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, i.e. 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 the VENUS-1 analysis. The final results of three fixed source calculations (two in plane and one in polar geometry) 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), are presented with a synthetic description of the calculational features.
|Titolo:||ENEA-Bologna Validation of the BUGLE-96 ENDF/B-VI Library on the VENUS-1 Neutron Shielding Benchmark Experiment|
|Data di pubblicazione:||12-apr-1999|
|Appare nelle tipologie:||4.1 Contributo in Atti di convegno|