Results 1 to 10 of about 183,014 (291)

Multivariate polynomial fit: Decay heat removal system and pectin degrading Fe3 O4 -SiO2 nanobiocatalyst activity. [PDF]

open access: yesIET Nanobiotechnol, 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. (1) For an effective fabrication of Pectin degrading Fe3 O4 -SiO2 Nanobiocatalyst activity (IU/mg). Here, the three parameters namely: pH value, pectinase loading
Muthusamy B   +3 more
europepmc   +4 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-hydraulic characteristics of the PRHRS under Station-Black-Out (SBO) accident condition. The results showed
Hu Chongju   +6 more
openaire   +2 more sources

Peningkatan Kinerja Sistem Keselamatan Pasif Pada Reaktor Nuklir Dengan Penambahan Komponen Rvacs [PDF]

open access: yesJurnal Pendidikan Fisika Indonesia, 2014
Completeness of passive safety systems and inherent in advanced reactors is a major prerequisite. This paper explores the results of a conceptual design of the heat removal system at the nuclear power plant (NPP) type Very High-Temperature Reactor.
Abdullah, A. G. (A)   +2 more
core   +4 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

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

Analysis of ESFR Decay Heat Removal Systems in Protected Station Blackout

open access: yesJournal of Nuclear Engineering and Radiation Science, 2021
Abstract As part of the European sodium fast reactor (ESFR)-safety measures assessment and research tools (SMART) project, safety assessments are being conducted on the updated ESFR design. An important part of the study is the evaluation of the reactor's behavior within hypothetical accidental conditions to assess and ensure that the ...
Bodi, Janos   +3 more
openaire   +2 more sources

Dynamic Hybrid Reliability Studies of a Decay Heat Removal System [PDF]

open access: yesInternational Journal of Reliability, Quality and Safety Engineering, 2015
Some critical safety systems exhibit the characteristics of hybrid stochastic class whose performance depends on the dynamic interactions of deterministic variables of physical phenomena and probabilistic variables of system failures. However, conventional probabilistic safety assessment (PSA) method involves static event and linked fault tree analysis
Kumar, Ranjan   +4 more
openaire   +2 more sources

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

Heat removal system for shutdown in nuclear thermal rockets and advanced concepts [PDF]

open access: yes, 2017
© 2016 by the American Institute of Aeronautics and Astronautics, Inc.It is well-known that a nuclear thermal rocket (NTR) cannot be abruptly shut down. After a power manoeuver, the reactor has contaminated itself with fission products and the decay heat
Arias Montenegro, Francisco Javier   +1 more
core   +2 more sources

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