scholarly journals A unique molten salt reactor feature – The freeze valve system: Design, operating experience, and reliability

2020 ◽  
Vol 368 ◽  
pp. 110803
Author(s):  
Brandon M. Chisholm ◽  
Steven L. Krahn ◽  
Andrew G. Sowder
Keyword(s):  
System Design ◽  
Molten Salt ◽  
Operating Experience ◽  
Molten Salt Reactor ◽  
Valve System

Numerical Investigation of Safety System Parameters in Molten Salt Reactor: Wall Effect on Freeze Valve Opening Time

2021 ◽  
Author(s):  
Muhammad Ilham ◽  
Indarta Kuncoro Aji ◽  
Tomio Okawa
Keyword(s):  
Molten Salt ◽  
Power Plants ◽  
Melting Process ◽  
Wall Effect ◽  
Fourth Generation ◽  
Reactor Wall ◽  
Molten Salt Reactor ◽  
Oak Ridge ◽  
Valve System ◽  
The Core

Abstract Molten Salt Reactor (MSRs) is one of the fourth generation Nuclear Power Plants with better capabilities and potentialities compared to previous generation, the enthusiasm for molten fuel reactor has been increasing around the world. MSRs has passive safety where if the core is overheating cause by accident event, the liquid salt fuel was required to be moved to the safety drain tank underneath the core vessel by gravity force. During this occasion, the freeze valve (FV) that formed in the pipe located between the core and drain tank must be melt out promptly to prevent the vessel to reach it is melting point. In this paper, we conduct on thermal analysis of the freeze valve at the solidification and melting process based on finite elements methods. The enthalpy-porosity method adopted by ANSYS Fluent was used to simulated the designed system at specified condition. The Oak Ridge National Laboratory of Molten Salt Reactor Experiment Freeze valve system was used as a references for parameters investigation. Using pipe wall thickness of 5 mm, 10 mm, and 15 mm to examined the wall effect to thermal properties of the designed freeze valve. The wall pipe for FV systems material was also investigate in order to examine its effect to the opening time. Further, the temperature distributions of the valve system were obtained and analyzed. It was found that the wall effect has significant impact to the solidification and melting process.

Signatures of plutonium diversion in Molten Salt Reactor dynamics

2021 ◽  
Vol 160 ◽  
pp. 108370
Author(s):  
Alexander M. Wheeler ◽  
Ondřej Chvála ◽  
Steven Skutnik
Keyword(s):  
Molten Salt ◽  
Molten Salt Reactor ◽  
Reactor Dynamics

Analyses of production capacity of 89Sr and 90Sr in the 2 MW molten salt reactor

2021 ◽  
Vol 173 ◽  
pp. 109714
Author(s):  
Chen Wu ◽  
Chenggang Yu ◽  
Ao Zhang ◽  
Chunyan Zou ◽  
Yuwen Ma ◽  
...  
Keyword(s):  
Molten Salt ◽  
Production Capacity ◽  
Molten Salt Reactor

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

Implementation of two-phase gas transport into VERA for molten salt reactor analysis

2022 ◽  
Vol 165 ◽  
pp. 108672
Author(s):  
Zack Taylor ◽  
Robert Salko ◽  
Aaron M. Graham ◽  
Benjamin S. Collins ◽  
G. Ivan Maldonado
Keyword(s):  
Molten Salt ◽  
Gas Transport ◽  
Molten Salt Reactor ◽  
Two Phase

Machine learning application to single channel design of molten salt reactor

2021 ◽  
Vol 161 ◽  
pp. 108409
Author(s):  
Mehmet Turkmen ◽  
Gwendolyn J.Y. Chee ◽  
Kathryn D. Huff
Keyword(s):  
Machine Learning ◽  
Molten Salt ◽  
Single Channel ◽  
Molten Salt Reactor ◽  
Channel Design

Distribution and behavior of fission product 95Nb in FLiBe salt

2021 ◽  
Vol 0 (0) ◽  
Author(s):  
Zhiqiang Cheng ◽  
Xiaohe Wang ◽  
Zhongqi Zhao ◽  
Junxia Geng ◽  
Jifeng Hu ◽  
...  
Keyword(s):  
Fission Product ◽  
Redox Potential ◽  
Molten Salt ◽  
Molten Salt Reactor ◽  
Lithium Metal ◽  
Site Monitoring ◽  
Salt Addition ◽  
Redox Indicator ◽  
Γ Ray ◽  
And Behavior

Abstract The 235,238UF4 was irradiated by photo-neutrons, distribution and behavior of the fission product 95Nb from irradiated 235,238UF4 in FLiBe salt were investigated by the measurement of its activity in the salt with the γ-ray spectroscopy. The experiments indicated that a part of 95Nb deposited on the surfaces of graphite and Hastelloy, as the moderator and the structural materials of molten salt reactor (MSR), respectively, and the majority of 95Nb maintained in molten salt. Addition of lithium metal made 95Nb in salt to be reduced and settled, leading to the decrease in its activity. Degree of the decrease was found to be correlated with niobium concentration. The experimental results supported the statement proposed early by ORNL, that 95Nb might be used as a redox indicator for MSR. Finally, the problem met with on-site monitoring for redox potential in MSR was pointed, and a possible protocol to resolve the problem was proposed.

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