TY - JOUR
T1 - Feasibility study on the core design of high-flux fast neutron research reactors
AU - Zhao, Miao
AU - Du, Xianan
AU - Zheng, Youqi
AU - Wu, Mingyu
AU - Yang, Rui
AU - Xu, Li
AU - Cao, Liangzhi
AU - Wu, Hongchun
N1 - Publisher Copyright:
© 2025 Korean Nuclear Society, Published by Elsevier Korea LLC. All rights are reserved, including those for text and data mining, AI training, and similar technologies. This is an open access article under the CC BY-NC-ND license. http://creativecommons.org/licenses/by-nc-nd/4.0/
PY - 2026/1
Y1 - 2026/1
N2 - The primary functions of research reactors include material irradiation experiments, isotope production, and the generation of neutron beam current. Generally, the higher the neutron flux level, the more favorable it is for material irradiation experiments and isotope production. To study the correlation between various core physical parameters on the neutron flux level of high-flux research reactor (HFR) cores, it is necessary to carry out a feasibility study on the core design of HFRs. In this paper, based on the NECP-MCX code and the SARAX code, the physical parameters of a high-flux fast neutron research reactor core are adjusted, evaluated, and analyzed from the neutronics point of view. Then, some qualitative conclusions that are conducive to improving the maximum total neutron flux in the core are summarized and ultimately applied. Finally, the safety aspects of some core designs in this paper are examined.
AB - The primary functions of research reactors include material irradiation experiments, isotope production, and the generation of neutron beam current. Generally, the higher the neutron flux level, the more favorable it is for material irradiation experiments and isotope production. To study the correlation between various core physical parameters on the neutron flux level of high-flux research reactor (HFR) cores, it is necessary to carry out a feasibility study on the core design of HFRs. In this paper, based on the NECP-MCX code and the SARAX code, the physical parameters of a high-flux fast neutron research reactor core are adjusted, evaluated, and analyzed from the neutronics point of view. Then, some qualitative conclusions that are conducive to improving the maximum total neutron flux in the core are summarized and ultimately applied. Finally, the safety aspects of some core designs in this paper are examined.
KW - High-flux fast neutron research reactor
KW - NECP-MCX
KW - Neutron flux
KW - Parameter adjustment
KW - SARAX
UR - https://www.scopus.com/pages/publications/105030397241
U2 - 10.1016/j.net.2025.103909
DO - 10.1016/j.net.2025.103909
M3 - 文章
AN - SCOPUS:105030397241
SN - 1738-5733
VL - 58
JO - Nuclear Engineering and Technology
JF - Nuclear Engineering and Technology
IS - 1
M1 - 103909
ER -