Results 11 to 20 of about 3,022 (226)
Nuclear Engineering and Technology, 2022 A hypothetical core destructive accident (HCDA) has received widespread attention as one of the most serious accidents in sodium-cooled fast reactors. This study combined recent advantages in numerical methods to realize realistic modeling of the complex
Zhihong Guo, Xiaodong Chen, Guoqing Hu
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Case Studies in Thermal Engineering, 2019 The aim of this paper is to present a fast-numerical tool based on the average channel approach to analyze the response of fast reactors under unprotected loss of flow events.
Alejandría-D. Pérez-Valseca +4 more
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Design Research on Steam Drain System of Fast Reactor Nuclear Power Plants
南方能源建设, 2021 [Introduction] The steam parameters of sodium-cooled fast reactor is different from PWR nuclear power or conventional fossil-fuel power plant, so it's necessary to restudy the drain system.
LIN Yan, YANG Daohong, SHI Haiyun
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CORE DESIGN ACTIVITIES OF THE VERSATILE TEST REACTOR – CONCEPTUAL PHASE [PDF]
EPJ Web of Conferences, 2021 The Versatile Test Reactor (VTR) is a new fast spectrum test reactor being developed in the United States under the direction of the US Department of Energy, Office of Nuclear Energy.
Heidet F., Roglans-Ribas J.
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Semiempirical model for wet scrubbing of bubble rising in liquid pool of sodium-cooled fast reactor
Nuclear Engineering and Technology, 2018 Mechanistic calculations for wet scrubbing of aerosol/vapor from gas bubble rising in liquid pool are essential to safety of sodium-cooled fast reactor. Hence, scrubbing of volatile fission product from mixed gas bubble rising in sodium pool is presented
Arjun Pradeep, Anil Kumar Sharma
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Soviet Atomic Energy, 1964 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
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Nuclear Energy and Technology, 2015 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
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Safety Method for the Preconceptual Phase of Sodium-Cooled Fast Reactors
Journal 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
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Sodium purification systems for NPP with fast reactors (retrospective and perspective views)
Nuclear 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
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Application of genetic algorithms in optimization of SFR nuclear reactor design
Nukleonika, 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
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