Conceptual design and analysis of heat pipe cooled silo cooling system for the transportable fluoride-salt-cooled high-temperature reactor

2017 ◽  
Vol 109 ◽  
pp. 458-468 ◽  
Author(s):  
Chenglong Wang ◽  
Limin Liu ◽  
Minghao Liu ◽  
Dalin Zhang ◽  
Wenxi Tian ◽  
...  
Keyword(s):  
High Temperature ◽  
Heat Pipe ◽  
Conceptual Design ◽  
Cooling System ◽  
Fluoride Salt ◽  
High Temperature Reactor

scholarly journals Pre-Conceptual Design of a Fluoride-Salt-Cooled Small Modular Advanced High Temperature Reactor (SmAHTR)

2011 ◽  
Author(s):  
Sherrell R Greene ◽  
Jess C Gehin ◽  
David Eugene Holcomb ◽  
Juan J Carbajo ◽  
Dan Ilas ◽  
...  
Keyword(s):  
High Temperature ◽  
Conceptual Design ◽  
Fluoride Salt ◽  
High Temperature Reactor

Preferred core conceptual design of pebble bed advanced high temperature reactor

2021 ◽  
Vol 151 ◽  
pp. 107983
Author(s):  
Lianjie Wang ◽  
Wei Sun ◽  
Bangyang Xia ◽  
Yang Zou ◽  
Rui Yan
Keyword(s):  
High Temperature ◽  
Conceptual Design ◽  
Pebble Bed ◽  
High Temperature Reactor

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

Performance Evaluation of DRACS System for FHTR and Time Assessment of Operation Procedure

2013 ◽  
Author(s):  
Junya Nakata ◽  
Mikihiro Wakui ◽  
Michitsugu Mori ◽  
Hiroto Sakashita ◽  
Charles Forsberg
Keyword(s):  
Performance Evaluation ◽  
High Temperature ◽  
Cooling System ◽  
Heat Removal ◽  
Severe Accident ◽  
Air Cooling ◽  
Fluoride Salt ◽  
Nuclear Power Reactor ◽  
Decay Heat ◽  
Operation Procedure

The Fluoride-salt-cooled High-temperature Reactor (FHR) is a new concept of nuclear power reactor being investigated mainly in U.S. and China. The coolant is a liquid salt with a melting point of about 460°C and a boiling point of over 1400°C. As the baseline decay heat removal system, a passive Direct Reactor Air Cooling System (DRACS) is utilized. Though DRACS system has been developed in Sodium Fast reactors (SFR), there are some differences between both. For example, the system in FHR must decrease heat removal when temperatures are low to avoid freezing of the salt and blocking the flow of liquid. Therefore, considering its characteristics, a numerical investigation of DRACS system is needed to evaluate whether FHR has proper ability to remove decay heat and to be robust for a long-time cooling operation after even a severe accident. Furthermore, in addition to its performance evaluation, it is required to make up the operation plan of FHR considering features of this system. It is highly important, with the view of avoiding severe accident, to determine by when the system should be started up. In both countries mentioned above, Fluoride-salt-cooled High-temperature Test Reactor (FHTR) is currently in progress to build. Reviewing its design and system is a crucial step needed to develop the FHR technology. In this research, a performance of DRACS system under some thermal-hydraulic basic events was evaluated by numerical simulation. This paper also suggested the adequate operation procedure suitable for FHTR to avoid a severe accident.

scholarly journals Preliminary Experiment of U-Shaped Heat Pipe as Passive Cooling System in High Temperature Gas-Cooled Reactor Cooling Tank

2019 ◽  
Vol 1198 (2) ◽  
pp. 022055
Author(s):  
Mukhsinun Hadi Kusuma ◽  
Anhar Riza Antariksawan ◽  
Giarno ◽  
Sri Ismarwanti ◽  
Mulya Juarsa ◽  
...  
Keyword(s):  
High Temperature ◽  
Heat Pipe ◽  
Cooling System ◽  
Passive Cooling ◽  
Passive Cooling System ◽  
High Temperature Gas

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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