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Nuclear and Hydro Power
Published in Anco S. Blazev, Energy Security for The 21st Century, 2021
This concept was first investigated at the Oak Ridge National Laboratory Molten-Salt Reactor Experiment in the 1960s. It has recently been the subject of a renewed interest worldwide. Japan, China, the UK, as well as private US, Czech and Australian companies have expressed intent to develop and commercialize the technology.
The Other Energy Sources
Published in Anco S. Blazev, Power Generation and the Environment, 2021
This concept was first investigated at the Oak Ridge National Laboratory Molten-Salt Reactor Experiment in the 1960s. It has recently been the subject of renewed interest worldwide. Japan, China, the UK, as well as private US, Czech and Australian companies have expressed intent to develop and commercialize the technology.
Testing of an Element Tracer Dilution Method for Measurement of Total Mass of Molten Salt in a Nuclear Fuel Cycle Process or Molten Salt Reactor
Published in Nuclear Technology, 2022
Huan Zhang, Shelly X. Li, Michael F. Simpson
Molten salts containing fissile actinides are utilized in pyroprocessing-based used nuclear fuel recycling processes, such as the electrometallurgical treatment of irradiated Experimental Breeder Reactor-II in the Fuel Conditioning Facility of Idaho National Laboratory1 (INL). Pyroprocessing technology has yet to be scaled to support treatment of commercial used fuel but is considered as a candidate for such application, most notably in Korea.2 Another emerging application of molten salts in the nuclear energy field is as a liquid fuel in a molten salt reactor (MSR). The first demonstration of a molten salt–fueled nuclear reactor was the Molten Salt Reactor Experiment at Oak Ridge National Laboratory in the 1960s (Ref. 3). In recent years, there is renewed interest in new approaches to the MSR (Ref. 4). Nuclear reactor design companies, including but not limited to TerraPower, Terrestrial Energy, and Flibe Energy, have notably publicized their intention to develop advanced versions of the MSR (Ref. 5). This development increases the probability that molten salt systems will be used in large-scale nuclear operations.
Manufacturing of molten salt reactor heat exchangers using inner hole welding
Published in Materials and Manufacturing Processes, 2021
Shuangjian Chen, Run-Sheng Gao, Zhijun Li
Molten salt reactor is one of the generation IV nuclear reactors, which using molten salt as heat-transfer medium. It was developed from the Molten Salt Reactor Experiment which ran for four years from 1965 to 1969.[1–4] This reactor employed UNS N10003 alloy (Ni-17Mo-7Cr-4Fe alloy) as the metallic structural material, which was designed by Oak Ridge National Laboratory and exhibited high molten salt corrosion resistance, excellent high-temperature strength and weldability.[5–10] Nowdays a 2 MW Thorium Molten Salt Reactor is under construction in China. Similar to Molten Salt Reactor Experiment, Thorium Molten Salt Reactor has two molten salt circuits connected by heat exchangers which are the key components in the reactor system.[1,8] The primary circuit of Thorium Molten Salt Reactor flows through the reactor vessel, pump and the shell side of the primary heat exchanger with a fuel molten salt consisting of lithium fluoride (LiF), beryllium fluoride (BeF2), zirconium fluoride (ZrF4), uranium fluoride (UF4) and thorium fluoride (ThF4) (not used in Molten Salt Reactor Experiment). The secondary circuit circulates through the tube side of the primary heat exchanger and an air-cooled system with a non-fuel-bearing coolant salt, lithium fluoride (LiF), beryllium fluoride (BeF2).[2,8,11]
Transient analysis of TMSR-SF0 simulator
Published in Journal of Nuclear Science and Technology, 2021
Jiajun Wang, Ye Dai, Yang Zou, Hongjie Xu
In the Molten Salt Reactor Experiment (MSRE), the fuel salt (a mixture of , , , and ) and the coolant salt (a mixture of and ), are heated up from 908 K to 936 K and 825 K to 866 K at 10-MW power level respectively, in which loss of flow and load were studied [3–5]. In the design of Molten-Salt Breeder Reactor (MSBR), the freezing of coolant salts in heat exchangers was concerned because of the high melting points; of course, it was demonstrated that prevention of coagulation is not a difficult control problem by MSRE [6]. Therefore, it is vital to study the experimental phenomena of SF0 in different conditions. A computer simulation of how the test facility should be operated is valued. The formulation of protective system and experimental process of test facility will be optimized according to the results of simulation by RELAP5.