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...

This paper presents two methods of object recognition by a robot vision which is being used to educate the students. includes basic manipulation objects using robotic arm. It describes procedures needed for setting up appropriate environment and each method gives examples practical usage vision. The part accomplished USB camera software named Image Inspector image analysis, ViewFlex interconnect output data from arm in described SCORBOT ER-4U, didactic manipulator. first presented uses blob...

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"...

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...

Abstract In this paper, shielding analysis was performed to determine neutron and gamma dose rates around the transfer cask HI-TRAC VW (Holtec International Transfer Cask Variable Weight) loaded with spent fuel assemblies (SFA) from nuclear power plant (NPP) Krsko dry storage (SFDS) campaign one. The is a multilayered cylindrical vessel designed accept multipurpose canister (MPC) during loading, unloading, building. MPC can contain up 37 assemblies. divided into two steps. first step source...

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...

This paper presents burnup/depletion calculations of the typical Westinghouse 17x17 fuel assembly to be used as a radioactive waste package in Generic Burnup Credit cask benchmark problem with 32 elements (GBC-32). first phase is addressing spent source terms calculation while evaluation shielding performance GBC-32 planned for second phase. The TRITON-NEWT methodology SCALE6.1.3 program was tandem ORIGEN-S code deterministic 2D neutron multiplication factor, providing spatial-temporal...

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,...

Recently a novel approach based on support vector regression technique has been proposed and tested for the estimation of multi layer buildup factors gamma ray shielding calculations, while neutron calculations some initial analyses have conducted. During development model number questions regarding possible application active learning measures raised. In this paper general applicability problem, in particular data transfer method used investigation, testing procedure are discussed.

The Integral Inherently Safe Light Water Reactor (I2S-LWR) concept developed by a team lead Georgia Tech is novel PWR reactor delivering electric power of 1000 MWe while implementing inherent safety features typically reserved for Generation III+ small modular reactors. main feature based on an integral primary circuit configuration, bringing together compact core design with 121 fuel assemblies (FA), control rod drive mechanism (CRDM), 8 heat exchangers (PHE), 4 passive decay removal...