The LOFT (Loss of Fluid Test) facility was available in the 70’s and the 80’s at the Idaho National Engineering Laboratory (INL, or INEEL or INEL) for performing pioneering experiments relevant to nuclear reactor safety. Actually LOFT is a 50 MW nuclear reactor originally designed as the ground prototype for a submarine reactor and later on used for experiments relevant to PWR (Pressurized Water Reactors). Namely, the L2-5 test, Large Break Loss of Coolant experiment (LBLOCA), was already used by Organization for Economic Cooperation and Development / Nuclear Energy Agency / Committee on the Safety of Nuclear Installation (OECD/NEA/CSNI) for an International Standard Problem (ISP) with the nuclear core in the early 80’s, i.e. ISP 13. Following the development of an improved set of specifications, the present document deals with the ‘final’ post-test analysis by the current Relap5 code version of the L2-5 experiment and with application of CIAU (Code with capability of Internal Assessment of Uncertainty) for the determination of uncertainty bands of the calculation (which were found as bounding the concerned experimental data trends). This new document replaces NT 558 (05) on the same topic: it is of interest is to check the differences between values here reported and values in NT 558 (05) to evaluate the impact of minor changes in Boundary and Initial Condition upon the uncertainty values.
Uncertainty evaluation of LOFT L2-5 test calculation by CIAU method
D’Auria F.
Co-primo
Conceptualization
2006-01-01
Abstract
The LOFT (Loss of Fluid Test) facility was available in the 70’s and the 80’s at the Idaho National Engineering Laboratory (INL, or INEEL or INEL) for performing pioneering experiments relevant to nuclear reactor safety. Actually LOFT is a 50 MW nuclear reactor originally designed as the ground prototype for a submarine reactor and later on used for experiments relevant to PWR (Pressurized Water Reactors). Namely, the L2-5 test, Large Break Loss of Coolant experiment (LBLOCA), was already used by Organization for Economic Cooperation and Development / Nuclear Energy Agency / Committee on the Safety of Nuclear Installation (OECD/NEA/CSNI) for an International Standard Problem (ISP) with the nuclear core in the early 80’s, i.e. ISP 13. Following the development of an improved set of specifications, the present document deals with the ‘final’ post-test analysis by the current Relap5 code version of the L2-5 experiment and with application of CIAU (Code with capability of Internal Assessment of Uncertainty) for the determination of uncertainty bands of the calculation (which were found as bounding the concerned experimental data trends). This new document replaces NT 558 (05) on the same topic: it is of interest is to check the differences between values here reported and values in NT 558 (05) to evaluate the impact of minor changes in Boundary and Initial Condition upon the uncertainty values.I documenti in IRIS sono protetti da copyright e tutti i diritti sono riservati, salvo diversa indicazione.
