The work presents the results of the detailed analyses performed on the shielding capability of HCLL DEMO-type fusion reactor. The analysis is based on three-dimensional calculations with the Monte Carlo code MCNP-4C and consists in assessment of radiation loads to the super-conducting TF-coil at the inboard side of the reactor. A suitable 20-sector model of DEMO reactor, based on the reactor p...

Abstract The contents and distribution of radionuclides in activated metallic wastes are major concerns while designing a leaching model safety case. This study investigated 60 Co as typical activation product the lower tie plate (i.e., stainless steel endpiece BWR fuel assembly) irradiated for 35.0 GWd/tHM burnup, using imaging (IP) method. calculations coupled with Monte Carlo burnup neutron ...

Procedures and results obtained in the installation process of a microcomputers cluster (Linux and PVM) to reduce processing time in MCNP simulations are described. The necessities and specificity concerned to the hardware, the Linux operational system, the PVM software package and an adequated compiled version for MCNP4B are presented. The system was tested to verify the gain in the processing...

Most analytical techniques do not comply with the need for direct trace element analysis of samples exceeding the order of grams. Instead, sub-sampling methods are used to obtain representative sampling of the initial material. The possibilities arising from directly analyzing voluminous samples have been discussed [4]. Instrumental Neutron Activation Analysis (INAA) is a powerful technique, wh...

This work presents an extensive study on Monte Carlo radiation transport simulation and thermoluminescent (TL) dosimetry for characterising mixed radiation fields (neutrons and photons) occurring in nuclear reactors. The feasibility of these methods is investigated for radiation fields at various locations of the Portuguese Research Reactor (RPI). The performance of the approaches developed in ...

Introduction BNCT is an effective method to destroy brain tumoral cells while sparing the healthy tissues. The recommended flux for epithermal neutrons is 10 n/cms, which has the most effectiveness on deep-seated tumors. In this paper, it is indicated that using D-T neutron source and optimizing of Beam Shaping Assembly (BSA) leads to treating brain tumors in a reasonable time where all IAEA re...

An artificial neural network has been designed to obtain the neutron spectra from the Bonner spheres spectrometer's count rates. The neural network was trained using 101 neutron spectra taken from IAEA's compilations. These include calibration, reference and operational neutron spectra whose energy distribution is different from UTA4 response matrix, therefore the spectra were converted from le...

There is considerable interest in transport models that will permit the simulation of neutral particle transport through stochastic mixtures. Chord length sampling techniques that simulate particle transport through binary stochastic mixtures consisting of spheres randomly arranged in a matrix have been implemented in several Monte Carlo Codes [1-3]. Though the use of these methods is growing, ...