Calculations of neutron shielding data for 10-100 MeV proton accelerators

Radiation Protection Dosimetry

Volumn 116, Issue 1-4, 2005, Pages 245-251

  Chen, C C ^a   Sheu, R J ^b   Jiang, S H ^a  

^a NATIONAL TSING HUA UNIVERSITY   (Taiwan)

^b NATIONAL SYNCHROTRON RADIATION RESEARCH CENTER   (Taiwan)

Author keywords

[No Author keywords available]

Indexed keywords

ALUMINUM; CARBON; COPPER; IRON; NITROGEN; PROTON; TUNGSTEN;

ACCURACY; ARTICLE; CALCULATION; MONTE CARLO METHOD; NEUTRON RADIATION; RADIATION DOSE; RADIATION ENERGY; RADIATION SHIELD;

COMPUTER SIMULATION; CONSTRUCTION MATERIALS; EQUIPMENT DESIGN; EQUIPMENT FAILURE ANALYSIS; LINEAR ENERGY TRANSFER; MATERIALS TESTING; MODELS, STATISTICAL; NEUTRONS; PARTICLE ACCELERATORS; PROTONS; RADIATION DOSAGE; RADIATION PROTECTION; RADIOMETRY;

EID: 31544433406     PISSN: 01448420     EISSN: None     Source Type: Journal    
DOI: 10.1093/rpd/nci193     Document Type: Article

References (7)

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6. International Commission on Radiological Protection. Conversion coefficients for use in radiological protection against external radiation. ICRP Publication 74. Ann. ICRP 26(3-4) (Oxford: Pergamon Press) (1996).
7. Agosteo, S., Fassò, A., Ferrari, A., Sala, P. R., Silari, M. and Tabarelli de Fatis, P. Double differential distributions and attenuation in concrete for neutron produced by 100-400 MeV protons on iron and tissue targets. Nucl. Instrum. Methods Phys. Res. B 114, 70-80 (1996).