Development and validation of a cross-section interface for PARCS
Artikel i vetenskaplig tidskrift, 2008
This paper deals with the development of a cross-section interface for PARCS and its validation. The interface is used to feed PARCS with material constants for Light Water Reactors. These material constants are obtained from a CASMO-4 library file and the SIMULATE-3 code is then used to read this library file. This interface allows a dependency of the material constants on exposure and on instantaneous and history variables. Since the functionalization of the cross-sections in CASMO-4/SIMULATE-3 is different from the one in PARCS, the conversion of the material data from the CASMO-4/SIMULATE-3 formalism to the PARCS formalism is not trivial. As a first check of the proper conversion of the data by the interface, the cross-section files created by the interface were read by PARCS. The data were thereafter edited for all possible burnup, instantaneous and history parameters and compared to the original data used to create the files. After this successful verification, a benchmark between PARCS and plant measured data was carried out. For this benchmark a number of measurement sets from the Swedish Ringhals-3 pressurized water reactor were obtained. These data were measured during different cycles and at different core exposures. The spatial distribution of the instantaneous variables, the history variables and the exposure were calculated by SIMULATE-3 and used by PARCS to retrieve the actual three-dimensional distribution of the material data. The deviation of the effective multiplication factor keff from criticality was found to be within ±200 pcm. Both the measured axial and radial power profiles were adequately reproduced by the PARCS simulations, although some discrepancies with plant data need to be further investigated.