Nuclear Techniques ›› 2020, Vol. 43 ›› Issue (8): 80006-080006.doi: 10.11889/j.0253-3219.2020.hjs.43.080006

• SPECIAL SECTION ON THE 11TH NATIONAL CONFERENCE ON NEW AND RESEARCH REACTORS (PART III) • Previous Articles     Next Articles

Preliminary neutronics design of space nuclear reactor based on molten salt cooling

Ting LI,Kun ZHUANG(),Wen SHANG,Xiaobin TANG   

  1. College of Materials Science and Technology, Nanjing University of Aeronautics and Astronautics, Nanjing 211106, China
  • Received:2020-04-27 Revised:2020-05-18 Online:2020-08-15 Published:2020-08-12
  • Contact: Kun ZHUANG E-mail:kzhuang@nuaa.edu.cn
  • About author:LI Ting, female, born in 1995, graduated from Taishan Medical College in 2018, master student, focusing on reactor physics
  • Supported by:
    Science and Technology Innovation Project for Overseas Students in Nanjing(YQR19037);China Postdoctoral Fund Pre Station Special Support Project(2019TQ0148);Basic Scientific Research Business Fees of Central University(NS2019036);Open Fund for Key Laboratory of Ministry of Industry and Information Technology of Space Nuclear Technology Application and Radiation Protection(NJ2020017-1)

Abstract: Background

Space nuclear reactor (SNR) has attracted more and more attention worldwide due to its significant advantages in deep space exploration. Different from the traditional liquid metal, gas and heat pipe cooling methods, molten salt coolant can dissolve fission materials with good heat transfer properties, hence can be used as a coolant in SNR scheme.

Purpose

This study aims at the preliminary neutronics design for molten salt cooled SNR.

Methods

Based on the design scheme of SNR, Monte Carlo code SERPENT and database ENDF/B-Ⅶ.1 were employed for preliminary neutron design of SNR with molten salt cooling. The effects of different fuel, cladding materials, rod pitch on the kinf of fuel rods and effects of different molten salts, reflector materials on the keff of core were investigated. Finally, a preliminary SNR core scheme based on fluoride salt 7LiF-BeF2-UF4 (66.4-32.7-0.9 mol%) to cool UC fuel (235U, mass fraction at 80%) was proposed.

Results

The results show that keff of fuel rods is closely related to the fuel material, it increases with the 235U enrichment of fuel and decreases with the rod pitch.

Conclusions

Different molten salts and reflector materials have great influences on keff of reactor core, but the 235U enrichment of UF4 in coolant is not sensitive to keff.

Key words: Space nuclear reactor, Molten salt cooling, Neutronics, Reactivity coefficient

CLC Number: 

  • TL32