Requirement Analysis on Ultra-high Flux Fast Neutron Research Reactors

Liao Wei; Xia Bangyang; Yu Hongxing; Li Wenjie; Mu Keliang; Zhang Fengshou

doi:10.13832/j.jnpe.2022.06.0222

Volume 43 Issue 6

Dec. 2022

Turn off MathJax

Article Contents

Article Navigation > Nuclear Power Engineering > 2022 > 43(6): 222-226

Liao Wei, Xia Bangyang, Yu Hongxing, Li Wenjie, Mu Keliang, Zhang Fengshou. Requirement Analysis on Ultra-high Flux Fast Neutron Research Reactors[J]. Nuclear Power Engineering, 2022, 43(6): 222-226. doi: 10.13832/j.jnpe.2022.06.0222

Citation:

Liao Wei, Xia Bangyang, Yu Hongxing, Li Wenjie, Mu Keliang, Zhang Fengshou. Requirement Analysis on Ultra-high Flux Fast Neutron Research Reactors[J]. Nuclear Power Engineering, 2022, 43(6): 222-226. doi: 10.13832/j.jnpe.2022.06.0222

Citation:

PDF( 2022 KB)

Requirement Analysis on Ultra-high Flux Fast Neutron Research Reactors

doi: 10.13832/j.jnpe.2022.06.0222

1.
Nuclear Power Institute of China, Chengdu, 610213, China
2.
Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, 610213, China

Received Date: 2022-07-17
Rev Recd Date: 2022-08-01
Publish Date: 2022-12-14

Abstract

Abstract

Achieving the ultra-high fast neutron flux is an important development direction of the world's advanced research reactors, which is of great significance for accelerating the innovative development of fuels and materials for the fourth generation advanced nuclear power system. From the aspects of the irradiation test of structural materials and nuclear fuels in advanced nuclear reactor and the production of long-reaction-chain transplutonium element, this paper preliminarily analyzes the necessity of building ultra-high flux fast neutron research reactor in China. On this basis, the core maximum neutron fluence rate and its coolant of the ultra-high flux fast neutron research reactor are determined, and the main parameters of the reactor and the coolant flow scheme are given as follows: the thermal power of the reactor is 200MW, the coolant is lead-bismuth alloy, and the maximum neutron fluence rate is more than 10¹⁶ cm⁻²·s⁻¹.
- Ultra high neutron flux,
- Fast neutron research reactor,
- Requirement analysis

FullText(HTML)

References(13)

References

[1]	IAEA. The applications of research reactors: IAEA-TECDOC-1234[R]. Vienna: IAEA, 2001.
[2]	王昆鹏,张春明,攸国顺,等. 全球研究堆的主要用途及发展趋势研究[J]. 核科学与工程,2015, 35(3): 413-418. doi: 10.3969/j.issn.0258-0918.2015.03.003
[3]	张禄庆. 国外研究堆发展趋向[J]. 核动力工程,1988, 9(2): 35-40.
[4]	LANE J A. Ultra high flux research reactors: 58-7-117[R]. Oak Ridge: Oak Ridge National Laboratory, 1958.
[5]	IZHUTOV A L, KRASHENINNIKOV Y M, ZHEMKOV I Y, et al. Prolongation of the BOR-60 reactor operation[J]. Nuclear Engineering and Technology, 2015, 47(3): 253-259. doi: 10.1016/j.net.2015.03.002
[6]	PIORO I L. Handbook of generation IV nuclear reactors[M]. Duxford: Woodhead Publishing, 2016: 37-52.
[7]	ELISEEV V A, KOROBEYNIKOVA L V, MASLOV P A, et al. On feasibility of using nitride and metallic fuel in the MBIR reactor core[J]. Nuclear Energy and Technology, 2016, 2(3): 179-182. doi: 10.1016/j.nucet.2016.07.009
[8]	GERSTNER D, ANDRUS J P, BUCKNOR M. ANS summary of safety design strategy for the versatile test reactor: INL/CON-19-54662-Revision-0[R]. Idaho Falls: Idaho National Laboratory, 2019.
[9]	GOUGAR H D, SHARP M T. Versatile irradiation test reactor user needs assessment: INL/MIS-16-40582[R]. Idaho Falls: Idaho National Laboratory, 2017.
[10]	ABDERRAHIM H A, BAETEN P, DE BRUYN D, et al. MYRRHA-A multi-purpose fast spectrum research reactor[J]. Energy Conversion and Management, 2012, 63: 4-10. doi: 10.1016/j.enconman.2012.02.025
[11]	PETTI D, HILL R, GEHIN J, et al. A summary of the department of energy's advanced demonstration and test reactor options study[J]. Nuclear Technology, 2017, 199(2): 111-128.
[12]	VORONIN V I, BERGER I F, PROSKURNINA N V, et al. Neutron diffraction study of structure and phase composition of fuel claddings made of cold-deformed steel ChS68 after normal operation in BN-600 reactor[J]. Journal of Nuclear Materials, 2018, 509: 218-224. doi: 10.1016/j.jnucmat.2018.06.036
[13]	NORGETT M J, ROBINSON M T, TORRENS I M. A proposed method of calculating displacement dose rates[J]. Nuclear Engineering and Design, 1975, 33(1): 50-54. doi: 10.1016/0029-5493(75)90035-7