Results 1 to 10 of about 18,606,918 (240)
After the first concrete was poured on December 9, 2012 at the Shidao Bay site in Rongcheng, Shandong Province, China, the construction of the reactor building for the world's first high-temperature gas-cooled reactor pebble-bed module (HTR-PM ...
Zuoyi Zhang +12 more
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Developing PCC and DCC integral effects test experiments at the High Temperature Test Facility
Among the Next-Generation Nuclear Plant (NGNP) designs, the High-Temperature Gas-Cooled Reactors (HTGRs) are very attractive, due to their inherent safety features, high power conversion efficiency, and potential of providing high-temperature process ...
Izabela Gutowska +2 more
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Simulation of the HTR-10 Operation History With the PANGU Code
The 10 MW High Temperature Gas-cooled Reactor-Test Module (HTR-10) is the first High Temperature Gas-cooled Reactor (HTGR) in China, which was operated from January 2003 to May 2007.
Ding She, Fubing Chen, Bing Xia, Lei Shi
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Accident occurrence frequency of a small helium-xenon gas cooled nuclear reactor system
BackgroundHelium-xenon gas cooled nuclear reactor adopts helium-xenon gas as the coolant and is able to apply the integral Brayton cycle. It has advantages in miniaturization and lightweight design, which has attracted more and more attention worldwide ...
WU Jianhui +6 more
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CFD Investigation of MHTGR Natural Circulation and Decay Heat Removal in P-LOFC Accident
One of the key postulated accidents in a high-temperature gas-cooled reactor (HTGR) is the pressurized loss of forced cooling (P-LOFC) of the primary loop, which can be triggered by its primary helium circulator trip or turbine trip.
Chengqi Wang +2 more
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Evaluation of failure fraction for high burnup High Temperature Gas-cooled Reactor fuel
In high temperature gas-cooled reactors (HTGRs), Tri-isotropic (TRISO)-coated fuel particles are employed as fuel. In the high burnup coated fuel particle, stress due to fission gas pressure and irradiation-induced pyrolytic carbon (PyC) shrinkage is ...
Kazuhiro SAWA, Masaya HASEDA, Jun AIHARA
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Exergy and exergoeconomic analysis of hydrogen and power cogeneration using an HTR plant
This paper proposes using sodium-cooled fast reactor technologies for use in hydrogen vapor methane (SMR) modification. Using three independent energy rings in the Russian BN-600 fast reactor, steam is generated in one of the steam-generating cycles with
Nima Norouzi +3 more
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Temperature Response of the HTR-10 during the Power Ascension Test
The 10 MW High Temperature Gas-Cooled Reactor-Test Module (HTR-10) is the first High Temperature Gas-Cooled Reactor in China. With the objective of raising the reactor power from 30% to 100% rated power, the power ascension test was planned and performed
Fubing Chen, Yujie Dong, Zuoyi Zhang
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Thermal study of the modular high-temperature gas-cooled reactor
The Modular High-Temperature Gas-Cooled Reactor (MHTGR) is an advanced power plant being a coupling between a modular helium cooled reactor and a gas turbine.
Antonella Lombardi Costa +4 more
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After a postulated design basis accident leads high temperature gas cooled reactor to emergency shutdown, steam generator still remains with high temperature level and needs to be cooled down by a precooling before reactor restarts with clearing of fault.
Yan Wang, Lei Shi, Yanhua Zheng
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