MCNP-modell för beräkning av neutrondos och DPA på reaktortanken vid Ringhals 2

Sammanfattning: In this report an MCNP (Monte Carlo N-Particle) model is described for the reactor vessel at Ringhals 2. The model is validated against the specific activity in neutron dosimeters, extracted in 1977, 1984 and 1994. The validation showed that the calculations of the model are within the requirements of a maximum of 20 percent uncertainty for every neutron dosimeter except one, extracted after the first cycle. The uncertainty of this cycle was mostly due to the operation data rather than to the MCNP model. The model has been used to investigate various questions concerning radiation damage. The reliability of the traditional measure of radiation damage, fast neutron flux (En > 1MeV) has been evaluated.  This has been done by taking the ratio for this and another measure of radiation damage, DPA (Displacement Per Atom), for various positions and layers. The results show good reliability, except for at the outer layers of the vessel wall, where the traditional measure underestimates the radiation damage. Inspections are carried out in connection with the change of fuel to investigate any possible cracking on the internal structures of the reactor vessel.  New data on local differences in the radiation of these have therefore been calculated for future evaluations.  This is in order to be able to focus the inspections mainly on those internal parts that are exposed to the highest dose of radiation. An estimation of the neutron dose after 40, 50 and 60 years of operation has been calculated for the surface of the reactor vessel that is being exposed to the highest neutron flux. The result confirms earlier appreciation that the radiation damage to the reactor vessel is not a limiting factor for the future operation of Ringhals 2. The report also presents which surface of the vessel wall that has been exposed to a neutron dose of 1017 n/cm2 for neutrons with En > 1 MeV.