Reactor dosimetry: accurate determination and benchmarking of radiation field parameter, relevant for pressure vessel monitoring (REDOS) - REDOS Final Report

The REDOS project aims to improve reactor dosimetry for radiation embrittlement monitoring of the reactor pressure vessel (RPV) steels. Benchmarking, as well as combined experimental and computational techniques, have been used. Specific objectives were the improvement of the neutron-gamma calculation methodologies through the LR-0 engineering benchmarks for WWER-1000 and WWER-440 reactor types, and the accurate determination of radiation field parameters in the vicinity and over the thickness of the RPV.
A review of the available experimental reactor dosimetry data of Kozloduy Units 1, 4, 5 was performed, and attenuation coefficients through the vessel wall were calculated. Existing data for the WWER-440 and WWER-1000 Mock-ups were reviewed and the preparatory work for subsequent measurement and experimental data analysis was carried out. Measurements of the space-energy distribution of the mixed neutron-gamma field in the WWER-1000 model over the RPV simulator were performed. The most important improvements in the experimental techniques used were the multiparameter spectrometer and a new low noise precise monitoring system in the LR-0 research reactor, developed for this type of measurements. For the WWER-1000 Mock-up and the two WWER-440 Mock-ups and for all positions, where measurements had been performed, neutron-gamma transport calculations were carried out independently by the participants using deterministic and/or stochastic codes and associated nuclear data libraries, mostly based on ENDF/BVI. The calculated neutron and gamma flux integrals, DPA-rates and spectra were compared with each other and with experimental values. Seven institutions from 5 countries (Bulgaria, Czech Republic, Germany, Hungary and Spain) delivered calculation results for the WWER-1000 Mock-up, six institutions from 4 countries performed calculations for one or both WWER-440 Mock-ups. More than eight different calculational schemes were used, covering the most important methods used for pressure vessel dosimetry and shielding. The codes used were the stochastic codes MCNP and TRAMO and the deterministic codes ANISN/DORT and TORT. They were associated with different data libraries and data preparation schemes. The BUGLE 47n/20g group structure was used for comparisons of calculated spectra as well as for comparison with experimental spectra. Results of RPV attenuation calculations for WWER-440s and WWER-1000s were obtained. A comparison between Western and Eastern attenuation determination approaches was carried out. The neutron/fluence (E>0.5 MeV) wall attenuation for WWER-440 and WWER-1000 RPVs is slower than the dpa attenuation. This means that fluence above 0.5 MeV is more conservative approach than the use of dpa. Another task performed was the application/extrapolation of the WWER mock-ups results to power reactors. The attenuation through the RPV of the neutron flux/fluence with energy above 0.5 MeV was determined. The relative difference value does not exceed 10% for WWER-440. The relative difference value does not exceed 10% for WWER-1000 too, except at the position behind the RPV wall.