Results 21 to 30 of about 7,764 (263)

Study on Influence of Upper Sodium Plenum Design on Coolant Boiling Transient in Large MOX Fuel Fast Reactor [PDF]

open access: yesYuanzineng kexue jishu
Unprotected loss of flow accident is severe for sodium-cooled fast reactor in that it will cause the boiling of sodium and then cause severe accident. For large MOX fuel sodium-cooled fast reactors, the sodium void reactivity is positive, which can make ...
ZHANG Xisi, LI Xinyu, HUO Xingkai, XU Li, LIU Yizhe, XUE Fangyuan
doaj   +2 more sources

Upsampling Monte Carlo Reactor Simulation Tallies in Depleted Sodium-Cooled Fast Reactor Assemblies Using a Convolutional Neural Network

open access: yesEnergies
The computational demand of neutron Monte Carlo transport simulations can increase rapidly with the spatial and energy resolution of tallied physical quantities.
Jessica Berry   +2 more
doaj   +2 more sources

Materials science research for sodium cooled fast reactors

open access: yesBulletin of Materials Science, 2009
The paper gives an insight into basic as well as applied research being carried out at the Indira Gandhi Centre for Atomic Research for the development of advanced materials for sodium cooled fast reactors towards extending the life of reactors to nearly 100 years and the burnup of fuel to 2,00,000 MWd/t with an objective of providing fast reactor ...
Baldev Raj,
openaire   +3 more sources

Determining the Sensitivity of Reactor Parameters in a Sodium Cooled Fast Reactor

open access: yes, 2020
The sensitivity of two operational output parameters, criticality and isotopic composition during burnup, to specific design and operational reactor parameters in a Sodium Cooled Fast Reactor, is investigated. The computational simulation tool Serpent is used.
Palfelt, Alexander   +2 more
openaire   +2 more sources

A Review of Models for the Sodium Boiling Phenomena in Sodium-Cooled Fast Reactor Subassemblies

open access: yes, 2022
International audienceThe Euratom Horizon-2020 project European sodium fast reactor safety measures assessment and research tools (ESFR-SMART) aims to enhance the safety and performance of the European sodium-cooled fast reactor (ESFR) considering safety
Tsige-Tamirat, Haileyesus   +8 more
core   +1 more source

Coolant Mixing in Sodium Cooled Fast Reactor Fuel Bundles. [PDF]

open access: yes, 1968
Radial subchannel temperature imbalances can be quite severe in typical fast reactor designs of tight pitch to diameter ratios. Consideration of mixing between interconnected subchannels is required to avoid the significant design penalties which would ...
Wilson, L. W.   +3 more
core   +1 more source

Reactor behavior comparisons for two liquid metal-cooled fast reactors during an event of loss of coolant

open access: yesCase Studies in Thermal Engineering, 2019
The aim of this paper is to present a fast-numerical tool based on the average channel approach to analyze the response of fast reactors under unprotected loss of flow events.
Alejandría-D. Pérez-Valseca   +4 more
doaj   +1 more source

Design Research on Steam Drain System of Fast Reactor Nuclear Power Plants

open access: yes南方能源建设, 2021
[Introduction] The steam parameters of sodium-cooled fast reactor is different from PWR nuclear power or conventional fossil-fuel power plant, so it's necessary to restudy the drain system.
LIN Yan, YANG Daohong, SHI Haiyun
doaj   +1 more source

CORE DESIGN ACTIVITIES OF THE VERSATILE TEST REACTOR – CONCEPTUAL PHASE [PDF]

open access: yesEPJ Web of Conferences, 2021
The Versatile Test Reactor (VTR) is a new fast spectrum test reactor being developed in the United States under the direction of the US Department of Energy, Office of Nuclear Energy.
Heidet F., Roglans-Ribas J.
doaj   +1 more source

Sodium-cooled fast reactors

open access: yesSoviet Atomic Energy, 1964
Based on the operational experience of the experimental fast reactor BR-5, the prototype of a full-scale fast-reactor power station of 350 Mwe and 1000 Mwt is being designed. Fuel elements are stainless steel tubes filled with uranium and plutonium dioxides, ribbed for spacing, and inserted into subassemblies. The radial blanket consists of cylindrical
A. I. Leipunskii   +5 more
openaire   +2 more sources

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