Results 1 to 10 of about 24,364 (164)

Multivariate polynomial fit: Decay heat removal system and pectin degrading Fe3O4‐SiO2 nanobiocatalyst activity [PDF]

open access: yesIET Nanobiotechnology, 2021
Herein, multivariate Lagrange's interpolation polynomial (MLIP) and multivariate least square (MLS) methods are used to derive linear and higher‐order polynomials for two varied applications.
Boopathi Muthusamy   +3 more
doaj   +2 more sources

Analysis on passive residual heat removal system with heat pipes for longterm decay heat removal of small lead-based reactor [PDF]

open access: yesE3S Web of Conferences, 2021
.A lead-based reactor with employing heat pipes as passive residual heat removal system (PRHRS) for longterm decay heat removal was designed. Three-dimensional computational fluid dynamics (CFD) software FLUENT was adopted to simulate the thermal ...
Hu Chongju   +6 more
doaj   +2 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   +2 more sources

Start-up, operation and thermal-hydraulic analysis of a self-propelling supercritical CO2 heat removal system coupled to a pressurized water reactor

open access: yesEPJ Nuclear Sciences & Technologies, 2022
The supercritical carbon dioxide (sCO21) heat removal system, which is based on a closed Brayton cycle with sCO2 as a working fluid, is an innovative, self-propelling and modular heat removal system for existing and future nuclear power plants.
Hofer Markus   +3 more
doaj   +1 more source

Development of probabilistic risk assessment methodology against strong wind for sodium-cooled fast reactors

open access: yesMechanical Engineering Journal, 2023
For nuclear power plants, probabilistic risk assessment (PRA) should be performed not only against earthquake and tsunami, which are critical events especially in Japan, but also other external hazards such as strong wind. The aim of the present study is
Hiroyuki NISHINO   +2 more
doaj   +1 more source

Analysis on short-term decay heat after shutdown during load-follow operation with seasonal and daily scenarios

open access: yesNuclear Engineering and Technology, 2022
For the future energy-mix policy for carbon neutrality, demand for the capability of load-follow operation has emerged in nuclear power plants in order to accommodate the intermittency of renewable energy.
Dae Hee Hwang, Yonghee Kim
doaj   +1 more source

A new method for characterizing the heat transfer capacity of the divertor and high heat flux components

open access: yesNuclear Fusion, 2023
The divertor is usually exposed to extreme incident heat flux conditions in nuclear fusion engineering and its ability to remove the heat is extremely crucial for the safe operation of magnetic confinement nuclear fusion device.
Qianqian Lin   +5 more
doaj   +1 more source

ELSMOR European Project: Experimental Results on an Innovative Decay Heat Removal System Based on a Plate-Type Heat Exchanger

open access: yesScience and Technology of Nuclear Installations, 2023
This paper summarises the results of an experimental campaign carried out at SIET on the ELSMOR facility built in 2022 to validate a decay heat removal system for the E-SMR.
Roberta Ferri   +7 more
doaj   +1 more source

Fade-out time shortening on radiotoxicity and decay heat using TRU generation reduction fuel

open access: yesMechanical Engineering Journal, 2023
We analyzed the possibility of TRU generation reduction fuel using HALEU as the initial enrichment to reduce the radiotoxicity and decay heat of TRU when using the LWR fuels that can suppress radiotoxicity and decay heat in HLW. Fade-out time was defined
Kouji HIRAIWA   +6 more
doaj   +1 more source

CLIRA DECAY HEAT REMOVAL TEST. [PDF]

open access: yes, 1972
This report describes the design and fabrication of an electrically heated test section that was used to simulate the heat transport associated with the handling, after irradiation and discharge from the reactor vessel, of a fueled Fast Flux Test Facility (FFTF) closed loop test assembly while in the air-cooled ex-vessel handling machine.
Winegardner, W. K., Romsos, W. N.
openaire   +2 more sources

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