Results 31 to 40 of about 7,764 (263)

New version of the reactor dynamics code DYN3D for Sodium cooled Fast Reactor analyses

open access: yes, 2017
The reactor dynamics code DYN3D being developed at the Helmholtz-Zentrum Dresden-Rossendorf is currently under extension for Sodium cooled Fast Reactor analyses.
S. Kliem   +3 more
core   +2 more sources

Safety Method for the Preconceptual Phase of Sodium-Cooled Fast Reactors

open access: yesJournal of Nuclear Engineering and Radiation Science, 2021
Abstract The European sodium fast reactor—safety measures assessment and research tools (ESFR-SMART) project (Contract number: 754501) focuses on the development of innovative safety design options for future sodium-cooled fast reactors (SFRs). The goal of this paper is to show how the objective provision tree (OPT) method, which is part
Ehster, Sophie   +5 more
openaire   +2 more sources

Sodium purification systems for NPP with fast reactors (retrospective and perspective views)

open access: yesNuclear Energy and Technology, 2016
Coolant purification systems constitute integral element of any reactor facility. A number of new tasks emerge in the current day reactor engineering, one of which is the task to enhance productivity and capacity of such systems.
F.A. Kozlov   +2 more
doaj   +1 more source

Application of genetic algorithms in optimization of SFR nuclear reactor design

open access: yesNukleonika, 2021
This work presents a demonstrational application of genetic algorithms (GAs) to solve sample optimization problems in the generation IV nuclear reactor core design.
Żurkowski Wojciech   +3 more
doaj   +1 more source

Application of the SCIANTIX fission gas behaviour module to the integral pin performance in sodium fast reactor irradiation conditions

open access: yesNuclear Engineering and Technology, 2022
The sodium-cooled fast reactor is among the innovative nuclear technologies selected in the framework of the development of Generation IV concepts, allowing the irradiation of uranium-plutonium mixed oxide fuels (MOX).
A. Magni   +4 more
doaj   +1 more source

Analysis of Fuel Burnup and Transmutations at High Burnup of Sodium Fast Breeder Reactor

open access: yesمجلة بغداد للعلوم, 2022
In this paper, the Monte Carlo N-Particle extended  computer code (MCNP) were used to design a model of the European Sodium-cooled Fast Reactor. The multiplication factor, conversion factor, delayed neutrons fraction, doppler constant, control rod worth,
Nehal Mohamed   +3 more
doaj   +1 more source

Study on Inherent Safety Characteristic on Thermal-hydraulic of Pool-type Sodium-cooled Fast Reactors

open access: yesYuanzineng kexue jishu, 2023
The concept of the inherent safety characteristic on thermal-hydraulic of the pool-type sodium-cooled fast reactor was proposed and its formation mechanism was analyzed.
ZHOU Zhiwei;XUE Xiuli;YANG Yong;YANG Hongyi
doaj  

Ultrasmall High‐Entropy Materials: Nanoscale Effects, Synthesis, and Mechanistic Insights

open access: yesAdvanced Functional Materials, EarlyView.
This review article focuses on sub‐10 nm high‐entropy materials that combine nanoscale design with complex compositions for next‐generation applications. ABSTRACT Ultrasmall high‐entropy nanomaterials (USHENMs, <10 nm) merge multicomponent chemistry with size‐dependent effects, forming a distinct class of materials with unprecedented properties.
Yueyue He   +5 more
wiley   +1 more source

Numerical Simulation of Natural Circulation Characteristic of Fast Reactor Passive Decay Heat Removal System Based on “1-D System+3-D CFD” Coupled Method

open access: yesYuanzineng kexue jishu
The sodium-cooled fast reactor is one of the important reactor types of the fourth-generation advanced nuclear energy system. The safety of sodium-cooled fast reactors is improved by introducing a new passive decay heat removal system.
LU Daogang1, 2, SONG Haijie1, 2, GUO Jinsong1, 2, ZHAO Haiqi1, 2, ZHANG Yuhao1, 2, , , SUI Danting1, 2
doaj   +1 more source

Experimental investigation of sodium boiling heat exchange in fuel subassembly mockup for perspective fast reactor safety substantiation

open access: yesNuclear Energy and Technology, 2015
Numerical modeling of ULOF-type accident development in sodium-cooled fast reactor carried out using the COREMELT code indicate the development and spreading of sodium boiling in the core accompanied with fluctuations of reactor technological parameters ...
R.R. Khafizov   +7 more
doaj   +1 more source

Home - About - Disclaimer - Privacy