https://doi.org/10.1051/epjconf/201715305008
Neutron-gamma flux and dose calculations in a Pressurized Water Reactor (PWR)
1 Institut de Radioprotection et de Sûreté Nucléaire (IRSN), Fontenay-aux-Roses, 92260, France
2 ENEA, Via M.M.Sole, 4, 40129 Bologna, Italy
3 IRSN subcontractor
a Corresponding author: mariya.brovchenko@irsn.fr
Published online: 25 September 2017
The present work deals with Monte Carlo simulations, aiming to determine the neutron and gamma responses outside the vessel and in the basemat of a Pressurized Water Reactor (PWR). The model is based on the Tihange-I Belgian nuclear reactor. With a large set of information and measurements available, this reactor has the advantage to be easily modelled and allows validation based on the experimental measurements. Power distribution calculations were therefore performed with the MCNP code at IRSN and compared to the available in-core measurements. Results showed a good agreement between calculated and measured values over the whole core. In this paper, the methods and hypotheses used for the particle transport simulation from the fission distribution in the core to the detectors outside the vessel of the reactor are also summarized. The results of the simulations are presented including the neutron and gamma doses and flux energy spectra. MCNP6 computational results comparing JEFF3.1 and ENDF-B/VII.1 nuclear data evaluations and sensitivity of the results to some model parameters are presented.
© The Authors, published by EDP Sciences, 2017
This is an Open Access article distributed under the terms of the Creative Commons Attribution License 4.0, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.
