An inter-comparison between ENDF/B-VIII.0-NECP-Atlas and ENDF/B-VIII.0-NJOY results for criticality safety benchmarks and benchmarks on the reactivity temperature coefficient
Since the nuclear data forms a vital component in reactor physics computations, the nuclear community needs processing codes as tools for translating the Evaluated Nuclear Data Files (ENDF) to simulate nuclear-related problems such as an ACE format that is used for MCNP. Errors, inaccuracies or disc...
Main Authors: | Ouadie Kabach, Abdelouahed Chetaine, Abdelfettah Benchrif, Hamid Amsil |
---|---|
Format: | Article |
Language: | English |
Published: |
Elsevier
2021-08-01
|
Series: | Nuclear Engineering and Technology |
Subjects: | |
Online Access: | http://www.sciencedirect.com/science/article/pii/S1738573321001029 |
Similar Items
-
Neutronic Characteristics of ENDF/B-VIII.0 Compared to ENDF/B-VII.1 for Light-Water Reactor Analysis
by: Kang-Seog Kim, et al.
Published: (2021-09-01) -
Verification of CENDL-3.2 and ENDF/B-VIII.0 Evaluated Nuclear Data Library on HTR-10 Benchmark
by: Tianyi Huang, et al.
Published: (2022-01-01) -
GENERATION AND INITIAL VALIDATION OF A NEW CASMO5 ENDF/B-VIII.0 NUCLEAR DATA LIBRARY
by: Ferrer Rodolfo, et al.
Published: (2021-01-01) -
Interpretation of two SINBAD photon-leakage benchmarks with nuclear library ENDF/B-VIII.0 and Monte Carlo code MCS
by: Matthieu Lemaire, et al.
Published: (2020-07-01) -
Study of MOX-fueled VVER-1000 pin cell using ν-TRAC with ENDF/B-VIII.0 library
by: Anmol Singh, et al.
Published: (2024-05-01)