This paper presents the results of RELAP5/Mod3.2 system thermalhydraulic code using the sub-channel analysis approach in predicting the NEPTUN separate effect boil off experiments. The boil off tests were conducted in order to simulate the consequences of bss of coolant inventory Ieading to uncovery and heat up of fuel elements of a nuclear reactor core. In this framework, the NEPTUN Iow pressure test N°5002 has been considered. A reference case was run, and the overali data comparison shows good agreement between calculated and experimental therrnalhydraulic parameters. A series of sensitivity analyses were also perforrned in order to assess the code prediction capabilities. The obtained results were almost satisfactory and demonstrate, as well, the reasonable success of the “sub-channel analysis” approach adopted in the present context for a system thermalhydraulic code.
Boil-off sub-channel analysis using Relap5 system code
D'AURIA, FRANCESCO SAVERIO;
2004-01-01
Abstract
This paper presents the results of RELAP5/Mod3.2 system thermalhydraulic code using the sub-channel analysis approach in predicting the NEPTUN separate effect boil off experiments. The boil off tests were conducted in order to simulate the consequences of bss of coolant inventory Ieading to uncovery and heat up of fuel elements of a nuclear reactor core. In this framework, the NEPTUN Iow pressure test N°5002 has been considered. A reference case was run, and the overali data comparison shows good agreement between calculated and experimental therrnalhydraulic parameters. A series of sensitivity analyses were also perforrned in order to assess the code prediction capabilities. The obtained results were almost satisfactory and demonstrate, as well, the reasonable success of the “sub-channel analysis” approach adopted in the present context for a system thermalhydraulic code.I documenti in IRIS sono protetti da copyright e tutti i diritti sono riservati, salvo diversa indicazione.
