Results 31 to 40 of about 7,764 (263)
New version of the reactor dynamics code DYN3D for Sodium cooled Fast Reactor analyses
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
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)
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
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
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
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
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
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
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
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

