Results 21 to 30 of about 3,177,092 (292)
Development and validation of reactor nuclear design code CORCA-3D
Nuclear Engineering and Technology, 2019 The advanced node core code CORCA-3D is one of the independent developed codes of NPIC for the nuclear reactor core design. CORCA-3D code can calculate the few-group cross section, solve the 3D diffusion equations, consider the thermal-hydraulic feedback,
Ping An +5 more
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Increasing the thermal efficiency of water heating boilers by improving design parameters [PDF]
E3S Web of Conferences, 2023 Currently, research is being conducted all over the world to create clearly defined operating, technological and design parameters that ensure the continuity of hydrodynamic and thermal processes, which will improve the energy efficiency of heat supply ...
Arifjanov Aybek, Kurbonov Kozim
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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
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Thermal-hydraulic analysis of light water reactors under different steady-state operating conditions, Part 1: Boiling water reactor [PDF]
Nuclear Technology and Radiation Protection, 2022 The steady-state thermal-hydraulic analysis of the core of the Boiling Water Reactor (BWR/6) at nominal operating conditions is presented in this paper. The BWR/6 is produced by General Electric USA.
Hutli Ezddin, Kridan Ramadan
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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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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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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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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
Thermal-hydraulic analysis on quench behavior of indium-tin soldered REBCO composite conductor
, 2020 data of Thermal-hydraulic analysis on quench behavior of indium-tin soldered REBCO composite ...
zhengshuo zhang (8475828)
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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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