Results 31 to 40 of about 2,419,768 (239)
Nuclear Engineering and Technology, 2019 This paper presents the drop performance test of the control rod assembly which is one of the main components strongly related to the safety of the prototype generation IV sodium-cooled fast reactor.
Jin Gwan Son +4 more
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Nuclear Engineering and Technology, 2020 As the refueling of a sodium-cooled fast reactor is conducted by rotating part of the reactor head without opening it, the monitoring of existing obstacles that can disturb the rotation of the reactor head is one of the most important issues.
Hoe-Woong Kim +3 more
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Modular High Temperature Gas-Cooled Reactor Commercialization and Generation Cost Estimates [PDF]
, 1993 Report on the cost estimates of modular high temperature gas cooled reactor commercialization and generation.
Gas-Cooled Reactor Associates +5 more
core +1 more source
COUPLED MODELLING OF THE EBR-II SHRT-45R INCLUDING PHOTON HEAT DEPOSITION [PDF]
EPJ Web of Conferences, 2021 The Fast REactor NEutronics/Thermal-hydraulICs (FRENETIC) code has been developed during the last years at Politecnico di Torino, implementing a full-core coupled neutronic/thermal-hydraulics model for steady-state and transient analysis of liquid-metal ...
Valerio Domenico +4 more
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Coolant Mixing in Sodium Cooled Fast Reactor Fuel Bundles. [PDF]
, 1968 Radial subchannel temperature imbalances can be quite severe in typical fast reactor designs of tight pitch to diameter ratios. Consideration of mixing between interconnected subchannels is required to avoid the significant design penalties which would ...
Wilson, L. W. +3 more
core +1 more source
FAST REACTOR MULTIPHYSICS AND UNCERTAINTY PROPAGATION WITHIN WIMS [PDF]
EPJ Web of Conferences, 2021 For liquid metal-cooled fast reactors (LMFRs), improved predictive modelling is desirable to facilitate reactor licensing and operation and move towards a best estimate plus uncertainty (BEPU) approach.
Lindley Ben +9 more
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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
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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.
doaj +1 more source