An innovative computational tool (DAG-MCNP) has been developed for efficient and accurate 3-D nuclear analysis of geometrically complex fusion systems. Direct coupling with CAD models allows preserving the geometrical details, eliminating possible human error, and faster design iterations. DAG-MCNP has been applied to perform 3-D nuclear analysis for several fusion designs and demonstrated the ...

Prediction of neutron flux at the irradiation devices of a research reactor facility is essential for the design and evaluation of experiments involving material irradiations. A computational model of the Greek Research Reactor (GRR-1) was developed using the Monte Carlo code MCNP with continuous energy neutron cross-section data evaluations from ENDF/B-VI library. The model included detailed g...

MCNP is widely used Monte Carlo program in reactor and nuclear physics. However, an option of simulating electrons was added into the code a few years ago. With this extension MCNP became a code, potentially applicable for applications in medical physics. In 1997, a new version of the code, named MCNP4B was released, which contains several improvements in electron transport modelling. To test s...

In this paper, we show that concentrations of manufactured carbon-based nanoparticles (MCNPs) in aquatic sediments will be negligible compared to levels of black carbon nanoparticles (BCNPs). This is concluded from model calculations accounting for MCNP sedimentation fluxes, removal rates due to aggregation or degradation, and MCNP burial in deeper sediment layers. The resultant steady state MC...

---------------------------------------------------------------------***--------------------------------------------------------------------Abstract The dose distribution in irradiation room and the dose rate at each dwell position of 60Co irradiator SVST-Co-60/B have been calculated using MCNP code. The calculated results are useful information to estimate radiation safety and design irradiato...

The accuracy of the results obtained using the surface source write/read feature of MCNP for toroidal fusion systems was assessed. Techniques that enhance the effectiveness of the surface source method were identified. Accurate results can be obtained for a specific component in a fusion system by either inserting the detailed component CAD geometry in the full model for the fusion system or ut...

Pohang Neutron Facility (PNF) is a pulsed neutron facility based on the 100-MeV electron linear accelerator. It was constructed for nuclear data production in Korea, and it consists of an electron linear accelerator, a watercooled Ta target with a water moderator and a time-offlight path with an 11 m length. The 100-MeV electron linac uses a thermionic RF-gun, an alpha magnet, four quadrupole m...

Pohang Neutron Facility (PNF) is a pulsed neutron facility based on the 100-MeV electron linear accelerator. It was constructed for nuclear data production in Korea, and it consists of an electron linear accelerator, a watercooled Ta target with a water moderator and a time-offlight path with an 11 m length. The 100-MeV electron linac uses a thermionic RF-gun, an alpha magnet, four quadrupole m...

Radiation Transport Simulation Studies Using MCNP for a Cow Phantom to Determine an Optimal Detector Configuration for a New Livestock Portal. (August 2012) Joe Justina, M.Sc., Mangalore University Co-Chairs of Advisory Committee: Dr. Craig M. Marianno Dr. Sunil S. Chirayath A large radiological accident will result in the contamination of surrounding people, animal, vegetation etc. In such a s...