Spent Fuel Pool Dose Rate Calculations Using Point Kernel and Hybrid Deterministic-Stochastic Shielding Methods

This paper presents comparison of the Krško Power Plant simplified Spent Fuel Pool (SFP) dose rates using different computational shielding methodologies. The analysis was performed to estimate limiting gamma on wall mounted level instrumentation in case significant loss cooling water. SFP represented with simple homogenized cylinders (point kernel and Monte Carlo (MC)) or cuboids (MC) uranium, iron, water, dry-air as a bulk region materials. pool is divided old new section where one has three additional subsections representing fuel assemblies (FAs) burnup/cooling time (60 days, 1 year 5 years). represents FAs 10 years. dependent assembly isotopic composition calculated ORIGEN2 code applied depletion present (AC-29). source used Microshield calculation based imported activities. photon spectrum total intensity from multigroup point calculations then prepared for two hybrid deterministic-stochastic sequences. One SCALE6.2b3/MAVRIC (Monaco Denovo) methodology another uses MCNP6.1.1b ADVANTG3.0.1. code. Even though this model fairly one, layers materials are thick enough pose problem MC method without use effective variance reduction (VR) technique. For that purpose ADVANTG generate VR parameters MCNP fixed-source continuous energy transport. ADVATNG employs deterministic forward-adjoint transport solver Denovo which implements CADIS/FWCADIS methodology. structured, Cartesian-grid SN Koch- Baker-Alcouffe parallel sweep algorithm across x-y domain blocks. our first application ANDVANTG/MCNP sequence type results compared SCALE/MAVRIC we regularly similar calculations. detector locations (central above at top periphery) showed good agreement between (point-kernel) methodologies cylindrical approximation geometry. More complicated cases multi-source option very