References
- D.A. Brown, M.B. Chadwick, R. Capote, et al., 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, Nucl. Data Sheets 148 (2018) 1-142. https://doi.org/10.1016/j.nds.2018.02.001
- A. Plompen, Announcing JEFF-3.3 Release, JEF/DOC, 2017, p. 1864.
- K. Shibata, O.I. wamoto, T. Nakagawa, et al., JENDL-4.0: a new library for nuclear science and engineering, Nucl. Sci. Technol. 48 (2011) 1-30. https://doi.org/10.1080/18811248.2011.9711675
- Z.G. Ge, Z.X. Zhao, H.H. Xia, et al., The updated version of Chinese evaluated nuclear data library (CENDL-3.1), J. Kor. Phys. Soc. 59 (2011).
- A.I. Blokhin, E.V. Gai, A.V. Ignatyuk, et al., Problems of atomic science and technology, Series: Nucl. React. Constants 2 (2) (2016) 5.
- D.G. Cacuci, Handbook of Nuclear Engineering, Springer, US, 2010.
- O. Cabellos, F. Alvarez-Velarde, M. Angelone, et al., Benchmarking and validation activities within JEFF project, EPJ Web Conf. 146 (2017), 06004.
-
K. Ouadie, C. Abdelouahed, B. Abdelfettah, et al., Processing and benchmarking of evaluated nuclear data file/b-viii.0
${\beta}$ 4 cross-section library by analysis of a series of critical experimental benchmark using the Monte Carlo code MCNP(X) and NJOY2016, Nucl. Eng. Technol. 49 (2017) 1610-1616. https://doi.org/10.1016/j.net.2017.08.017 - K. Ouadie, C. Abdelouahed, B. Abdelfettah, Processing of JEFF-3.3 and ENDF/BVIII. 0 and testing with critical benchmark experiments and TRIGA Mark II research reactor using MCNPX, Appl. Radiat. Isot. 150 (2019) 146-156. https://doi.org/10.1016/j.apradiso.2019.05.015
- T. Goorley, M. James, T. Booth, et al., Features of MCNP6, Ann. Nucl. Energy 87 (2) (2016) 772-783. https://doi.org/10.1016/j.anucene.2015.02.020
- J.S. Hendricks, G.W. McKinney, M.L. Fensin, et al., MCNPX 2.6.0 Extensions, LAUR-08-2216, Los Alamos National Laboratory, April 11, 2008.
- K. Wang K, Z. Li, D. She, et al., RMC - a Monte Carlo code for reactor core analysis, Ann. Nucl. Energy 82 (2015) 121-129. https://doi.org/10.1016/j.anucene.2014.08.048
- National nuclear data center, Available from: https://www.nndc.bnl.gov/endf/b8.0/download.html, 2019.
- Nuclear energy agency, Available from: https://www.oecd-nea.org/dbdata/jeff/jeff33/index.html, 2019.
- R.D. Mosteller, An Expanded Criticality Validation Suite for MCNP, Tech. Rep. LA-UR-10-06230, Los Alamos National Laboratory, 2010.
- M.B. Chadwick, P. Oblozinsky, M. Herman, et al., ENDF/B-VII.0: next generation evaluated nuclear data library for nuclear science and technology, Nucl. Data Sheets 107 (2006) 2931-3060. https://doi.org/10.1016/j.nds.2006.11.001
- M.B. Chadwick, M. Herman, P. Oblozinsk, et al., ENDF/B-VII.1 nuclear data for science and technology: cross sections, covariances, fission product yields and decay data, Nucl. Data Sheets 112 (2011) 2887-2996. https://doi.org/10.1016/j.nds.2011.11.002
- A.J. Koning, D. Rochman, et al., TENDL-2017: TALYS-based evaluated nuclear data library. https://tendl.web.psi.ch/tendl_2017/tendl2017.html, 2017.
- T.E. Booth, F.B. Brown, J.S. Bull, et al., MCNP5 1.50 Release Notes, Tech. Rep. LA-UR-08-2300, Los Alamos National Laboratory, 2008.
- D.K. Parsons, in: NJOY Processing of ENDF/B VIII.0 Thermal Scattering Files, Tech. Rep. LA-UR-18-25096, Los Alamos National Laboratory, 2018.
- L. Zheng, K. Wang K, W. Wang, Continuous thermal neutron scattering data processing capability in RMC code, RPHA19 TPC, in: Proceedings of the 3rd Reactor Physics Asia Conference in 2019 (RPHA19), 2019. KURNS-EKR-5, ISSN 2434-1088, Institute for Integrated Radiation and Nuclear Science, Kyoto University.
- International Handbook of Evaluated Criticality Safety Benchmark Experiments/Nuclear Energy Agency, OECD Nuclear Energy Agency, Paris, 2006.
- Y. Qiu, Z. Li, K. Wang, et al., Research on full core large scale parallism of the code RMC, in: The 14th Chinese Conference on Reactor Numerical Calculations and Particle Transport & 2012 Chinese Conference on Reactor Physics, 2012. Yinchuan, China.
- J.C. Jaboulay, P.Y. Cayla, C. Fausser, et al., TRIPOLI-4 Monte Carlo code ITER Alite neutronic model validation, Fusion Eng. Des. 89 (2014) 2174-2178. https://doi.org/10.1016/j.fusengdes.2014.02.038
- M. Cornock, Benchmarking of ENDF/B-VII.1 and JENDL-4.0 in the fast neutron range, Nucl. Data Sheets 118 (2014) 430-432. https://doi.org/10.1016/j.nds.2014.04.098
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