نتایج جستجو برای: mcnp 4c code

تعداد نتایج: 171417  

ژورنال: سنجش و ایمنی پرتو 2020

The present study deals with a new method for measuring the power of a reactor. This method uses gamma and neutron radiation resulted from the entire reactor structure, without changing its structure (online). In terms of functionality, this method can measure the reactor power in real-time and report it instantly. In order to obtain the relationship between reactor power and gamma and neutron ...

2007
S. D. Clarke S. A. Pozzi E. Padovani T. J. Downar Shaun D. Clarke Sara A. Pozzi

The most recent release of photonuclear interaction data for Monte Carlo applications is the ENDF/B-VII library. While this current version offers several improvements over its predecessors, it does not address the observed, sometimes quite significant variance in the measured data. For instance, for U, the cross-section data in the ENDF/B-VII library is consistently larger than all measurement...

2007
D. V. Fedorchenko

Design and maintenance of nuclear cycle facilities mandatory imply implementation of efficient radiation protection. Radiation environment assessment and shielding optimization require a considerable amount of numerical calculations. Nowadays mathematical modelling methods and corresponding software are widely used for such kind of problems. All the software used for radiation fields modelling ...

1999
John S. Hendricks Christopher N. Culbertson

The weight window variance reduction method in the general-purpose Monte Carlo N-Particle radiation transport code MCNP has recently been rewritten. In particular, it is now possible to generate weight window importance functions on a superimposed mesh, eliminating the need to subdivide geometries for variance reduction purposes. Our assessment addresses the following questions: (1) Does the n...

2008
Vicente Abella Rafael Miró Belén Juste Gumersindo Verdú

The purpose of this work is to obtain the voxelization of a series of tomography slices in order to provide a voxelized human phantom throughout a MatLab algorithm, and the consequent simulation of the irradiation of such phantom with the photon beam generated in a Theratron 780® (MDS Nordion) 60 Co radiotherapy unit, using the Monte Carlo transport code MCNP (Monte Carlo N-Particle), version 5...

Journal: :IEEE Transactions on Nuclear Science 1992

A. Hashemian H. Miri H. Saberi M. H. Bahreyni Toosi M. Momen Nezhad M. T. Bahreyni Toosi R. Salek

ntroduction:  Monte  Carlo  simulation  is  the  most  accurate  method  of  simulating  radiation  transport  and  predicting doses at different points of interest in radiotherapy. A great advantage of the Monte Carlo method  compared  to  the  deterministic  methods  is  the  ability  to  deal  accurately  with  any  complex  geometry.  Its  disadvantage is the extremely long computing time r...

2004
M. Ramos S. Ferrer J. I. Villaescusa G. Verdú

The aim of this study is the development of a methodology to reconstruct the image of detail defects from a mammographic phantom employed in quality control testing. The MCNP-4c2 code has been used to model the mammography unit and the CIRS 11A (MAMMO PHANTOM SP01) mammographic phantom. This phantom is made of poly-methyl methacrilate and contains a reference point, contrast and resolution deta...

Ahmad Esmaili-Torshabi Ahmad Mosalaei Kamal Hadad Mohammad Amin Mosleh-Shirazi, Reza Faghihi, Simin Mehdizadeh Vahid Moslemi

Introduction: In brachytherapy, radioactive sources are placed close to the tumor, therefore, small changes in their positions can cause large changes in the dose distribution. This emphasizes the need for computerized treatment planning. The usual method for treatment planning of cervix brachytherapy uses conventional radiographs in the Manchester system. Nowadays, because of their advantages ...

2014
Birju P. Shah Nicholas Pasquale Gejing De Tao Tan Jianjie Ma Ki-Bum Lee

Mitochondria-targeting peptides have garnered immense interest as potential chemotherapeutics in recent years. However, there is a clear need to develop strategies to overcome the critical limitations of peptides, such as poor solubility and the lack of target specificity, which impede their clinical applications. To this end, we report magnetic core-shell nanoparticle (MCNP)-mediated delivery ...

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