In this work we integrate MCNP and PROTEUS, two high-fidelity reactor physics codes, into the Nuclear Energy Advanced Modeling Simulation (NEAMS)Workbench. Specifically, enhance user interface of each code by developing full-featured editor services. Next, re-define textual outputs in HDF5 formats, at great convenience to user. Further, these are (optionally) coerced OpenMC format, enabling pow...

Monte Carlo particle transport is often introduced primarily as a method to solve linear integral equations such as the Boltzmann transport equation. This paper discusses some common misconceptions about Monte Carlo methods that are often associated with an equation-based focus. Many of the misconceptions apply directly to standard Monte Carlo codes such as MCNP and some are worth noting so tha...

The structure of a 150 MeV neutron data le is outlined. Emphasis is put on the possibility to process a high-energy le with NJOY into an MCNPlibrary. Examples of parts of such a le are given as illustration. Furthermore, we have processed some existing data libraries and report on the encountered di culties. Accordingly, we give recommendations for the format to be used for evaluated neutron da...

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,...

background: the radiation doses resulting from diagnostic x-ray examinations are routinely measured in terms of entrance surface dose (esd) and effective dose (ed). in this study, for the purpose of radiation protection, the radiation doses received from digital chest x-ray examination were evaluated in terms of esd and ed. material and methods: the ed was calculated by using the mcnp monte car...

In this paper, we show that a module implemented in the MCNP transport code to perform sensitivity analyses can be diverted topology optimizations of nuclear equipment. Component design with approach leads sophisticated solutions outperform their human-designed counterparts.