Results 11 to 20 of about 19,514,073 (287)

DECAY HEAT REMOVAL SYSTEM SYSTEM DESCRIPTION NO. 8 [PDF]

open access: yes, 1956
The decay heat removal system of the PWR is described. (T.R.H.)
openaire   +3 more sources

Decay Heat Removal in GEN IV Gas-Cooled Fast Reactors [PDF]

open access: yesScience and Technology of Nuclear Installations, 2009
The safety goal of the current designs of advanced high-temperature thermal gas-cooled reactors (HTRs) is that no core meltdown would occur in a depressurization event with a combination of concurrent safety system failures.
Lap-Yan Cheng, Thomas Y. C. Wei
doaj   +4 more sources

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

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   +2 more sources

CFD Analysis of the Passive Decay Heat Removal System of an LBE-Cooled Fast Reactor

open access: yesScience and Technology of Nuclear Installations, 2018
This paper presents capacity of the passive decay heat removal system (DHRS) operated under the natural circulation conditions to remove decay heat inside the main vessel of the Lead-bismuth eutectic cooled Fast Reactor (LFR).
Jiarun Mao   +5 more
doaj   +2 more sources

Design and modelling of underground decay heat removal system for a district heating reactor [PDF]

open access: yes, 2021
V današnjem svetu je jedrska energija uveljavljena kot čist in zanesljiv vir energije v omrežjih številnih držav. V luči doseganja ničelnih izpustov CO2 se raziskave o uporabi jedrske energije razvijajo v različne smeri. Daljinsko ogrevanje z jedrsko energijo je obetavno področje, o katerem razmišljajo zlasti številne severne države.
Dif, Brahim
core   +3 more sources

Decay Heat Removal and Transient Analysis in Accidental Conditions in the EFIT Reactor [PDF]

open access: yesScience and Technology of Nuclear Installations, 2008
The development of a conceptual design of an industrial-scale transmutation facility (EFIT) of several 100 MW thermal power based on accelerator-driven system (ADS) is addressed in the frame of the European EUROTRANS Integral Project. In normal operation,
Giacomino Bandini   +5 more
doaj   +2 more sources

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

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

Studies on surface condensation for passive safety system in light water reactor: A review [PDF]

open access: yesNuclear Technology and Radiation Protection, 2023
A system with a passive mechanism has been considered to have better trustworthiness because it does not require an external driving force to function.
Susyadi   +3 more
doaj   +1 more source

COMPARISON OF THE DECAY HEAT REMOVAL SYSTEMS IN THE KALIMER-600 AND DSFR [PDF]

open access: yesNuclear Engineering and Technology, 2012
A sodium-cooled demonstration fast reactor with the KALIMER-600 as a reference plant is under design by KAERI. The safety grade decay heat removal system (DHRS), which is important to mitigate design basis accidents, was changed in the reactor design.
Kwi-Seok Ha, Hae-Yong Jeong
openaire   +1 more source

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