Monte Carlo Simulation of Neutronic Characteristics of the Yalina-Thermal Subcritical Assembly Using the ENDF/B-VII and JENDL-3.2 Evaluated Neutron Data Libraries
- 作者: Beresneva V.A.1, Korbut T.N.1, Korneyev S.V.1
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隶属关系:
- Joint Institute for Power and Nuclear Research—Sosny
- 期: 卷 81, 编号 10 (2018)
- 页面: 1441-1449
- 栏目: Mathematical Modeling in Nuclear Technologies
- URL: https://journal-vniispk.ru/1063-7788/article/view/193917
- DOI: https://doi.org/10.1134/S1063778818100010
- ID: 193917
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详细
The results of the numerical simulation of an experiment on the Yalina-Thermal subcritical assembly with 10% enriched fuel conducted for the determination of the fast neutron spectrum in the core volume of the subcritical assembly are presented. The work was carried out using the MCNP4B radiation transport calculation code, the ENDF/B-VII and JENDL-3.2 evaluated nuclear data libraries, and the SAND-II neutron spectrum unfolding code. The neutron spectra calculated using MCNP4B and the neutron spectra unfolded using SAND-II agree well, which proves that the SAND-II code is correct and can be used to unfold spectra from the experimental data of reaction rates with use of the Monte Carlo spectrum as a reference.
作者简介
V. Beresneva
Joint Institute for Power and Nuclear Research—Sosny
编辑信件的主要联系方式.
Email: vaberesneva93@gmail.com
白俄罗斯, Minsk, 220109
T. Korbut
Joint Institute for Power and Nuclear Research—Sosny
Email: vaberesneva93@gmail.com
白俄罗斯, Minsk, 220109
S. Korneyev
Joint Institute for Power and Nuclear Research—Sosny
Email: vaberesneva93@gmail.com
白俄罗斯, Minsk, 220109
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