Results 21 to 30 of about 56,882 (308)
Thermal-hydraulic analysis of a VVER-1000 core in MSLB conditions [PDF]
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
doaj +1 more source
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
doaj +1 more source
Thermal-hydraulically calculation for the Dalat nuclear research reactor [PDF]
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
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
doaj +1 more source
The role of a building’s thermal properties on pupils’ thermal comfort in junior school classrooms as determined in field studies [PDF]
Recent thermal comfort research in a light-weight junior school building showed that children were more sensitive to higher temperatures than adults and subsequently that current thermal comfort standards were not appropriate for the assessment of their ...
James, Patrick A.B. +5 more
core +1 more source
Thermal-hydraulic analysis of operated heat exchanger
The diploma thesis is focused on the thermal-hydraulic analysis of an operating heat exchanger in an ethylene evaporation unit. In the theoretical part of the thesis the design of shell and tube heat exchanger and the basics of the thermal-hydraulic ...
Chudý, Dávid
core +2 more sources
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
doaj +1 more source
COUPLED SIMULATION OF GAS COOLED FAST REACTOR FUEL ASSEMBLY WITH NESTLE CODE SYSTEM
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
doaj +1 more source
Development of multi-physics calculation method in lead cooled fast reactor code system MOSASAUR
A 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
doaj +1 more source
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
doaj +1 more source

