This paper demonstrates the applicability of Monte Carlo analysis to perform nuclear reactor core simulations with thermofluid feedback from a computational fluid dynamics code. An interface program, McSTAR, was written to couple MCNP5 to the commercial computational fluid dynamics code STAR-CD. McStar is a Perl script which alternately executes MCNP5, STAR-CD and cross section update routines ...

Following the design of the German research reactor, FRM-II, which delivers high thermal neutron fluxes, we have already developed an asymmetric compact cylindrical core with an inner and outer reflector. The goal was to maximize the maximum thermal flux to power ratio, which is a desirable characteristic of a modern research reactor. This design, for a 10 MW power, was analyzed using MCNP, ORI...

The 250kW TRIGA Mark II research reactor, Vienna, is equipped with experimental facilities inside and outside the reactor core. Outside the core, there are four beam tubes (three radial and one tangential beam tube), a thermal column and a neutron radiography collimator, supplying neutrons for irradiation experiments. These experiments include neutron radiography, neutron tomography, neutron ac...

Modern technical computing environments, such as Mathematica or Matlab, provide powerful tools and techniques for research reactor analysis combined with advanced graphical user interfaces. In addition, reactor calculations can now be efficiently supported by neutronics codes based on the Monte Carlo method due to the dramatic increase of computer performance in recent years. In particular for ...

Most HWRs currently use natural uranium fuel. Using enriched uranium fuel results in a significant improvement in fuel cycle costs and uranium utilization. On the other hand, reactivity changes of HWRs over the full range of operating conditions from cold shutdown to full power are small. This reduces the required reactivity worth of control devices and minimizes local flux distribution perturb...

BACKGROUND Obtaining high quality images in Single Photon Emission Tomography (SPECT) device  is the most important goal in nuclear medicine. Because if image quality is low, the possibility of making a mistake in diagnosing and treating the patient will rise. Studying effective factors in spatial resolution of imaging systems is thus deemed to be vital. One of the most important factors in SPE...

Medical isotopes can be produced by reactors and accelerators [1]. For certain isotopes there could be an advantage to a certain production method. For example; in some cases production via the ( ,n) or ( ,p) reaction has advantages that include high production yield [2] and production in a matrix that simplifies chemical separation of the desired isotope. To maximize isotope production, a high...

We present a computing framework for Monte Carlo simulation of radiation transport. In conformity with our belief that Monte Carlo studies should be anchored to physics but not to any particular code, we have enabled different Monte Carlo codes in this environment. The framework embraces the EGSnrc family, FLUKA, MCNP/MCNPX, GEANT4 and PENELOPE; dedicated and non-dedicated resources; shared and...

A non destructive technique based on gamma spectrometry and application of the Monte Carlo method for detector efficiency calibration, was used to assay radioactive content waste drums. Exploranium GR-130 miniSPEC portable gamma ray spectrometer was used to externally monitor radioactive waste drums containing ion exchange resin waste from the water demineralization system of GRR-1 open pool-ty...

Ionizing radiation effectively reduces the number of common microbial pathogens in fresh produce. However, the efficacy of the process for pathogens internalized into produce tissue is unknown. The objective of this study was to understand gamma irradiation of lettuce leaf structure exposed in a Cs irradiator using MCNP. The simulated Cs irradiator is a self-shielded device, and its geometry an...