Fuel Cycle Performance of Fast Spectrum Molten Salt Reactor Designs

4 fast-spectrum molten salt conceptual designs have been selected for fuel cycle performance analysis. 3D full core and 2D unit cell models have been developed to justify the possibility to use a simplified model for computational-heavy depletion simulation with truly continuous online reprocessing. Finally, 60-years depletion simulation for Molten Salt Fast Reactor (MSFR) shown lifetime breeding ratio 1.0072 and doubling time 139 years in Th/U fuel cycle.

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Self-Breeding and Radiotoxicity Analysis on Thorium-Based Molten Salt Reactors

Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors ◽

10.1115/icone21-15454 ◽

2013 ◽

Author(s):

Chun-yan Zou ◽

Jin-gen Chen ◽

Xiang-zhou Cai ◽

Cheng-gang Yu ◽

Da-zhen Jiang ◽

...

Keyword(s):

Molten Salt ◽

Nuclear Energy ◽

Fuel Cycle ◽

Molten Salt Reactor ◽

Nuclear System ◽

Energy Sustainability ◽

Waste Production ◽

Breeding Ratio ◽

Fuel Salt ◽

System Project

As one of the candidates in the Generation IV reactors program., the molten salt reactor (MSR) has the properties of online refueling and fuel salt reprocessing, MSR is especially attractive for the Thorium fuel cycle, which is very ideal for nuclear non-proliferation, radiotoxicity and nuclear energy sustainability. Therefore, the “Thorium-based Molten Salt Reactor (TMSR) nuclear system” project has been proposed as one of the “Strategic Priority Research Program” of Chinese Academy of Science (CAS). In this paper, we mainly investigated the influence on the breeding ratio and waste radiotoxicity with different reprocessing schemes. By considering the key parameters mentioned above, the aim is to choose an efficient reprocessing scheme for TMSR to reach self-breeding with Th/U fuel cycle and minimize the radioactive waste production of the molten salt.

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Preliminary analysis of fuel cycle performance for a small modular heavy water-moderated thorium molten salt reactor

Nuclear Science and Techniques ◽

10.1007/s41365-020-00823-5 ◽

2020 ◽

Vol 31 (11) ◽

Author(s):

Ya-Peng Zhang ◽

Yu-Wen Ma ◽

Jian-Hui Wu ◽

Jin-Gen Chen ◽

Xiang-Zhou Cai

Keyword(s):

Molten Salt ◽

Heavy Water ◽

Preliminary Analysis ◽

Fuel Cycle ◽

Cycle Performance ◽

Molten Salt Reactor ◽

Thorium Molten Salt Reactor

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Assessment of the Neutronic and Fuel Cycle Performance of the Transatomic Power Molten Salt Reactor Design

10.2172/1410921 ◽

2017 ◽

Cited By ~ 2

Author(s):

Sean Robertson ◽

Leslie Dewan ◽

Mark Massie ◽

Eva E. Davidson ◽

Benjamin R. Betzler ◽

...

Keyword(s):

Molten Salt ◽

Fuel Cycle ◽

Reactor Design ◽

Cycle Performance ◽

Molten Salt Reactor

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Transition to thorium fuel cycle on a heavy water moderated molten salt reactor by using low enrichment uranium

Annals of Nuclear Energy ◽

10.1016/j.anucene.2021.108638 ◽

2022 ◽

Vol 165 ◽

pp. 108638

Author(s):

Jianhui Wu ◽

Jingen Chen ◽

Chunyan Zou ◽

Chenggang Yu ◽

Xiangzhou Cai ◽

...

Keyword(s):

Molten Salt ◽

Heavy Water ◽

Fuel Cycle ◽

Molten Salt Reactor

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Molten Salt Reactor With Simplified Fuel Recycling and Delayed Carrier Salt Cleaning

Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security ◽

10.1115/icone22-30396 ◽

2014 ◽

Cited By ~ 4

Author(s):

Jiři Křepel ◽

Valentyn Bykov ◽

Konstantin Mikityuk ◽

Boris Hombourger ◽

Carlo Fiorina ◽

...

Keyword(s):

Molten Salt ◽

Fuel Cycle ◽

Ex Situ ◽

Molten Salt Reactor ◽

Inherent Safety ◽

Neutron Spectra ◽

Fuel Fabrication

The Molten Salt Reactor (MSR) represents an old concept, but its properties are qualifying it for the advanced utilization: inherent safety, excellent neutron economy, possibility of continuous or batch reprocessing without fuel fabrication. The aim of this paper is to characterize the MSR unique fuel cycle advantages in different neutron spectra using the results of ERANOS-based EQL3D and ECCO-MATLAB based EQL0D procedures. It also focuses on the low production of higher actinides in the Th-U cycle and based on the results, it proposes a simplified in situ recycling of the fuel and the delayed ex situ carrier salt cleaning or direct disposal by vitrification.

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