Transient analysis of tritium transport characteristics of thorium molten salt reactor with solid fuel

2020 ◽  
Vol 141 ◽  
pp. 107337
Author(s):  
Chenglong Wang ◽  
Hao Qin ◽  
Wenxi Tian ◽  
Suizheng Qiu ◽  
G.H. Su
2018 ◽  
Vol 335 ◽  
pp. 391-399 ◽  
Author(s):  
Chenglong Wang ◽  
Hao Qin ◽  
Dalin Zhang ◽  
Wenxi Tian ◽  
Suizheng Qiu ◽  
...  

Author(s):  
S. Jiang ◽  
M. Perez-Ferragut ◽  
Z. Fu ◽  
J. K. Hohorst

In recent years, organizations both at home and abroad are actively carrying out a research on the Molten Salt Reactor systems (MSRs). For example, the Shanghai Institute of Applied Physics (SINAP), Chinese Academy of Science (CAS), is currently involved in the design and development of a 10MWth Solid Fuel Thorium Molten Salt Reactor (TMSR-SF1). SINAP started their analysis of TMSR using an earlier version of RELAP/SCDAPSIM, MOD4.0. MOD4.0 included models and correlations for molten salts but was unable to treat molten salts in the presence of non-condensable gases. Since that time SINAP and ISS have worked in parallel to extend the models and correlations for such systems. The SINAP modified code, using SINAP proprietary models and correlations, is described in the “open literature” under the name RELAP5-MSR. More general, but comparable, models developed by ISS for liquid metals/salts in the presence of non-condensable have been incorporated into RELAP/SCDAPSIM/MOD4.1. This extended option is currently being implemented for Li-Pb, Pb-Bi, molten salts, and Na.


2008 ◽  
Vol 163 (3) ◽  
pp. 358-365 ◽  
Author(s):  
Elsa Merle-Lucotte ◽  
Ludovic Mathieu ◽  
Daniel Heuer ◽  
Véronique Ghetta ◽  
Roger Brissot ◽  
...  

2006 ◽  
Vol 48 (7) ◽  
pp. 664-679 ◽  
Author(s):  
L. Mathieu ◽  
D. Heuer ◽  
R. Brissot ◽  
C. Garzenne ◽  
C. Le Brun ◽  
...  

2020 ◽  
Vol 135 ◽  
pp. 106973
Author(s):  
Robert Mardus-Hall ◽  
Mark Ho ◽  
Andrew Pastrello ◽  
Guan Yeoh

Author(s):  
Julien de Troullioud de Lanversin ◽  
Alexander Glaser ◽  
Malte Göttsche

In circulating fuel reactors, such as the Molten Salt Reactor, the fuel circulates throughout the reactor instead of being immobile as in solid fuel reactors. The vast majority of nuclear simulation codes are primarily designed to simulate solid fuel reactors. Hence, many features unique to circulating fuel reactors, such as fuel injection and removal, cannot be properly modeled with these codes. The work presented here focuses on developing a numerical simulation package that can effectively and accurately model these reactors. This package consists of the coupling of the Monte Carlo particle transport code OpenMC with a modified version of ORIGEN-S, and uses a novel algorithm that calculates the optimal fuel injection and removal schemes for such reactors to achieve certain conditions such as a stable reactivity. We demonstrate our code’s accuracy by benchmarking the coupling module with the MCODE coupling code, and by simulating the operation of the ORNL Denatured Molten Salt Reactor using the coupling and fuel injection modules. The resulting fuel injection scheme is in agreement with the original study of that reactor while offering a much finer resolution for the injection scheme over time. This work is part of a broader project to develop an open-source neutronics code for circulating fuel reactors that will couple OpenMC with an in-house open-source depletion module.


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