OpenMC interpretation and analysis of two series highly-enriched-uranium thermal-spectrum benchmarks for nuclear data validation

A comparative study on k-infinity uncertainty due to cross-section covariance data in nuclear data libraries

(2023) Tatsuya Fujita   JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY

Verification of OpenMC for fast reactor physics analysis with China experimental fast reactor start-up tests

(2022) Hui Guo et al.   Nuclear Engineering and Technology

Beryllium oxide utilized in nuclear reactors: Part I: Application history, thermal properties, mechanical properties, corrosion behavior and fabrication methods

(2022) Ming-dong Hou et al.   Nuclear Engineering and Technology

Recent studies on potential accident-tolerant fuel-cladding systems in light water reactors

(2020) Sheng-Li Chen et al.   Nuclear Science and Techniques

The joint evaluated fission and fusion nuclear data library, JEFF-3.3

(2020) A. J. M. Plompen et al.   EUROPEAN PHYSICAL JOURNAL A

TENDL: Complete Nuclear Data Library for Innovative Nuclear Science and Technology

(2019) A.J. Koning et al.   NUCLEAR DATA SHEETS

Processing of JEFF-3.3 and ENDF/B-VIII.0 and testing with critical benchmark experiments and TRIGA Mark II research reactor using MCNPX

(2019) Ouadie Kabach et al.   APPLIED RADIATION AND ISOTOPES

Validation study of the reactor physics lattice transport code DRAGON5 & the Monte Carlo code OpenMC by critical experiments of light water reactors

(2019) H. El Yaakoubi et al.   JOURNAL OF KING SAUD UNIVERSITY SCIENCE

Evaluation of the Neutron Data Standards

(2018) A.D. Carlson et al.   NUCLEAR DATA SHEETS

ENDF/B-VIII.0: The 8 th Major Release of the Nuclear Reaction Data Library with CIELO-project Cross Sections, New Standards and Thermal Scattering Data

(2018) D.A. Brown et al.   NUCLEAR DATA SHEETS

IAEA CIELO Evaluation of Neutron-induced Reactions on 235 U and 238 U Targets

(2018) R. Capote et al.   NUCLEAR DATA SHEETS

NECP-Atlas: A new nuclear data processing code

(2018) Tiejun Zu et al.   ANNALS OF NUCLEAR ENERGY

RMC – A Monte Carlo code for reactor core analysis

(2015) Kan Wang et al.   ANNALS OF NUCLEAR ENERGY

TRIPOLI-4®, CEA, EDF and AREVA reference Monte Carlo code

(2015) E. Brun et al.   ANNALS OF NUCLEAR ENERGY

OpenMC: A state-of-the-art Monte Carlo code for research and development

(2015) Paul K. Romano et al.   ANNALS OF NUCLEAR ENERGY

JENDL-4.0: A New Library for Nuclear Science and Engineering

(2012) Keiichi SHIBATA et al.   JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY

ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and Decay Data

(2011) M.B. Chadwick et al.   NUCLEAR DATA SHEETS