At the ENEA TRIGA research reactor (Casaccia Research Center, Rome), a new neutron collimator has been designed and installed at the neutron tangential channel. This collimator, that is part of a neutron/X-ray facility for NDT analysis, was experimentally characterized and optimized in terms of thermal neutron flux, its spatial/energetic distribution, photon air KERMA and effective beam diamete...

The University of Missouri Research Reactor has designed and constructed a thermal neutron beam line for use in small animal boron neutron capture therapy (BNCT) experiments. Details of the facility have been previously reported by Brockman et al.[1] and Pozzi et al.[2]. The facility utilizes a 15.24 cm diameter beam tube that extends from the beryllium reflector to the biological shield, a dis...

The authors developed a new neutron-measuring instrument that was designed to measure a neutron personal dose equivalent, Hp(10). This instrument is composed of a conventional moderator-based neutron dose equivalent meter and a neutron shield made of borated polyethylene which covers a backward hemisphere to adjust the angular dependence. The whole design was determined on the basis of MCNP cal...

In present work, the SHIELD code system have been used to investigate the physics properties of spallation neutron target, such as the neutron spectra, the yield, the radioactivity in the target and the target size etc. The fragment mass distribution of the residual nuclei from proton-induced spallation reaction on thick lead target with energy 1.6 GeV have been analysed also. Radiation damage,...

Background: High density concrete is extensively used for efficient radiation attenuation in radiotherapy rooms and nuclear reactors. Over the past eight years, some efficient galena-based concrete samples for shielding X or gamma rays was produced. The goal of this study was to produce a novel high density concrete against neutron and photon radiations using tourmaline and galena. Materials an...

A power plant design based on the spherical torus (ST) concept has been developed by the ARIES team. This paper documents the results of the nuclear and radiation protection analyses carried out for the ARIES-ST design. The nuclear analysis addresses the key neutronics issues, such as the neutron wall loading profile, radiation damage to structural components and their lifetimes, tritium breedi...

Background: Given the importance of scattered and low doses in secondary cancer caused by radiation treatment, the point dose of critical organs, which were not subjected to radiation treatment in breast cancer radiotherapy, was measured.Objective: The purpose of this study is to evaluate the peripheral dose in two techniques of breast cancer radiotherapy with two energies. Methods: Eight diff...

The neutronics activities for SPPS included the determination of the blanket dimensions that provide tritium self-sufficiency, radiation damage to the structural materials, lifetime of the in-vessel components, radiation level at the superconducting magnets, and shielding requirements for magnet protection. The neutron wall loading varies in both poloidal and toroidal directions. For an average...