357 Page:110384
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Çelik Yurdunaz,Malambu Edouard,Van den Eynde Gert^ORCID,Krása Antonín,Wagemans Jan

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

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

4. Complete thermal and epithermal neutron self-shielding corrections for NAA using a spreadsheet;Chilian;J. Radioanal. Nucl. Chem.,2008

5. Review of the natC(n, γ) cross section and criticality calculations of the graphite moderated reactor BR1;Diez;Ann. Nucl. Energy,2013

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