Results 11 to 20 of about 1,865 (177)
RELAP5/MOD3.3 Code Validation with Plant Abnormal Event [PDF]
Science and Technology of Nuclear Installations, 2008 Measured plant data from various abnormal events are of great importance for code validation. The purpose of the study was to validate the RELAP5/MOD3.3 Patch 03 computer code with the abnormal event which occurred at Krško Nuclear Power Plant (NPP) on ...
Andrej Prošek, Borut Mavko
doaj +3 more sources
Development and Assessment of the COBRA/RELAP5 Code [PDF]
Journal of Nuclear Science and Technology, 1997 The COBRA/RELAP5 code has been developed to combine the realistic three-dimensional reactor vessel model of COBRA-TF with RELAP5/MOD3.2, thus to produce an advanced system analysis code with a multidimensional thermal-hydraulic module. This paper provides the integration scheme of the two codes. The results of developmental assesments are also provided,
JEONG, Jae-Jun +2 more
exaly +2 more sources
SCDAP/RELAP5/MOD2 code manual [PDF]
, 1989 The SCDAP/RELAP5 code has been developed for best-estimate transient simulation of light water reactor coolant systems during a severe accident. The code models the coupled behavior of the reactor coolant system, the core, and the fission products and aerosols in the system during a severe accident transient as well as large and small break loss-of ...
Allison, C. M. +13 more
openaire +7 more sources
RELAP5-3D Code Validation for RBMK Phenomena [PDF]
, 1999 The RELAP5-3D thermal-hydraulic code was assessed against Japanese Safety Experiment Loop (SEL) and Heat Transfer Loop (HTL) tests. These tests were chosen because the phenomena present are applicable to analyses of Russian RBMK reactor designs. The assessment cases included parallel channel flow fluctuation tests at reduced and normal water levels, a ...
Fisher, J.E., Fisher, James Ebberly
openaire +5 more sources
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 +2 more sources
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
doaj +2 more sources
MNSR transient analysis using the RELAP5/Mod3.2 code
Nuclear Engineering and Technology, 2020 To support the safe operation of the Miniature Neutron Source Reactor (MNSR), a thermo-hydraulic transient model using the RELAP5/Mod3.2 code was simulated.
S. Dawahra, K. Khattab, F. Alhabit
doaj +2 more sources
Energies, 2021 In-box LOCA was identified as one of the worst accidental scenarios for the HCLL TBS (Helium Cooled Lithium-Lead Test Blanket System). Aiming to experimentally analyze the consequences of this transient, ENEA designed and built THALLIUM (Test HAmmer in ...
Alessandro Venturini +2 more
doaj +1 more source
RELAP5 application for water hammer analysis in different thermal-hydraulic systems
International Journal of Thermofluids, 2022 The water hammer phenomenon investigations employing RELAP5 code with one-dimensional two-fluid six-equation models of water and steam flow were performed and the main results shared in this paper.
Algirdas Kaliatka +3 more
doaj +1 more source
Assessment of RELAP5 model for the University of Massachusetts Lowell Research Reactor [PDF]
Nuclear Technology and Radiation Protection, 2006 RELAP5 is a system code developed at the Idaho National Environmental and Engineering Laboratory for thermal hydraulic analysis of nuclear reactors. The code RELAP5 is widely used for safety analysis studies of commercial nuclear power plants.
Bousbia-Salah Anis +5 more
doaj +1 more source