Results 21 to 30 of about 105,023 (307)
Thermal-hydraulic analysis of a VVER-1000 core in MSLB conditions [PDF]
E3S Web of Conferences, 2021 The objective of this paper is to analyze the ability of a VVER-1000 core and its control system to cope with a hypothetical main steam line break (MSLB) accident in case of multiple equipment failures.
Mitkov Svetlomir +2 more
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Problems of calculation of heat transfer crisis in fuel assembles of water cooled reactors [PDF]
Ядерна фізика та енергетика, 2018 Current problem of the ensuring reliability of the results of mathematical computer simulation of the operational modes of water-cooled nuclear reactors is considered in this article.
G. I. Sharaevsky +3 more
doaj +1 more source
Nuclear Engineering and Technology, 2020 Small Modular Reactors (SMRs) are attracting wide attention due to their outstanding performance, extensive studies have been carried out for lead-based fast reactors (LFRs) that cooled with Lead or Lead-bismuth (LBE), and small modular natural ...
Pengcheng Zhao, PhD +5 more
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Revista Investigaciones y Aplicaciones Nucleares, 2019 With cooperation of the International Atomic Energy Agency (IAEA), thermal-hydraulic calculations were carried out for conversion of the IAN-R1 Reactor from MTR-HEU fuel to TRIGA-LEU fuel. To establish thermal-hydraulic calculation and analysis research
José Antonio Sarta +1 more
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Convection Heat Transfer and Flow Calculations Suitable for Electric Machines Thermal Models [PDF]
, 2008 This paper deals with the formulations used to predict convection cooling and flow in electric machines. Empirical dimensionless analysis formulations are used to calculate convection heat transfer.
Cavagnino, Andrea, Staton, D.A.
core +1 more source
Thermal-hydraulically calculation for the Dalat nuclear research reactor [PDF]
Vietnam Journal of Mechanics, 1991 This paper concerns with thermal-hydraulically calculation for the core domain of the Dalat nuclear reactor in the nominal regime of works. On the base of this calculation some conclusions. On thermal safely of the reactor are conducted.
openaire +2 more sources
MATEC Web of Conferences, 2018 The lowering of the temperature graph in the lower-level heat networks is often carried out by a mixture of coolant from the return pipeline at mixing pumping stations in order to maintain the set temperature of the mixed water. In this case, part of the
Tokarev Vyacheslav, Novitsky Nikolay
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COUPLED SIMULATION OF GAS COOLED FAST REACTOR FUEL ASSEMBLY WITH NESTLE CODE SYSTEM
Acta Polytechnica CTU Proceedings, 2018 The paper is focused on coupled calculation of the Gas Cooled Fast Reactor. The proper modelling of coupled neutronics and thermal-hydraulics is the corner stone for future safety assessment of the control and emergency systems.
Filip Osusky +4 more
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Development of multi-physics calculation method in lead cooled fast reactor code system MOSASAUR
Nuclear Engineering and TechnologyA full-core three-dimensional multi-physics calculation method was researched based on the Lead cooled fast reactor (LFR) code system MOSASAUR, which is focused on both core steady-state and transient analyses of LFR. In the previous version of MOSASAUR,
Bin Zhang +3 more
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Известия высших учебных заведений: Проблемы энергетики, 2017 The application of the regenerative heat exchanger with a moving dense layer of solid heat carrier for heat recovery ash products conversion sulfur shale. The technique of hydraulic and thermal calculation of the regenerative heat exchanger with a moving
A. A. Morev +2 more
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