Revised guidelines with the support of computational benchmarks are needed for regulation allowed neutron irradiation to reactor structures during power plant lifetime. Currently, US NRC Regulatory Guide 1.190 is effective guideline dosimetry calculations. A well known international shielding database SINBAD contains large selection models benchmarking transport methods. In this paper a PCA benchmark has been chosen from qualification our methodology pressure vessel fluence calculations, as...

A climate relevant and immediately available proven light water nuclear strategy with a potential to contribute essentially timely reduction of carbon dioxide emission the year 2065 was assumed.The perspective fission energy after that is considered.Two technologies long term which need no or small amounts uranium, i.e. fast breeders molten salt thorium reactors were singled out.The main technical safety characteristics considered.In both these it essential have starter nuclides as neither...

The capabilities of the SCALE6.1/MAVRIC hybrid shielding methodology (CADIS and FW-CADIS) were demonstrated when applied to a realistic deep penetration Monte Carlo (MC) problem full-scale PWR containment model. Automatic preparation variance reduction (VR) parameters is based on deterministic transport theory (<mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML"...

The usual approach to loading pattern optimization involves high degree of engineering judgment, a set heuristic rules, an algorithm, and computer code used for evaluating proposed patterns. speed the process is highly dependent on evaluation. In this paper, we investigate applicability machine learning model which could be fast We employ recently introduced technique, support vector regression (SVR), data driven, kernel based, nonlinear modeling paradigm, in parameters are automatically...

An important aspect of pressurized water reactor (PWR) lifetime monitoring is supporting radiation shielding analyses which can quantify various in-core and out-core effects induced in materials by varying neutron–gamma fields. A good understanding such a environment during normal accidental operating conditions required plant regulators to ensure proper equipment working personnel. The complex design typical PWR posing deep penetration problem for an elaborate simulation model needed, not...

In this paper we give an analysis of the neutron transmission through iron sphere using Monte Carlo and transport theory methods based on ENDF/B-VII.1 general purpose library. The motivation for investigation comes from a well-known deficiency in inelastic data older library evaluation (ENDF/B-V), giving concern fast flux underestimation within reactor pressure vessels. order to benchmark next-generation ENDF/B-VI data, U.S. Nuclear Regulatory Commission former Czechoslovakian National...

The Pool Critical Assembly Pressure Vessel (PCA) benchmark is a well known in the reactor shielding community which described Shielding Integral Benchmark Archive and Database (SINBAD). It based on experiments performed at PCA facility Oak Ridge National Laboratory (ORNL) it can be used for qualification of pressure vessel fluence calculational methodology. measured quantities to compared against calculated values are equivalent fission fluxes several experimental access tubes (A1 A8) front,...

Abstract The intention was to model a dry storage facility that could satisfy the needs of medium nuclear power plant similar NPP Krsko. attention has been focused on radiation dose rate analyses and criticality calculations. Using SCALE 4.4 code package modified QAD-CGGP code, we modeled satisfies basic criteria for public protection. capacity is 1,400 spent fuel assemblies which adequate forty years lifetime.