Current calculation methods and nuclear data are well validated for conventional nuclear reactor systems. However there is a further need for validating the computational tools and the nuclear data for ADS applications. The OECD/NEA, in co-operation with CIEMAT (Spain) and CEA (France), therefore launched a benchmark based on the MUSE-4 experiments being carried out at Cadarache, France, to sim...

The dose calculation accuracy of a commercial pencil beam IMRT planning system is evaluated by comparison with Monte Carlo calculations and measurements in an anthropomorphic phantom. The target volume is in the right lung and mediastinum and thus significant tissue inhomogeneities are present. The Monte Carlo code is an adaptation of the MCNP code and the measurements were made with TLD and fi...

This article summarizes ways to verify neutron fluence for neutron transmutation doping of silicon with phosphorus on the LVR-15 reactor. Neutron fluence is determined using activation detectors placed along the crystal in a strip or encapsulated in a rod holder. Holders are placed at the centre of a water-filled capsule or in an aluminum or silicon ingot that simulates a real single crystal. I...

Relation to high absorption fraction of Tc sestamibi by kidneys in heart scan and these organs are near to generation organs (Ovaries and uterus). Urinary system (kidneys and urinary bladder) are specified as sources organs. The main object of this study is to determine the absorbed dose in these critical organs. we have set amount of absorbed fraction radiopharmaceutical in position of kidneys...

In this paper, the Monte Carlo N-Particle extended computer code (MCNP) were used to design a model of European Sodium-cooled Fast Reactor. The multiplication factor, conversion delayed neutrons fraction, doppler constant, control rod worth, sodium void masses for major heavy nuclei, radial and axial power distribution at high burnup are studied. results show that reactor breeds fissile isotope...

Criticality safety reanalyzes of the NPP Krško spent fuel pool has been performed. Limiting criticality cases at optimal moderation conditions are calculated using different SCALE code versions (SCALE-4.4a, SCALE-5.1 and SCALE-6.1) with 44-group ENDF/B-V 238-group ENDF/B-VII.0 derived cross section libraries. Relative small discrepancies observed. Additional verification is provided SERPENT MCN...

INTRODUCTION Monte Carlo (MC) methods have become the "gold standard" for assessing dose distribution, organ doses and effective dose associated with the exposure, both external and internal, of humans to ionizing radiation. Powerful and sophisticated tools for simulation of radiation transport (for example, MCNP, EGS4) are now widely available. However, these codes are designed for general-pur...

The neutron temperature is a characteristic parameter in irradiation channels of reactor. For nuclides which have resonances in the thermal neutron energy range, their Westcott g-factors are different from unity. The values of g-factors and cross-sections of (n, γ) reaction of these nuclides are temperature dependence. The standard energy for tabulation of thermal neutron cross-section (σ0) is ...

In our most recent study of normal aging, we found decreased concentration of multiple chemicals in the brain of middle-aged subjects, as compared with younger subjects using in vivo proton magnetic resonance spectroscopy ((1)H-MRS). We hypothesized that these age-dependent differences in brain chemistry changes might be a reflection of the multichemical-networking-profile (MCNP) changes during...