Condition monitoring of an advanced gas-cooled nuclear reactor core [PDF]
, 2007 A critical component of an advanced gas-cooled reactor station is the graphite core. As a station ages, the graphite bricks that comprise the core can distort and may eventually crack.
Giovanini, L. +3 more
core +4 more sources
Monitoring a gas-cooled nuclear reactor core integrity [PDF]
, 2008 This work concerns with the problem of monitoring an Advanced Gas-cooled Nuclear Reactor (AGR) core. In the world wide context of energy production, the advanced gas-cooled reactor (AGR) nuclear power stations are approaching the end of their predicted ...
Grimble, Michael J. +4 more
core +4 more sources
Control rod monitoring of advanced gas-cooled reactors [PDF]
, 2010 The UK’s fleet of Advanced Gas Cooled Reactors (AGR) are approaching, and have in some cases exceeded, their original design lives. Continued operation is under enhanced safety cases based on monitoring, inspection and component condition assessment of ...
Mcarthur, Stephen +5 more
core +3 more sources
Modular High Temperature Gas-Cooled Reactor Commercialization and Generation Cost Estimates [PDF]
, 1993 Report on the cost estimates of modular high temperature gas cooled reactor commercialization and generation.
Gas-Cooled Reactor Associates +5 more
core +1 more source
Investigation of gas circulator response to load transients in nuclear power plant operation [PDF]
, 2012 Gas circulator units are a critical component of the Advanced Gas-cooled Reactor (AGR), one of the nuclear power plant (NPP) designs in current use within the UK.
Campbell, Graeme +3 more
core +3 more sources
Study on key parameters design of small helium xenon cooled reactor
He jishu, 2021 BackgroundThe fast breeder reactor using helium-xenon mixture gas as coolant combined with Brayton thermoelectric conversion system is the development trend of space nuclear power in the future.
HU Wenzhen +4 more
doaj +1 more source
CFD Investigation of MHTGR Natural Circulation and Decay Heat Removal in P-LOFC Accident
Frontiers 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
Thermal Characteristics of High Temperature Naturally Circulating Helium Cooling Loop
Journal of Mechanical Engineering, 2018 The paper deals with the process properties in terms of the heat transfer, i.e. the thermal performance of the thermal-process units within a helium loop intended for the testing of the decay heat removal (DHR) from the model of the gas-cooled fast ...
Dzianik František +2 more
doaj +1 more source
Semiempirical model for wet scrubbing of bubble rising in liquid pool of sodium-cooled fast reactor
Nuclear Engineering and Technology, 2018 Mechanistic calculations for wet scrubbing of aerosol/vapor from gas bubble rising in liquid pool are essential to safety of sodium-cooled fast reactor. Hence, scrubbing of volatile fission product from mixed gas bubble rising in sodium pool is presented
Arjun Pradeep, Anil Kumar Sharma
doaj +1 more source
Thermal study of the modular high-temperature gas-cooled reactor
Brazilian 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