Results 21 to 30 of about 24,364 (164)

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

Unique safety features and licensing requirements of the NuScale small modular reactor

open access: yesFrontiers 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
doaj   +1 more source

Thermal Characteristics of High Temperature Naturally Circulating Helium Cooling Loop

open access: yesJournal 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

Numerical investigation of two-phase natural convection and temperature stratification phenomena in a rectangular enclosure with conjugate heat transfer

open access: yesNuclear 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
doaj   +1 more source

Numerical Simulation of Heat Transfer Enhancement in the Paths of Propulsion Systems with Single-Row Spherical and Oval Dimples on the Wall

open access: yesEnergies, 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
doaj   +1 more source

Numerical Simulation of Natural Circulation Characteristic of Fast Reactor Passive Decay Heat Removal System Based on “1-D System+3-D CFD” Coupled Method

open access: yesYuanzineng kexue jishu
The 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
doaj   +1 more source

Mathematical approach for optimization of magnetohydrodynamic circulation system

open access: yesNuclear 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
doaj   +1 more source

Hydrodynamic Properties of High Temperature Natural Circulating Helium Cooling Loop

open access: yesJournal of Mechanical Engineering, 2017
The paper deals with the hydrodynamic properties, i.e. the consumption of mechanical energy expressed by pressure drops within a helium loop intended for the testing of decay heat removal (DHR) from the model of a gas-cooled fast reactor (GFR).
Dzianik František, Gužela Štefan
doaj   +1 more source

Experimental validation of depletion calculations with VESTA 2.1.5 using JEFF-3.2

open access: yesEPJ Web of Conferences, 2017
The removal of decay heat is a significant safety concern in nuclear engineering for the operation of a nuclear reactor both in normal and accidental conditions and for intermediate and long term waste storage facilities.
Haeck Wim, Ichou Raphaëlle
doaj   +1 more source

ASSESSMENT OF CONDENSATION HEAT TRANSFER MODEL TO EVALUATE PERFORMANCE OF THE PASSIVE AUXILIARY FEEDWATER SYSTEM

open access: yesNuclear Engineering and Technology, 2013
As passive safety features for nuclear power plants receive increasing attention, various studies have been conducted to develop safety systems for 3rd-generation (GEN-III) nuclear power plants that are driven by passive systems.
YUN-JE CHO   +5 more
doaj   +1 more source

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