Self-sintered nanopore-isotropic graphite derived from green pitch coke for application in molten salt nuclear reactor

2019 ◽  
Vol 131 ◽  
pp. 412-416 ◽  
Author(s):  
Hongchao Zhao ◽  
Zhao He ◽  
Zhanjun Liu ◽  
Jinliang Song ◽  
D.K.L. Tsang ◽  
...  
Carbon ◽  
2014 ◽  
Vol 79 ◽  
pp. 36-45 ◽  
Author(s):  
Jinliang Song ◽  
Yanling Zhao ◽  
Junpeng Zhang ◽  
Xiujie He ◽  
Baoliang Zhang ◽  
...  

Fuel ◽  
2021 ◽  
Vol 290 ◽  
pp. 120055
Author(s):  
Zhao He ◽  
Jinliang Song ◽  
Zheng Wang ◽  
Xiaohui Guo ◽  
Zhanjun Liu ◽  
...  

Author(s):  
Jian Ge ◽  
Dalin Zhang ◽  
Wenxi Tian ◽  
Suizheng Qiu ◽  
G. H. Su

As one of the six selected optional innovative nuclear reactor in the generation IV International Forum (GIF), the Molten Salt Reactor (MSR) adopts liquid salt as nuclear fuel and coolant, which makes the characteristics of thermal hydraulics and neutronics strongly intertwined. Coupling analysis of neutronics and thermal hydraulics has received considerable attention in recent years. In this paper, a new coupling method is introduced based on the Finite Volume Method (FVM), which is widely used in the Computational Fluid Dynamics (CFD) methodology. Neutron diffusion equations and delayed neutron precursors balance equations are discretized and solved by the commercial CFD package FLUENT, along with continuity, momentum and energy equations simultaneously. A Temporal And Spatial Neutronics Analysis Model (TASNAM) is developed using the User Defined Functions (UDF) and User Defined Scalar (UDS) in FLUENT. A neutronics benchmark is adopted to demonstrate the solution capability for neutronics problems using the method above. Furthermore, a steady state coupled analysis of neutronics and thermal hydraulics for the Molten Salt Advanced Reactor Transmuter (MOSART) is performed. Two groups of neutrons and six groups of delayed neutron precursors are adopted. Distributions of the liquid salt velocity, temperature, neutron flux and delayed neutron precursors in the core are obtained and analyzed. This work can provide some valuable information for the design and research of MSRs.


2020 ◽  
Author(s):  
J. Blanco ◽  
V. Ghetta ◽  
J. Giraud ◽  
V. Richard ◽  
P. Rubiolo ◽  
...  

Author(s):  
Qiming Li ◽  
Zhongfeng Tang ◽  
Yuan Fu ◽  
Zhong Li ◽  
Naxiu Wang

The use of passive shutdown systems to enhance safety is one element of next-generation reactor design. The Freeze-Valve has been proposed as a key device in the passive system to stop the chain reaction of the Molten Salt Reactor (MSR), which has been chosen by Generation IV International Forum (GIF) as one of the six Generation IV reactor concepts. During reactor normal operation, the molten salt in the valve is cooled to a solid plug. In the event that the reactor overheats under accident conditions when all other active control systems fail, the plug will melt. The liquid fuel salt will be pulled out from the reactor core by gravity into dump tanks, and criticality will cease because the reaction is no longer moderated by the graphite in the reactor core. The more accurate the Freeze-Valve’s thermal design is, the more efficient the passive shutdown system becomes. In this study, an investigation of the thermal performance of the Freeze-Valve is conducted based on finite element methods verified by experimental data, and some modified designs are presented with recommendations. For further consideration, some innovative governing techniques used to control the Freeze-Valve are discussed in detail. Here, a more critical thermal design is focused on that can make the passive system shut down the nuclear reactor quickly and reliably. The Freeze-Valve can be used in the molten salt loop rather than a mechanical valve, which may become jammed by frozen salt. Paper published with permission.


2020 ◽  
Author(s):  
J. Blanco ◽  
V. Ghetta ◽  
J. Giraud ◽  
V. Richard ◽  
P. Rubiolo ◽  
...  

Author(s):  
Brian C. Kelleher ◽  
Kieran P. Dolan ◽  
Paul Brooks ◽  
Mark H. Anderson ◽  
Kumar Sridharan

Li 2 BeF 4 , or flibe, is the primary candidate coolant for the fluoride-salt-cooled high-temperature nuclear reactor (FHR). Kilogram quantities of pure flibe are required for repeatable corrosion tests of modern reactor materials. This paper details fluoride salt purification by the hydrofluorination–hydrogen process, which was used to regenerate 57.4 kg of flibe originating from the secondary loop of the molten salt reactor experiment (MSRE) at Oak Ridge National Laboratory (ORNL). Additionally, it expounds upon necessary handling precautions required to produce high-quality flibe and includes technological advancements which ease the purification and analysis process. Flibe batches produced at the University of Wisconsin are the largest since the MSRE program, enabling new corrosion, radiation, and thermal hydraulic testing around the United States.


Author(s):  
Z. Wang ◽  
G. F. Naterer ◽  
K. S. Gabriel

Thermochemical hydrogen cogeneration using heat of molten salt nuclear reactors (MSRs) is discussed in this paper. Sulfur-iodine and copper-chlorine cycles are taken as typical examples for analysis and discussion. It is found that the heat exchanger design is predominately determined by the maximum and range of temperatures of themochemical hydrogen production cycles with MSRs. Copper-chlorine (Cu-Cl) thermochemical cycles can link with most MSRs, but sulfur-iodine (S-I) cycles can only link with very high temperature MSRs. The location of extracted heat from MSRs to S-I and Cu-Cl cycles is investigated, and its influence on the layout of nuclear reactor coolant loop is discussed. Some conceptual designs of heat exchangers are proposed to transfer heat from MSRs to Cu-Cl and S-I cycles. The available heat quantity at different hours of a day and corresponding hydrogen production scales are determined. It is found that the available heat at most hours of power demand in a day is equivalent to the hydrogen cogeneration capacity of an industrial scale steam methane reforming plant, if an MSR power station is operating at an invariable maximum power, independent of an electrical load throughout a day or year.


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