IKE-Contribution to the NEA PWR Shielding Benchmark for Studying the Effect of Nuclear Data Uncertainties

摘要

The paper presents the IKE contribution to the PWR reactor shield benchmark No. 2. The report documents the results of integral target quantity determination performed with ANISN. The cross sections were taken from the recent multigroup data library VIT-IKE-1 where the group structure is identical with VITAMIN-C. The thermal neutron cross section was taken from the 126 thermal neutron group cross-section library THERM-126. The cross-section data and the covariance data library used for hydrogen and iron, are all based on ENDF/B/V data. For the first time a comprehensive cross section and secondary energy distribution (SED) sensitivity and uncertainly analysis for a PWR (Biblis B, 1300 MWsub(el)) was performed with SWANLAKE and SENSIT. The target quantities considered are th exp 54 Fe(n,p) exp 54 Mn activation rate in the barrel material near the surveillance capsules and in the pressure vessel cladding, the iron displacement rate at the inner edge of the pressure vessel, the gamma heating rate at the inner edge of core baffle, at the core barrel, pressure vessel and concrete shield and the biological neutron- and gamma dose rate at the outer side of the concrete shield. (ERA citation 09:000510)