Within the framework of the activities proposed by the OECD/NEA Nuclear Science Committee Task Force on Computing Radiation Dose and Modelling of Radiation-Induced Degradation of Reactor Components (TFRDD), the results of a three-dimensional deterministic transport analysis of the VENUS-3 neutron shielding benchmark experiment are presented. The work was performed at the ENEA-Bologna Nuclear Data Centre. In particular the discrete ordinates transport code TORT-3.2 was used together with the ENDF/B-VI based DLC-185/BUGLE-96 cross section library and the IRDF-90 Version 2 dosimetry file. Among the available low-flux experiments, the VENUS-3 experiment offers the exceptional advantage of exhibiting a realistic radial core shape and a neutron spectrum typical of PWRs together with a L3P (Low Leakage Loading Pattern) core region. These features permit, in particular, an interesting test of the calculational methods and cross section libraries addressed to predict the fast neutron damage parameters in the PWR pressure vessels.
ENEA Neutron Transport Analysis of the VENUS-3 Shielding Benchmark Experiment - Preliminary Report
Orsi, R.;Pescarini, M.
2000-12-05
Abstract
Within the framework of the activities proposed by the OECD/NEA Nuclear Science Committee Task Force on Computing Radiation Dose and Modelling of Radiation-Induced Degradation of Reactor Components (TFRDD), the results of a three-dimensional deterministic transport analysis of the VENUS-3 neutron shielding benchmark experiment are presented. The work was performed at the ENEA-Bologna Nuclear Data Centre. In particular the discrete ordinates transport code TORT-3.2 was used together with the ENDF/B-VI based DLC-185/BUGLE-96 cross section library and the IRDF-90 Version 2 dosimetry file. Among the available low-flux experiments, the VENUS-3 experiment offers the exceptional advantage of exhibiting a realistic radial core shape and a neutron spectrum typical of PWRs together with a L3P (Low Leakage Loading Pattern) core region. These features permit, in particular, an interesting test of the calculational methods and cross section libraries addressed to predict the fast neutron damage parameters in the PWR pressure vessels.I documenti in IRIS sono protetti da copyright e tutti i diritti sono riservati, salvo diversa indicazione.
