Within the framework of the activities of the OECD/NEA-NSC Task Force on Computing Radiation Dose and Modelling of Radiation-induced Degradation of Reactor Components (TFRDD) it was proposed to perform neutron shielding calculations for the VENUS-1 benchmark experiment (PWR core, fresh fuel loading), arranged in the SCK/CEN Centre of Mol (Belgium). The purpose of this international blind test (without knowing in advance the experimental dosimetry data) was to prove that the calculated dose predictions can be made within 20% of uncertainty with respect to the experimental data. The goal of the complex of these activities was to improve the calculational accuracy of the neutron damage parameters used in the LWR pressure vessel dosimetry. The exclusive use of two-dimensional transport codes was recommended for this blind test. In this paper, a simulation of the VENUS-1 experiment, performed with the DORT-3.1 two-dimensional discrete ordinates transport code included in the DOORS-3.1 ORNL modular system of deterministic codes, is presented. The cross sections used in the fixed source transport calculations, the detector response functions and the U-235 fission spectrum were obtained from the DLC-185 / BUGLE-96 (47 neutron + 20 gamma-ray) multigroup shielding library, based on the ENDF/B-VI Release 3 evaluated data files. The DORT-3.1 code was used in the (X,Y) plane geometry option with proper axial neutron leakage treatment, taking into account a square region in the geometrical model, describing one quarter of the VENUS-1 reactor configuration.

VENUS-1 Benchmark Experiment Details and Results of the ENEA-Bologna Calculations

Orsi, R.;Pescarini, M.
1998-03-03

Abstract

Within the framework of the activities of the OECD/NEA-NSC Task Force on Computing Radiation Dose and Modelling of Radiation-induced Degradation of Reactor Components (TFRDD) it was proposed to perform neutron shielding calculations for the VENUS-1 benchmark experiment (PWR core, fresh fuel loading), arranged in the SCK/CEN Centre of Mol (Belgium). The purpose of this international blind test (without knowing in advance the experimental dosimetry data) was to prove that the calculated dose predictions can be made within 20% of uncertainty with respect to the experimental data. The goal of the complex of these activities was to improve the calculational accuracy of the neutron damage parameters used in the LWR pressure vessel dosimetry. The exclusive use of two-dimensional transport codes was recommended for this blind test. In this paper, a simulation of the VENUS-1 experiment, performed with the DORT-3.1 two-dimensional discrete ordinates transport code included in the DOORS-3.1 ORNL modular system of deterministic codes, is presented. The cross sections used in the fixed source transport calculations, the detector response functions and the U-235 fission spectrum were obtained from the DLC-185 / BUGLE-96 (47 neutron + 20 gamma-ray) multigroup shielding library, based on the ENDF/B-VI Release 3 evaluated data files. The DORT-3.1 code was used in the (X,Y) plane geometry option with proper axial neutron leakage treatment, taking into account a square region in the geometrical model, describing one quarter of the VENUS-1 reactor configuration.
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Utilizza questo identificativo per citare o creare un link a questo documento: http://hdl.handle.net/20.500.12079/5816
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