Results 41 to 50 of about 99,355 (324)
Mechanical Engineering Journal, 2022 A direct reactor auxiliary cooling system (DRACS) under natural circulation (NC) conditions with a dipped-type direct heat exchanger (D-DHX) in the upper plenum of a reactor vessel (RV) has been investigated for enhancing the safety of sodium-cooled fast
Erina HAMASE +5 more
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Unique safety features and licensing requirements of the NuScale small modular reactor
Frontiers in Energy Research, 2023 Small modular reactors (SMR) offer a novel approach to the construction and operation of nuclear power plants. The NuScale VOYGR™ plant uses a simplified SMR design that is based on proven light-water reactor technology with substantial improvements in ...
Kent Welter +2 more
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Simulation of Steady States of Helium Loop at Long Time Scenarios [PDF]
MATEC Web of Conferences, 2020 The natural circulation helium loop is an experimental facility designed for the research of the possibility of utilizing natural convection cooling for the case of decay heat removal from a fast nuclear reactor.
Világi František +6 more
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Passive decay heat removal system for water-cooled nuclear reactors [PDF]
, 1990 This document describes passive decay-heat removal system for a water-cooled nuclear reactor which employs a closed heat transfer loop having heat-exchanging coils inside an open-topped, insulated evaporator located inside the reactor vessel, below its ...
Forseberg, C.W.
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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
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Journal of Nuclear Engineering and Radiation Science, 2020 In the frame of the ESFR-SMART European project, aiming at improving the safety level of the European sodium cooled fast reactor (ESFR), this paper presents the preliminary assessment of decay heat removal systems (DHRSs) in the ESFR-SMART design: the ...
Jeremy Bittan, C. Bore, J. Guidez
semanticscholar +1 more source
Yuanzineng kexue jishuThe sodium-cooled fast reactor is one of the important reactor types of the fourth-generation advanced nuclear energy system. The safety of sodium-cooled fast reactors is improved by introducing a new passive decay heat removal system.
LU Daogang1, 2, SONG Haijie1, 2, GUO Jinsong1, 2, ZHAO Haiqi1, 2, ZHANG Yuhao1, 2, , , SUI Danting1, 2
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Mathematical approach for optimization of magnetohydrodynamic circulation system
Nuclear Engineering and Technology, 2019 The geometrical and electromagnetic variables of a rectangular-type magnetohydrodynamic (MHD) circulation system are optimized to solve MHD equations for the active decay heat removal system of a prototype Gen-IV sodium fast reactor.
Geun Hyeong Lee, Hee Reyoung Kim
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Nuclear Engineering and Technology, 2020 Natural convection and thermal stratification phenomena are found in large water pools that are being used as heat sinks for decay heat removal from the reactor core using passive heat removal systems. In this study, the two-phase (water and air) natural
Audrius Graževičius +2 more
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Energies, 2022 Modeling the vortex intensification of turbulent heat transfer in narrow engine ducts using single-row dimples was carried out within the framework of multi-block computing technologies implemented in a special VP2/3 package.
Sergey Isaev +6 more
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