Intercalibration of physical neutron dosimetry for the RA-3 and MURR thermal neutron sources for BNCT small-animal research
Author:
Publisher
Elsevier BV
Subject
Radiation
Reference6 articles.
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1. Coupling Between MCNPX Code and Delphi 7 Programming Language for Studying Neutron Behavior in a New Physical Model of Liver Tissue in Neutron Radiation Therapy;Journal of Medical Imaging and Health Informatics;2018-02-01
2. Neutron flux and gamma dose measurement in the BNCT irradiation facility at the TRIGA reactor of the University of Pavia;Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms;2018-01
3. Validation and Comparison of the Therapeutic Efficacy of Boron Neutron Capture Therapy Mediated By Boron-Rich Liposomes in Multiple Murine Tumor Models;Translational Oncology;2017-08
4. Presenting and simulating an innovative model of liver phantom and applying two methods for dosimetry of it in neutron radiation therapy;REP PRACT ONCOL RADI;2017
5. Design and Simulation of a New Model for Treatment by NCT;Science and Technology of Nuclear Installations;2012
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