Comparison of ENDF/B-VIII.0 and ENDF/B-VII.1 in criticality, depletion benchmark, and uncertainty analyses by McCARD

Author:

Park Ho JinORCID,Kang Hyunwook,Lee Hyun ChulORCID,Cho Jin Young

Funder

NRF

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference20 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. CIELO collaboration: neutron reactions on 1H, 16O, 56Fe, 235U, 238U, and 239Pu;Chadwick;Nucl. Data Sheets,2014

3. JENDL-4.0 benchmarking for fission reactor applications;Chiba;J. Nucl. Sci. Technol.,2011

4. International Handbook of Evaluated Criticality Safety Benchmark Experiments, NEA/NSC/DOC(95)03, OECD Nuclear Energy (2006).

5. Benchmark for Uncertainty Analysis in Modeling (UAM) for Design, Operation and Safety Analysis of LWRs, Volume I: Specification and Support Data for the Neutronics Cases (Phase I);Ivanov,2012

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