Design and Simulation of a New Model for Treatment by NCT-Reference-Cited by-同舟云学术

Design and Simulation of a New Model for Treatment by NCT

Published:2012 Issue: Volume:2012 Page:1-7
ISSN:1687-6075
Container-title:Science and Technology of Nuclear Installations
language:en
Short-container-title:Science and Technology of Nuclear Installations

Author:

Mousavi Shirazi Seyed Alireza¹,Sardari Dariush²

Affiliation:

1. Department of Physics, Sciences College, Islamic Azad University, South Tehran Branch, Tehran 1581819411, Iran

2. Department of Nuclear Engineering, Technical College, Islamic Azad University, Science and Research Branch, Tehran, Iran

Abstract

In this investigation, neutron capture therapy (NCT) through high energy neutrons using Monte Carlo method has been studied. In this study a new method of NCT for a sample liver phantom has been defined, and interaction of 12 MeV neutrons with a multilayer spherical phantom is considered. In order to reach the desirable energy range of neutrons in accord with required energy in absence of eligible clinical neutron source for NCT, this model of phantom might be utilized. The neutron flux and the deposited dose in the all components and different layers of the mentioned phantom are computed by Monte Carlo simulation. The results of Monte Carlo method are compared with analytical method results so that by using a computer program in Turbo-Pascal programming, the deposited dose in the liver phantom has been computed.

Publisher

Hindawi Limited

Subject

Nuclear Energy and Engineering

Link

http://downloads.hindawi.com/journals/stni/2012/213640.pdf

Reference18 articles.

1. Intercalibration of physical neutron dosimetry for the RA-3 and MURR thermal neutron sources for BNCT small-animal research

2. What can we learn about the spectrum of high-energy stray neutron fields from Bonner sphere measurements?

3. Neutron and gamma irradiation studies of packaged VCSEL emitters for the optical read-out of the ATLAS electromagnetic calorimeter

4. Response functions of spherically moderated neutron detectors

Cited by 10 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Finding Out and Exploration of Two New Equations for Calculating the Dead-time of Neutron Detectors and the Energy of Slow-downed Neutrons;EQUATIONS;2022-06-03

2. Decomposition of a Tissue Into Its Constituent Elements for Specifying the Values of Doses;MOLECULAR SCIENCES AND APPLICATIONS;2022-05-07

3. Estimation of KERMA because of neutron emission into the constituent elements of a tissue in radiotherapy;PROCEEDING OF THE 1ST INTERNATIONAL CONFERENCE ON ADVANCED RESEARCH IN PURE AND APPLIED SCIENCE (ICARPAS2021): Third Annual Conference of Al-Muthanna University/College of Science;2022

4. A new investigation into the estimation of transferred energy from a neutron source to a human’s body;THE 7TH INTERNATIONAL CONFERENCE ON ENGINEERING, APPLIED SCIENCES AND TECHNOLOGY: (ICEAST2021);2021

5. Calculation of neutron flux and neutron visualization in a spherical reactor core applying a conceptual approach and drawing a comparison with the results obtained by the CITATION code;International Journal of Advanced Nuclear Reactor Design and Technology;2021