Researching | Criticality safety analysis of nuclear fuel storage of molten salt reactor

NUCLEAR TECHNIQUES, Volume. 47, Issue 8, 080606(2024)

Criticality safety analysis of nuclear fuel storage of molten salt reactor

Zhen YANG^1,2,3, Zhimin DAI^1、*, Zhangzhong YANG³, and Yang ZOU¹

Author Affiliations

¹Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai 201800, China

²University of Chinese Academy of Sciences, Beijing 100049, China

³North-Western China Regional Office of Nuclear and Radiation Saftety Inspection, National Nuclear Safety Administration, Lanzhou 730020, China

show less

Abstract Get PDF(in Chinese)

Figures&Tables (8)

References (21)

Paper Information

References(21)

[1] Zhao X C, Zou Y, Yan R et al. Analysis of burnup performance and temperature coefficient for a small modular molten-salt reactor started with plutonium[J]. Nuclear Science and Techniques, 34, 17(2023).

[2] HUO Yuting, LUO Yan, XIANG Haifei et al. Study on the condensation behavior of the key metal fluorides in molten salts during low-pressure distillation[J]. Nuclear Techniques, 47, 010301(2024).

[3] ZHOU Tianze, YU Kaicheng, CHENG Maosong et al. Development and analysis of a K-nearest-neighbor-based transient identification model for molten salt reactor systems[J]. Nuclear Techniques, 46, 110604(2023).

[4] CHEN Shichao, LI Rui, ZUO Xiandi et al. Development and validation of real-time modeling and simulation platform for molten salt reactor, based on EPICS framework[J]. Nuclear Techniques, 46, 110601(2023).

[5] Yu S H, Liu Y F, Yang P et al. Neutronics analysis for MSR cell with different fuel salt channel geometries[J]. Nuclear Science and Techniques, 32, 9(2021).

[6] YU Shihe, LIU Yafen, YANG Pu et al. Effect analysis of core structure changes on reactivity in molten salt experimental reactor[J]. Nuclear Techniques, 42, 020603(2019).

[7] Haubenreich P N, Engel J R. Experience with the molten-salt reactor experiment[J]. Nuclear Applications and Technology, 8, 118-136(1970).

[8] Yu G P, Cheng Y F, Zhang N et al. Multi-objective optimization and evaluation of supercritical CO2 Brayton cycle for nuclear power generation[J]. Nuclear Science and Techniques, 35, 22(2024).

[9] He L Y, Cui Y, Chen L et al. Effect of reprocessing on neutrons of a molten chloride salt fast reactor[J]. Nuclear Science and Techniques, 34, 46(2023).

[10] Wulandari C, Waris A, Permana S et al. Evaluating the JEFF 3.1, ENDF/B-VII.0, JENDL 3.3, and JENDL 4.0 nuclear data libraries for a small 100 MWe molten salt reactor with plutonium fuel[J]. Nuclear Science and Techniques, 33, 165(2022).

[11] Li X X, Cui D Y, Ma Y W et al. Influence of 235U enrichment on the moderator temperature coefficient of reactivity in a graphite-moderated molten salt reactor[J]. Nuclear Science and Techniques, 30, 166(2019).

[12] Liu H, Lei G H, Huang H F et al. Review on synergistic damage effect of irradiation and corrosion on reactor structural alloys[J]. Nuclear Science and Techniques, 35, 57(2024).

[13] Sun G M, Cheng M S. Development of a MCNP5 and ORIGEN2 based burnup code for molten salt reactor[J]. Nuclear Science and Techniques, 27, 65(2016).

[14] Zhang Z H, Xia X B, Cai J et al. Simulation of radiation dose distribution and thermal analysis for the bulk shielding of an optimized molten salt reactor[J]. Nuclear Science and Techniques, 26, 040603(2015).

[15] Zhang D, Qiu S, Liu C et al. Steady thermal hydraulic analysis for a molten salt reactor[J]. Nuclear Science and Techniques, 19, 187-192(2008).

[16] Zhu G F, Yan R, Peng H H et al. Application of Monte Carlo method to calculate the effective delayed neutron fraction in molten salt reactor[J]. Nuclear Science and Techniques, 30, 34(2019).

[17] Xu H X, Lin J, Zhong Y J et al. Characterization of molten 2LiF–BeF2 salt impregnated into graphite matrix of fuel elements for thorium molten salt reactor[J]. Nuclear Science and Techniques, 30, 74(2019).

[18] Yu J H, Xu H X, Ye X X et al. Corrosion behavior of pure metals (Ni and Ti) and alloys (316H SS and GH3535) in liquid GaInSn[J]. Nuclear Science and Techniques, 35, 54(2024).

[19] Huang J L, Jia G B, Han L F et al. Dynamic simulation analysis of molten salt reactor-coupled air-steam combined cycle power generation system[J]. Nuclear Science and Techniques, 35, 30(2024).

[20] Ai H, Yang X M, Liu H J et al. Study on the corrosion behavior of 316H stainless steel in molten NaCl-KCl-MgCl2 salts with and without purification[J]. Nuclear Science and Techniques, 34, 191(2023).

[21] WANG Yujiao, QU Yaxin, FU Haiying et al. Separation of rare earth fission products from LiF-BeF2 molten salt by sulfide precipitation[J]. Nuclear Techniques, 47, 010302(2024).

Tools

Get Citation

Copy Citation Text

Zhen YANG, Zhimin DAI, Zhangzhong YANG, Yang ZOU. Criticality safety analysis of nuclear fuel storage of molten salt reactor[J]. NUCLEAR TECHNIQUES, 2024, 47(8): 080606

Download Citation

EndNote(RIS)BibTex Plain Text

Set citation alerts for article

Save article for my favorites

Paper Information

Category: NUCLEAR ENERGY SCIENCE AND ENGINEERING

Received: Apr. 15, 2024

Accepted: --

Published Online: Sep. 23, 2024

The Author Email: DAI Zhimin (戴志敏)

DOI:10.11889/j.0253-3219.2024.hjs.47.080606

Topics

laser devices and laser physics

Lasers and Laser Optics

laser manufacturing

Instrumentation, Measurement and Metrology