Results 21 to 30 of about 1,033,988 (155)
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
International Journal of Energy Research, Volume 44, Issue 5, Page 3295-3315, April 2020., 2020 Summary Simulation is becoming increasingly important in the safety analysis of nuclear reactors nowadays. The physical phenomena in a nuclear power plant happen on three classified scales: system scale (phenomenon over the whole plant is concerned), component scale (phenomenon in specific component is concerned), and mesoscale (phenomenon in a small ...
Kanglong Zhang
wiley +1 more source
Thermal Hydraulic and Neutronics Coupling Analysis for Plate Type Fuel in Nuclear Reactor Core
Science and Technology of Nuclear Installations, Volume 2020, Issue 1, 2020., 2020 The thermal hydraulic and neutronics coupling analysis is an important part of the high‐fidelity simulation for nuclear reactor core. In this paper, a thermal hydraulic and neutronics coupling method was proposed for the plate type fuel reactor core based on the Fluent and Monte Carlo code.
Linrong Ye +8 more
wiley +1 more source
Automated, Highly Accurate Verification of RELAP5-3D [PDF]
Volume 2B: Thermal Hydraulics, 2014 Computer programs that analyze light water reactor safety solve complex systems of governing, closure and special process equations to model the underlying physics. In addition, these programs incorporate many other features and are quite large. RELAP5-3D[1] has over 300,000 lines of coding for physics, input, output, data management, user-interaction,
George L. Mesina +2 more
openaire +1 more source
Science and Technology of Nuclear Installations, Volume 2020, Issue 1, 2020., 2020 Multiphysics coupling of neutronics/thermal‐hydraulics models is essential for accurate modeling of nuclear reactor systems with physics feedback. In this work, SCALE/TRACE coupling is used for neutronic analysis and spent fuel validation of BWR assemblies, which have strong coolant feedback.
Dean Price +5 more
wiley +1 more source
Science and Technology of Nuclear Installations, 2010 The Institute of Neutron Physics and Reactor Technology (INR) is involved in the qualification of coupled codes for reactor safety evaluations, aiming to improve their prediction capability and acceptability.
V. Sánchez +3 more
doaj +1 more source
TRISO fuel thermal simulations in the LS-VHTR
Brazilian Journal of Radiation Sciences, 2019 The liquid-salt-cooled very high-temperature reactor (LS-VHTR) is a reactor that presents very good characteristics in terms of energy production and safety aspects.
Mario C. Ramos +4 more
doaj +1 more source
A PVM Executive Program for Use With RELAP5-3D© [PDF]
10th International Conference on Nuclear Engineering, Volume 3, 2002 A PVM executive program has been developed for use with the RELAP5-3D© computer program. The PVM executive allows RELAP5-3D© to be coupled with any number of other computer programs to perform integrated analyses of nuclear power reactor systems and related experimental facilities. The executive program manages all phases of a coupled computation.
Weaver, W. L. +2 more
openaire +1 more source
Numerical Simulation and Validation for Early Core Degradation Phase under Severe Accidents
Science and Technology of Nuclear Installations, Volume 2020, Issue 1, 2020., 2020 Early core degradation determines the amount of hydrogen generated by cladding oxidation as well as the temperature, the mass, and the composition of corium that further relocates into the lower head of reactor pressure vessel (RPV), which is essential for the effectiveness analysis of in‐vessel retention (IVR) and hydrogen recombiners.
Dekui Zhan +5 more
wiley +1 more source
Modeling Moving Systems with RELAP5-3D
Nuclear Science and Engineering, 2016 RELAP5-3D is typically used to model stationary, land-based reactors. However, it can also model reactors in other inertial and accelerating frames of reference. By changing the magnitude of the gravitational vector through user input, RELAP5-3D can model reactors on a space station or the moon.
G. L. Mesina +3 more
openaire +2 more sources