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REACTOR PHYSICS EXPERIMENT IN A GRAPHITE-MODERATION SYSTEM FOR HTGR [PDF]

open access: yesEPJ Web of Conferences, 2021
The Japan Atomic Energy Agency (JAEA) started the Research and Development (R&D) to improve nuclear prediction techniques for High Temperature Gas-cooled Reactors (HTGRs).
Fukaya Y.   +7 more
doaj   +1 more source

Development of adjusted nuclear data library for fast reactor application [PDF]

open access: yesEPJ Web of Conferences, 2023
In Japan, development of adjusted nuclear data library for fast rector application based on the cross-section adjustment method has been conducted since the early 1990s.
Yokoyama Kenji
doaj   +1 more source

Structural analysis of a reactor vessel in a sodium-cooled fast reactor under extremely high temperature conditions

open access: yesMechanical Engineering Journal, 2023
To enhance resilience of next-generation nuclear structures, it is necessary to develop design methodology that mitigates impacts of failure caused by extremely high temperature conditions which might lead to a severe accident.
Hidemasa YAMANO   +2 more
doaj   +1 more source

Applicability evaluation of Akaike’s Bayesian information criterion to covariance modeling in the cross-section adjustment method [PDF]

open access: yesEPJ Web of Conferences, 2023
The applicability of Akaike’s Bayesian Information Criterion (ABIC) to the covariance modeling in the cross-section adjustment method has been investigated.
Maruyama Shuhei   +2 more
doaj   +1 more source

Kinetic study on eutectic reaction between boron carbide and stainless steel by differential thermal analysis

open access: yesMechanical Engineering Journal, 2021
In a postulated severe accidental condition of sodium-cooled fast reactor (SFR), the eutectic reaction between boron carbide (B4C) as control rod element and stainless steel (SS) as control rod cladding or related structure materials may take place. Thus,
Shin KIKUCHI   +2 more
doaj   +1 more source

Simulating a lead-cooled reactor campaign using the EUCLID/V1 code [PDF]

open access: yesNuclear Energy and Technology, 2022
The paper presents the results of the development of the EUCLID/V1 integrated dynamic code designed to analyze and justify the safety of fast neutron reactor facilities with a liquid-metal coolant, in terms of simulating the reactor campaign.
Aleksandr A. Belov   +7 more
doaj   +3 more sources

Economic Dispatch Model of Nuclear High-Temperature Reactor with Hydrogen Cogeneration in Electricity Market

open access: yesEnergies, 2021
Hydrogen produced without carbon emissions could be a useful fuel as nations look to decarbonize their electricity, transport, and industry sectors.
James Richards   +4 more
doaj   +1 more source

Comparative evaluation of response reliability during accidents in light water reactors and fast reactors

open access: yesMechanical Engineering Journal, 2020
To identify functions and facilities that are critical for ensuring safety in advanced reactors, for which only a limited usage history is available, it is necessary to consider the characteristics of each reactor type by utilizing more risk-related ...
Masaaki SUZUKI   +3 more
doaj   +1 more source

Development and validation of fuel stub motion model for the disrupted core of a sodium-cooled fast reactor

open access: yesNuclear Engineering and Technology, 2021
To improve the capability of the SAS4A code, which simulates the initiating phase of core disruptive accidents for MOX-fueled Sodium-cooled Fast Reactors (SFRs), the authors have investigated in detail the physical phenomena under unprotected loss-of ...
Kenichi Kawada, Tohru Suzuki
doaj   +1 more source

The Promising Features of New Nano Liquid Metals—Liquid Sodium Containing Titanium Nanoparticles (LSnanop)

open access: yesMetals, 2015
A new kind of suspension liquid was developed by dispersing Ti nanoparticles (10 nm) in liquid Na, which was then determined by TEM (transmission electron microscopy) analysis.
Toshio Itami   +2 more
doaj   +1 more source

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