RELAP5-3D Code Validation for RBMK Phenomena
RELAP5-3D Code Validation for RBMK Phenomena
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 channel inlet pipe rupture test, and a high power, density wave oscillation test. The results showed that RELAP5-3D has the capability to adequately represent these RBMK-related phenomena.
- University of North Texas United States
22 General Studies Of Nuclear Reactors, 22 - General Studies Of Nuclear Reactors High Density, Water Levels, Computing, Thermal-Hydraulic, Hydraulics, Pipe Rupture, High Density, 600, 21 Specific Nuclear Reactors And Associated Plants, Heat Transfer, 99 General And Miscellaneous//Mathematics, Rbmk Reactor, Parallel Channel Flow, Reactor Accidents Thermal-Hydraulic, And Information Science, Validation, Relap5-3D, Lwgr Type Reactors, High Power, Reactor Safety Experiments, R Codes
22 General Studies Of Nuclear Reactors, 22 - General Studies Of Nuclear Reactors High Density, Water Levels, Computing, Thermal-Hydraulic, Hydraulics, Pipe Rupture, High Density, 600, 21 Specific Nuclear Reactors And Associated Plants, Heat Transfer, 99 General And Miscellaneous//Mathematics, Rbmk Reactor, Parallel Channel Flow, Reactor Accidents Thermal-Hydraulic, And Information Science, Validation, Relap5-3D, Lwgr Type Reactors, High Power, Reactor Safety Experiments, R Codes
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