Results 11 to 20 of about 36,342 (264)
A Preliminary Safety Analysis for the Prototype Gen IV Sodium-Cooled Fast Reactor
Nuclear Engineering and Technology, 2016 Korea Atomic Energy Research Institute has been developing a pool-type sodium-cooled fast reactor of the Prototype Gen-IV Sodium-cooled Fast Reactor (PGSFR).
Kwi Lim Lee +9 more
doaj +3 more sources
Thermodynamic analysis and preliminary design of closed Brayton cycle using nitrogen as working fluid and coupled to small modular Sodium-cooled fast reactor (SM-SFR) [PDF]
Applied Energy, 2017 © 2017Sodium-cooled fast reactor (SFR) is considered the most promising of the Generation IV reactors for their near-term demonstration of power generation.
Kelsall, G., Olumayegun, O., Wang, M.
core +3 more sources
Stability characteristics of the 500 mw Indian PFBR [PDF]
Nuclear Technology and Radiation Protection, 2015 After the successful operation of the fast breeder test reactor for over two decades, India is now nearing the completion of a 500 MW (electrical) prototype fast breeder reactor. This commercial scale power reactor is a sodium-cooled, pool-type,
Anuraj Vijayan L. +2 more
doaj +1 more source
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
doaj +1 more source
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
doaj +1 more source
Kajian Perkembangan Pltn Generasi IV [PDF]
, 2013 STATUS TERKINI PERKEMBANGAN PLTN GENERASI IV. Saat ini perkembangan teknologi PLTN telah mencapai tahap penelitian dan pengembangan PLTN Generasi IV (sistem reaktor maju) yang merupakan pengembangan inovatif dari PLTN generasi sebelumnya.
Anggoro, Y. D. (Yohanes) +3 more
core +2 more sources
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
doaj +1 more source
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.
doaj +1 more source
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
doaj +1 more source
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
openaire +2 more sources