U233 Data Evaluation for Criticality Study
Author:
Affiliation:
1. Jordan Research and Training Reactor, Shafa Badran, P.O Box: 70, Amman, Jordan e-mail: ;
2. Department of Engineering Physics, Tsinghua University, Beijing 100084, China e-mail:
Abstract
Publisher
ASME International
Subject
Nuclear Energy and Engineering,Radiation
Link
http://asmedigitalcollection.asme.org/nuclearengineering/article-pdf/doi/10.1115/1.4032814/6067351/ners_2_3_034501.pdf
Reference12 articles.
1. Development of a Code FITWR for Nuclear Cross Section Statistical Analysis;Ann. Nucl. Energy,2014
2. Nuclear Cross Section Statistical Analysis With FITWR Program;Energy Dev. Front.
3. Updated Users’ Guide for Sammy: Multilevel r-Matrix Fits to Neutron Data Using Bayes’ Equations,1984
4. ENDF-201: ENDF/B-VI Summary Documentation,1991
5. A Suite of Criticality Benchmarks for Validating Nuclear Data,1999
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