gas-cooled reactor


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gas-cooled reactor

[′gas ‚küld rē′ak·tər]
(nucleonics)
A nuclear reactor in which a gas, such as air, carbon dioxide, or helium, is used as a coolant.
References in periodicals archive ?
Jiang, "High temperature gas-cooled reactor project in Tsinghua University," in Proceedings of 21st-Century-COE Workshop on Energy and Environmental Issues in Asia, Kyoto, Japan, 2006.
Chen, "Studies on disintegrating spherical fuel elements of high temperature gas-cooled reactor by an electrochemical method," Journal of Nuclear Materials, vol.
Tompson, "Adsorption of iodine on graphite in High Temperature Gas-Cooled Reactor systems: a review," Progress in Nuclear Energy, vol.
Huang, Final Safety Analysis Report of the high temperature gas-cooled reactor pebble-bed module (HTR-PM), Institute of Nuclear and New Energy Technology, Tsinghua University, Beijing, China, 2016.
Duan et al., "Analysis of DR testing blind zone of spherical fuel elements for 10 MW high-temperature gas-cooled reactor," NDT & E International, vol.
Due to its inherent safety feature and potential economic competitiveness, the modular high temperature gas-cooled reactor (MHTGR) has already been seen as one of the best candidates in building the next generation nuclear plants.