Results 1 to 10 of about 18,606,918 (240)

The Shandong Shidao Bay 200 MWe High-Temperature Gas-Cooled Reactor Pebble-Bed Module (HTR-PM) Demonstration Power Plant: An Engineering and Technological Innovation

open access: yesEngineering, 2016
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
doaj   +3 more sources

Developing PCC and DCC integral effects test experiments at the High Temperature Test Facility

open access: yesFrontiers in Energy Research, 2023
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
doaj   +1 more source

Simulation of the HTR-10 Operation History With the PANGU Code

open access: yesFrontiers in Energy Research, 2021
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
doaj   +1 more source

Accident occurrence frequency of a small helium-xenon gas cooled nuclear reactor system

open access: yesHe jishu, 2022
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
doaj   +1 more source

CFD Investigation of MHTGR Natural Circulation and Decay Heat Removal in P-LOFC Accident

open access: yesFrontiers in Energy Research, 2020
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
doaj   +1 more source

Evaluation of failure fraction for high burnup High Temperature Gas-cooled Reactor fuel

open access: yesNihon Kikai Gakkai ronbunshu, 2023
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
doaj   +1 more source

Exergy and exergoeconomic analysis of hydrogen and power cogeneration using an HTR plant

open access: yesNuclear Engineering and Technology, 2021
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
doaj   +1 more source

Temperature Response of the HTR-10 during the Power Ascension Test

open access: yesScience and Technology of Nuclear Installations, 2015
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
doaj   +1 more source

Thermal study of the modular high-temperature gas-cooled reactor

open access: yesBrazilian Journal of Radiation Sciences, 2022
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
doaj  

Analysis of Precooling Injection Transient of Steam Generator for High Temperature Gas Cooled Reactor

open access: yesScience and Technology of Nuclear Installations, 2017
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
doaj   +1 more source

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