Results 81 to 90 of about 2,939 (182)
Science and Technology of Nuclear Installations, 2015 RELAP5 is a system thermal-hydraulic code that is used to perform safety analysis on nuclear reactors. Since the code is based on steady state, two-phase flow regime maps, there is a concern that RELAP5 may provide significant errors for rapid transient ...
Viet-Anh Phung +3 more
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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
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N Reactor RELAP5 model benchmark comparisons [PDF]
, 1988 This report documents work performed at the Idaho National Engineering Laboratory (INEL) in support of Westinghouse Hanford Company safety analyses for the N Reactor.
Fletcher, C. D., Bolander, M. A.
core +1 more source
Workstation experience with RELAP5
, 1993 One of the major improvements in the progress from RELAP5/MOD2 to RELAP5/MOD3 was the modification to improve portability. The use of the code was thus extended from the 60 and 64 bit work mainframe computers to 32 bit workstations and PC`s.
Wagner, R. J., Miller, C. S.
core
Study of thermal-hydraulic phenomena in hot leg break LOCA of PWR systems
, 2011 The present work cope with the execution of two post tests analysis relative to experiments executed in two different Integral test facilities. The aim of the work is to understand if the Thermal-Hydraulic system code utilized, has the capability to ...
MATTEOLI, CAMILLA
core
SCDAP/RELAP5/MOD3 code development [PDF]
, 1992 The SCOAP/RELAP5/MOD3 computer code is designed to describe the overall reactor coolant system (RCS) thermal-hydraulic response, core damage progression, and fission product release and transport during severe accidents.
Siefken, J. L. +2 more
core
Code Development in Coupled PARCS/RELAP5 for Supercritical Water Reactor
Science and Technology of Nuclear Installations, 2014 The new capability is added to the existing coupled code package PARCS/RELAP5, in order to analyze SCWR design under supercritical pressure with the separated water coolant and moderator channels. This expansion is carried out on both codes.
Po Hu, Paul Wilson
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Atom Indonesia, 2019 In order to anticipate station blackout, the use of safety system based on passive features is highly considered in advanced nuclear power plant designs, especially after the Fukushima Dai-ichi nuclear power station accident.
A.R. Antariksawan +7 more
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Liquid metal cooled fast reactor thermal hydraulic research development: A review. [PDF]
Heliyon, 2023 Agbevanu KT +3 more
europepmc +1 more source
Modifications to the VV PHTS RELAP5 Model [PDF]
, 2011 Modifications and improvements to a previous RELAP5 model of the Vacuum Vessel Primary Heat Transfer System are described in this report. The modifications were new pump models, a new steam pressurizer, new coolant water control systems, additional pipe structures, and reduction of the pulse power to 6 MW.
openaire +2 more sources