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Title: Neutron, Proton, and Photonuclear Cross Sections for Radiation Therapy and Radiation Protection

Abstract

The authors review recent work at Los Alamos to evaluate neutron, proton, and photonuclear cross section up to 150 MeV (to 250 MeV for protons), based on experimental data and nuclear model calculations. These data are represented in the ENDF format and can be used in computer codes to simulate radiation transport. They permit calculations of absorbed dose in the body from therapy beams, and through use of kerma coefficients allow absorbed dose to be estimated for a given neutron energy distribution. For radiation protection, these data can be used to determine shielding requirements in accelerator environments, and to calculate neutron, proton, gamma-ray, and radionuclide production. Illustrative comparisons of the evaluated cross section and kerma coefficient data with measurements are given.

Authors:
Publication Date:
Research Org.:
Los Alamos National Lab., NM (US)
Sponsoring Org.:
USDOE Office of Defense Programs (DP) (US)
OSTI Identifier:
759286
Report Number(s):
LA-UR-98-4139
TRN: US0004331
DOE Contract Number:  
W-7405-ENG-36
Resource Type:
Conference
Resource Relation:
Conference: International Meeting on Computational Methods in Track Structure Simulation in Physical and Biological Sciences, Theory and Applications, Oxford (GB), 09/10/1998--09/13/1998; Other Information: PBD: 10 Sep 1998
Country of Publication:
United States
Language:
English
Subject:
62 RADIOLOGY AND NUCLEAR MEDICINE; 61 RADIATION PROTECTION AND DOSIMETRY; 73 NUCLEAR PHYSICS AND RADIATION PHYSICS; CROSS SECTIONS; ENERGY SPECTRA; NEUTRONS; NUCLEAR DATA COLLECTIONS; PROTONS; RADIATION DOSES; RADIATION PROTECTION; RADIATION TRANSPORT; RADIOISOTOPES; RADIOTHERAPY

Citation Formats

Chadwick, M.B.. Neutron, Proton, and Photonuclear Cross Sections for Radiation Therapy and Radiation Protection. United States: N. p., 1998. Web.
Chadwick, M.B.. Neutron, Proton, and Photonuclear Cross Sections for Radiation Therapy and Radiation Protection. United States.
Chadwick, M.B.. Thu . "Neutron, Proton, and Photonuclear Cross Sections for Radiation Therapy and Radiation Protection". United States. doi:. https://www.osti.gov/servlets/purl/759286.
@article{osti_759286,
title = {Neutron, Proton, and Photonuclear Cross Sections for Radiation Therapy and Radiation Protection},
author = {Chadwick, M.B.},
abstractNote = {The authors review recent work at Los Alamos to evaluate neutron, proton, and photonuclear cross section up to 150 MeV (to 250 MeV for protons), based on experimental data and nuclear model calculations. These data are represented in the ENDF format and can be used in computer codes to simulate radiation transport. They permit calculations of absorbed dose in the body from therapy beams, and through use of kerma coefficients allow absorbed dose to be estimated for a given neutron energy distribution. For radiation protection, these data can be used to determine shielding requirements in accelerator environments, and to calculate neutron, proton, gamma-ray, and radionuclide production. Illustrative comparisons of the evaluated cross section and kerma coefficient data with measurements are given.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Thu Sep 10 00:00:00 EDT 1998},
month = {Thu Sep 10 00:00:00 EDT 1998}
}

Conference:
Other availability
Please see Document Availability for additional information on obtaining the full-text document. Library patrons may search WorldCat to identify libraries that hold this conference proceeding.

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