scholarly journals Chemical compatibility of silicon carbide in molten fluoride salts for the fluoride salt-cooled high temperature reactor

2019 ◽  
Vol 524 ◽  
pp. 119-134 ◽  
Author(s):  
Jo Jo Lee ◽  
Stephen S. Raiman ◽  
Yutai Katoh ◽  
Takaaki Koyanagi ◽  
Cristian I. Contescu ◽  
...  
Keyword(s):  
Silicon Carbide ◽  
High Temperature ◽  
Fluoride Salt ◽  
Chemical Compatibility ◽  
Molten Fluoride ◽  
High Temperature Reactor ◽  
Fluoride Salts

Considerations of Alloy N for Fluoride Salt-Cooled High-Temperature Reactor Applications

2011 ◽  
Author(s):  
Weiju Ren ◽  
Govindarajan Muralidharan ◽  
Dane F. Wilson ◽  
David E. Holcomb
Keyword(s):  
High Temperature ◽  
Current Status ◽  
Coolant Temperature ◽  
High Temperature Strength ◽  
Fluoride Salt ◽  
Chemical Compatibility ◽  
Distinctive Property ◽  
Higher Temperature ◽  
Alloy Properties ◽  
Fluoride Salts

Fluoride Salt-Cooled High-Temperature Reactors (FHRs) are a promising new class of thermal-spectrum nuclear reactors. The reactor structural materials must possess high-temperature strength and chemical compatibility with the liquid fluoride salt as well as with a power cycle fluid such as supercritical water while remaining resistant to residual air within the containment. Alloy N was developed for use with liquid fluoride salts and it possesses adequate strength and chemical compatibility up to about 700°C. A distinctive property of FHRs is that their maximum allowable coolant temperature is restricted by their structural alloy maximum service temperature. As the reactor thermal efficiency directly increases with the maximum coolant temperature, higher temperature resistant alloys are strongly desired. This paper reviews the current status of Alloy N and its relevance to FHRs including its design principles, development history, high temperature strength, environmental resistance, metallurgical stability, component manufacturability, ASME codification status, and reactor service requirements. The review will identify issues and provide guidance for improving the alloy properties or implementing engineering solutions.

scholarly journals Fluoride-Salt-Cooled High-Temperature Reactor (FHR) for Power and Process Heat

2015 ◽  
Author(s):  
Charles Forsberg ◽  
Lin-wen Hu ◽  
Per Peterson ◽  
Kumar Sridharan
Keyword(s):  
High Temperature ◽  
Fluoride Salt ◽  
High Temperature Reactor ◽  
Process Heat

Effects of Thermal Ageing on Microstructure and Hardness of Ni Cladding on Austenitic Stainless Steel by GTAW

2018 ◽  
Author(s):  
Kun Yu ◽  
Xianwu Shi ◽  
Zhijun Li ◽  
Chaowen Li ◽  
Shuangjian Chen ◽  
...  
Keyword(s):  
Stainless Steel ◽  
High Temperature ◽  
Austenitic Stainless Steel ◽  
Fuel Cycle ◽  
Thermal Ageing ◽  
High Temperature Strength ◽  
Characterization Methods ◽  
Gas Tungsten Arc ◽  
Molten Fluoride ◽  
Fluoride Salts

As one of the most promising Generation IV nuclear reactors, thorium molten salt reactor (TMSR) possesses inherent safety, simplified fuel cycle and high power generation efficiency. However, the structure material of TMSR must encounter challenges of high-temperature environment and serious molten fluoride salts corrosion. Although the UNS N10003 alloy has excellent performance in TMSR, the high cost of this alloy reduces the economy of TMSR. Although the austenitic stainless steel possesses excellent high temperature strength and lower cost, it exhibits poor corrosion resistance in molten fluoride salts. Therefore, the purpose of this work is using Ni cladding on austenitic stainless steel by gas tungsten arc welding (GTAW) for corrosion protection and investigating the effects of thermal ageing on microstructure and hardness of cladding. The elements distribution and segregation, the precipitates behavior and the microstructure evolution of interface and cladding layer under as-welded and thermal ageing conditions were studied by a series of characterization methods respectively. The hardness evolution of claddings under as-welded and thermal ageing conditions were tested and discussed.

Intergranular corrosion of high temperature alloys in molten fluoride salts

2010 ◽  
Vol 27 (2) ◽  
pp. 145-149 ◽  
Author(s):  
Luke Olson ◽  
Kumar Sridharan ◽  
Mark Anderson ◽  
Todd Allen
Keyword(s):  
High Temperature ◽  
Intergranular Corrosion ◽  
High Temperature Alloys ◽  
Molten Fluoride ◽  
Fluoride Salts

An experimental test facility to support development of the fluoride-salt-cooled high-temperature reactor

2014 ◽  
Vol 64 ◽  
pp. 511-517 ◽  
Author(s):  
Graydon L. Yoder ◽  
Adam Aaron ◽  
Burns Cunningham ◽  
David Fugate ◽  
David Holcomb ◽  
...  
Keyword(s):  
High Temperature ◽  
Experimental Test ◽  
Test Facility ◽  
Fluoride Salt ◽  
High Temperature Reactor
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