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

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.

scholarly journals Fuel Cycle Performance of Fast Spectrum Molten Salt Reactor Designs

2019 ◽  
Author(s):  
Andrei Rykhlevskii ◽  
Benjamin R. Betzler ◽  
Jin Whan Bae ◽  
Kathryn Huff
Keyword(s):  
Performance Analysis ◽  
Molten Salt ◽  
Doubling Time ◽  
Fuel Cycle ◽  
Cycle Performance ◽  
Simplified Model ◽  
Molten Salt Reactor ◽  
Cell Models ◽  
Breeding Ratio ◽  
Full Core

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.

Steady State Analysis of Molten Salt Reactor in Consideration of the Effect of Fuel Salt Flow

2004 ◽  
Author(s):  
Takahisa Yamamoto ◽  
Koshi Mitachi ◽  
Takashi Suzuki
Keyword(s):  
Steady State ◽  
Thermal Neutron ◽  
Molten Salt ◽  
Fuel Cycle ◽  
Molten Salt Reactor ◽  
Delayed Neutron ◽  
Steady State Analysis ◽  
Fuel Salt ◽  
Salt Flow ◽  
State Analysis

The Molten Salt Reactor (MSR) is a thermal neutron reactor with graphite moderation and operates on the thorium-uranium fuel cycle. The feature of the MSR is that fuel salt flows the inside of the reactor accompanying nuclear fission reaction. In the previous study, the authors had developed numerical model to simulate the effects of the fuel salt flow on the reactor characteristics. This paper applies the model to the steady state analysis of the small MSR system and estimates the effects of the fuel flow. The model consists of two group diffusion equations for fast and thermal neutron fluxes, balance equations for six-group delayed neutron precursors and energy conservation equations for fuel salt and graphite moderator. The following results are obtained: (1) the fuel salt flow affects the distributions of the delayed neutron precursors, especially long-lived one, and (2) the extension of residence time in the external loop system and the rise of fuel inflow temperature slightly show negative reactivity effects, decreasing neutron multiplication factor of the small MSR system.

A new method for monitoring the redox potential of fuel salt based on the deposition of 95Nb on Hastelloy C276

2021 ◽  
Vol 109 (5) ◽  
pp. 357-365
Author(s):  
Zhiqiang Cheng ◽  
Zhongqi Zhao ◽  
Junxia Geng ◽  
Xiaohe Wang ◽  
Jifeng Hu ◽  
...  
Keyword(s):  
Redox Potential ◽  
Molten Salt ◽  
Specific Activity ◽  
Chemical Reduction ◽  
Quantitative Approach ◽  
Experimental Results ◽  
New Method ◽  
Molten Salt Reactor ◽  
Fuel Salt ◽  
Well Correlation

Abstract To develop the application of 95Nb as an indicator of redox potential for fuel salt in molten salt reactor (MSR), the specific activity of 95Nb in FLiBe salt and its deposition of 95Nb on Hastelloy C276 have been studied. Experimental results indicated that the amount of 95Nb deposited on Hastelloy C276 resulted from its chemical reduction exhibited a positive correlation with the decrease of 95Nb activity in FLiBe salt and the relative deposition coefficient of 95Nb to 103Ru appeared a well correlation with 95Nb activity in FLiBe salt. Both correlations implied that the measurement of 95Nb activity deposited on Hastelloy C276 specimen might provide a quantitative approach for monitoring the redox potential of fuel salt in MSR.

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

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

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

2014 ◽  
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.

Accelerator-driven subcritical fission in molten salt core: Closing the nuclear fuel cycle for green nuclear energy

2013 ◽  
Author(s):  
Peter McIntyre ◽  
Saeed Assadi ◽  
Karie Badgley ◽  
William Baker ◽  
Justin Comeaux ◽  
...  
Keyword(s):  
Molten Salt ◽  
Nuclear Fuel ◽  
Nuclear Energy ◽  
Fuel Cycle ◽  
Nuclear Fuel Cycle

Molten-Salt Reactor for Nuclear Fuel Cycle Closure on All Actinides

Atomic Energy ◽  
2019 ◽  
Vol 125 (5) ◽  
pp. 279-283 ◽  
Author(s):  
V. V. Ignatiev ◽  
M. V. Kormilitsyn ◽  
L. A. Kormilitsyna ◽  
Yu. M. Semchenkov ◽  
Yu. S. Fedorov ◽  
...  
Keyword(s):  
Molten Salt ◽  
Nuclear Fuel ◽  
Fuel Cycle ◽  
Nuclear Fuel Cycle ◽  
Molten Salt Reactor

Impact on Nuclear Waste Production of Different Fuel Cycle Strategies

2006 ◽  
Author(s):  
Lionel Boucher ◽  
Jean-Paul Grouiller ◽  
Charles Courtois ◽  
Sylvain David ◽  
Matthieu Maurin
Keyword(s):  
Waste Management ◽  
Nuclear Waste ◽  
Nuclear Energy ◽  
Fuel Cycle ◽  
Present Situation ◽  
Single Stage ◽  
French Law ◽  
Waste Production ◽  
French Case ◽  
Phase Out

In the frame of the French law for the researches about waste management, different dynamic scenarios have been studied [1]. These scenarios are considering the French case and start from the present situation, which consists in a single stage of Plutonium recycling in PWRs. The scenarios described in this paper take into account two main options: Continuation of nuclear energy or phase out option.

Prospects of subcritical molten salt reactor for minor actinides incineration in closed fuel cycle

Kerntechnik ◽  
2015 ◽  
Vol 80 (4) ◽  
pp. 389-393 ◽  
Author(s):  
P. N. Alekseev ◽  
A. L. Balanin ◽  
V. Yu. Blandinsky ◽  
A. A. Dudnikov ◽  
P. A. Fomichenko ◽  
...  
Keyword(s):  
Molten Salt ◽  
Fuel Cycle ◽  
Minor Actinides ◽  
Molten Salt Reactor ◽  
Closed Fuel Cycle
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