Results 41 to 50 of about 2,419,768 (239)
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
Mixed nitride uranium–plutonium fuel is the most attractive and advanced type of fuel for fast-neutron sodium-cooled reactors, and is considered as the base fuel for future commercial fast-neutron power reactors.
V.I. Matveev +2 more
doaj +1 more source
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
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 +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
A large‐area, deformable high‐entropy‐ceramic (HEC)‐doped triboelectric nanogenerator with a trilayer architecture is developed, consisting of an HEC‐doped triboelectric layer, a graphite‐like textile charge‐storage layer, and stretchable carbon black electrodes.
Shengyou Li +13 more
wiley +1 more source

