Feasibility study on the core design of high-flux fast neutron research reactors

IF 2.6 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Miao Zhao , Xianan Du , Youqi Zheng , Mingyu Wu , Rui Yang , Li Xu , Liangzhi Cao , Hongchun Wu
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引用次数: 0

Abstract

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.
高通量快中子研究堆堆芯设计可行性研究
研究堆的主要功能包括物质辐照实验、同位素生产和中子束电流的产生。一般来说,中子通量水平越高,越有利于物质辐照实验和同位素生产。为了研究高通量研究堆堆芯各物理参数与中子通量水平之间的相关性,有必要对高通量研究堆堆芯设计进行可行性研究。本文基于NECP-MCX代码和SARAX代码,从中子学的角度对高通量快中子研究堆堆芯的物理参数进行了调整、评价和分析。然后总结了一些有助于提高堆芯最大总中子通量的定性结论,并最终加以应用。最后,对部分核心设计的安全性进行了分析。
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来源期刊
Nuclear Engineering and Technology
Nuclear Engineering and Technology 工程技术-核科学技术
CiteScore
4.80
自引率
7.40%
发文量
431
审稿时长
3.5 months
期刊介绍: Nuclear Engineering and Technology (NET), an international journal of the Korean Nuclear Society (KNS), publishes peer-reviewed papers on original research, ideas and developments in all areas of the field of nuclear science and technology. NET bimonthly publishes original articles, reviews, and technical notes. The journal is listed in the Science Citation Index Expanded (SCIE) of Thomson Reuters. NET covers all fields for peaceful utilization of nuclear energy and radiation as follows: 1) Reactor Physics 2) Thermal Hydraulics 3) Nuclear Safety 4) Nuclear I&C 5) Nuclear Physics, Fusion, and Laser Technology 6) Nuclear Fuel Cycle and Radioactive Waste Management 7) Nuclear Fuel and Reactor Materials 8) Radiation Application 9) Radiation Protection 10) Nuclear Structural Analysis and Plant Management & Maintenance 11) Nuclear Policy, Economics, and Human Resource Development
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