Results 31 to 40 of about 247,859 (329)

Neutronics Assessment of the Spatial Distributions of the Nuclear Loads on the DEMO Divertor ITER-like Targets: Comparison between the WCLL and HCPB Blanket

open access: yesApplied Sciences, 2023
The Plasma Facing Components (PFCs) of the divertor target contribute to the fundamental functions of heat removal and particle exhaust during fusion operation, being subjected to a very hostile and complex loading environment characterized by intense ...
Simone Noce   +8 more
doaj   +1 more source

Determination of Design Extension Conditions List and Design Optimization of Safety Systems for ADS by Lines of Defenses Method

open access: yesIEEE Access, 2018
During the conceptual design phase of an accelerator-driven sub-critical system (ADS), the reliability requirements of safety systems need to be determined for future practical construction to balance the economy performance with the safety performance ...
Zhao Xu, Lizhi Wang, Ming Jin
doaj   +1 more source

Neutron skins and neutron stars [PDF]

open access: yesAIP Conference Proceedings, 2013
The neutron-skin thickness of heavy nuclei provides a fundamental link to the equation of state of neutron-rich matter, and hence to the properties of neutron stars. The Lead Radius Experiment ("PREX") at Jefferson Laboratory has recently provided the first model-independence evidence on the existence of a neutron-rich skin in 208Pb.
openaire   +2 more sources

Reaction mechanisms in the 6Li+ 52Cr system

open access: yesEPJ Web of Conferences, 2015
Reactions induced by the weakly bound 6Li projectile interacting with the intermediate mass target 52Cr are investigated. The choice of this particular reaction in our study is because it is proposed as a surrogate reaction [6Li(52Cr, d)56Fe*] for the ...
Pandey Bhawna   +10 more
doaj   +1 more source

A rapid modeling method and accuracy criteria for common-cause failures in Risk Monitor PSA model

open access: yesNuclear Engineering and Technology, 2021
In the development of a Risk Monitor probabilistic safety assessment (PSA) model from the basic PSA model of a nuclear power plant, the modeling of common-cause failure (CCF) is very important.
Bing Zhang   +9 more
doaj   +1 more source

Implementation of Safety Aspects in IFMIF-DONES Design

open access: yesJournal of Nuclear Engineering, 2022
Integration of safety aspects in IFMIF-DONES design is a main objective of EUROfusion and European Commission projects. IFMIF-DONES will be a radioactive facility of the first category, and stringent safety objectives must be achieved and demonstrated. A
Francisco Martín-Fuertes   +11 more
doaj   +1 more source

CONCEPTUAL FUEL ELEMENT DESIGN CANDIDATES FOR CONVERSION OF HIGH FLUX ISOTOPE REACTOR WITH LOW-ENRICHED URANIUM SILICIDE DISPERSION FUEL* [PDF]

open access: yesEPJ Web of Conferences, 2021
Engineering design studies are underway to assess the feasibility of converting the High Flux Isotope Reactor (HFIR) to operate with low-enriched uranium silicide dispersion (LEU3Si2-Al) fuel. These studies are supported by the U.S.
Chandler D.   +4 more
doaj   +1 more source

A Consistent One-Dimensional Multigroup Diffusion Model for Molten Salt Reactor Neutronics Calculations

open access: yesJournal of Nuclear Engineering, 2023
Molten Salt Reactors (MSRs) have recently gained resurged research and development interest in the advanced reactor community. Several computational tools are being developed to capture the strong neutronics/thermal-hydraulics coupling effect in this ...
Mohamed Elhareef   +2 more
doaj   +1 more source

Neutronics analysis of JSI TRIGA Mark II reactor benchmark experiments with SuperMC3.3

open access: yesNuclear Engineering and Technology, 2019
Jozef Stefan Institute (JSI), TRIGA Mark II reactor employs the homogeneous mixture of uranium and zirconium hydride fuel type. Since its upgrade, a series of fresh fuel steady state experimental benchmarks have been conducted. The benchmark results have
Wanbin Tan   +4 more
doaj   +1 more source

Research on Neutronics/Thermal-hydraulics Coupling Effect of CFETR Blanket

open access: yesYuanzineng kexue jishu, 2022
Chinese Fusion Engineering Test Reactor (CFETR) has been proposed to bridge the technology gap between the International Thermonuclear Experimental Reactor (ITER) and the Fusion Demonstration Reactor (DEMO). As the most crucial nuclear component, fusion
DAI Tao;CAO Liangzhi;HE Qingming;WU Hongchun
doaj  

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