Results 31 to 40 of about 2,651,698 (166)
RELAP5-3D Code Includes ATHENA Features and Models [PDF]
Volume 2: Thermal Hydraulics, 2006 Version 2.3 of the RELAP5-3D computer program includes all features and models previously available only in the ATHENA version of the code. These include the addition of new working fluids (i.e., ammonia, blood, carbon dioxide, glycerol, helium, hydrogen, lead-bismuth, lithium, lithium-lead, nitrogen, potassium, sodium, and sodium-potassium) and a ...
Riemke, Richard A. +2 more
openaire +1 more source
Reactivity feedback effect on loss of flow accident in PWR
Nuclear Engineering and Technology, 2018 In this work, the reactor kinetics capability is used to compute the design safety parameters in a PWR due to complete loss of coolant flow during protected and unprotected accidents.
Basma Foad +2 more
doaj +1 more source
RELAP5 Modeling of a Siphon Break Effect on the Brazilian Multipurpose Reactor
Brazilian Journal of Radiation Sciences, 2021 This work presents the thermal-hydraulic simulation of the Brazilian Multipurpose Reactor (RMB) using the RELAP5/Mod3 code. The RMB will provide Brazil with a fundamental infrastructure for the national development on activities of the nuclear sector in ...
Humberto Vitor Soares +2 more
doaj +1 more source
Numerical Study on Laminar-Turbulent Transition Flow in Rectangular Channels of a Nuclear Reactor
Frontiers in Energy Research, 2020 Laminar-turbulent transition flow can be observed in thermal engineering applications, but the flow resistance and heat transfer characteristics are not fully understood.
Zhenying Wang +6 more
doaj +1 more source
, 2018 As in many other energy generating system, in the nuclear power plant, the use of natural circulation principle for the safety system is increasingly considered.
A. R. Antariksawan +5 more
semanticscholar +1 more source
Thermal-Hydraulics analysis of pressurized water reactor core by using single heated channel model [PDF]
Journal of Applied and Computational Mechanics, 2017 Thermal hydraulics of nuclear reactor as a basis of reactor safety has a very important role in reactor design and control. The thermal-hydraulic analysis provides input data to the reactor-physics analysis, whereas the latter gives information about the
Reza Akbari +2 more
doaj +1 more source
RELAP5 Calculations of Bethsy 9.1b Test
Science and Technology of Nuclear Installations, 2012 Recently, several advanced computational tools for simulating reactor system behavior during real and hypothetical transient scenarios were developed.
Andrej Prošek
doaj +1 more source
Recent Hydrodynamics Improvements to the RELAP5-3D Code [PDF]
Volume 3: Thermal Hydraulics; Current Advanced Reactors: Plant Design, Construction, Workforce and Public Acceptance, 2009 The hydrodynamics section of the RELAP5-3D computer program has been recently improved. Changes were made as follows: (1) improved turbine model, (2) spray model for the pressurizer model, (3) feedwater heater model, (4) radionuclide transport model, (5) improved pump model, and (6) compressor model. These changes will be discussed.
Riemke, Richard A. +2 more
openaire +1 more source
Assessment of RELAP/SCDAPSIM/MOD3.4 Prediction Capability with Severe Fuel Damage Scoping Test
Science and Technology of Nuclear Installations, 2017 The Power Burst Facility (PBF) was designed to provide experimental data to determine the thresholds for failure during accident conditions. Thus, the PBF benchmark using severe accidental analysis codes is essential to designing reactor for current ...
Noppawan Rattanadecho +4 more
doaj +1 more source
Loss of offsite power accident analysis in a VVER-1000/V446 nuclear power plant [PDF]
Nuclear Technology and Radiation Protection, 2019 The aim of this study is to present a thermo-hydraulic analysis of the loss of offsite power accident in VVER-1000/V446 nuclear power plant using the RELAP5 code.
Esfandiari Mohsen +3 more
doaj +1 more source