0
research-article

New Exploration on TMSR: Redesign of the TMSR Lattice

[+] Author and Article Information
Jinkun ZHAO

Shanghai Nuclear Engineering Research & Design Institute Co., Ltd., No.29 Hongcao Road, Shanghai, China, 200233
zhaojinkun@snerdi.com.cn

Shengyi SI

Shanghai Nuclear Engineering Research & Design Institute Co., Ltd., No.29 Hongcao Road, Shanghai, China, 200233
hankspapa@snerdi.com.cn

Qichang CHEN

Shanghai Nuclear Engineering Research & Design Institute Co., Ltd., No.29 Hongcao Road, Shanghai, China, 200233
chenqichang@snerdi.com.cn

Hua BEI

Shanghai Nuclear Engineering Research & Design Institute Co., Ltd., No.29 Hongcao Road, Shanghai, China, 200233
beihua@snerdi.com.cn

1Corresponding author.

ASME doi:10.1115/1.4041192 History: Received October 25, 2017; Revised August 13, 2018

Abstract

Molten Salt Reactor (MSR) has been recognized as one of the Next Generation Nuclear Power systems. Most MSR concepts are the variants evolved from the ORNL's Molten-Salt Breeder Reactor (MSBR) which employs Molten-Salt as both fuel and coolant, and normally graphite is used as moderator. Many evaluations have revealed that such concepts have low breeding ratio and might present positive power coefficient. Facing these impediments, TMSR (Thorium Molten Salt Reactor) with redesigned lattice is proposed in this paper. Based on comprehensive investigation and screening, important lattice parameters including molten salt fuel composition, solid moderator material, lattice size, structure and lattice P/D ratio (lattice pitch to channel diameter) are redesigned. In this paper, a fuel composition without BeF2 is adopted to increase the solubility for actinides (ThF4, UF4), and BeO is introduced as moderator to improve neutron economy. Moreover, lattice size and structure with cladding to separate fuel and moderator were also optimized. With these lattice parameters, TMSR has a high breeding ratio close to 1.14 and a short doubling time about 15 years. Meanwhile a negative power coefficient is maintained. Based on this lattice design, TMSR can have excellent performance of safety and sustainability. SONG/TANG-MSR codes system is applied in the simulation, which is independently developed by Shanghai Nuclear Engineering Research & Design Institute (SNERDI).

Copyright (c) 2018 by ASME
Your Session has timed out. Please sign back in to continue.

References

Figures

Tables

Errata

Some tools below are only available to our subscribers or users with an online account.

Related Content

Customize your page view by dragging and repositioning the boxes below.

Related Journal Articles
Related eBook Content
Topic Collections

Sorry! You do not have access to this content. For assistance or to subscribe, please contact us:

  • TELEPHONE: 1-800-843-2763 (Toll-free in the USA)
  • EMAIL: asmedigitalcollection@asme.org
Sign In