Monte Carlo simulation of the IRSN CANEL/T400 realistic mixed neutron-photo radiation field

Radiation Protection Dosimetry

Volumn 110, Issue 1-4, 2004, Pages 123-127

  Lacoste, Veronique ^a   Gressier, V ^a  

^a INSTITUT DE RADIOPROTECTION ET DE SÛRETÉ NUCLÉAIRE IRSN   (France)

Author keywords

[No Author keywords available]

Indexed keywords

IRON; POLYETHYLENE; URANIUM; WATER;

ARTICLE; CALCULATION; CALIBRATION; CONTROLLED STUDY; FISSION NEUTRON; MONTE CARLO METHOD; NEUTRON DOSIMETRY; NEUTRON RADIATION; NEUTRON SCATTERING; OCCUPATIONAL EXPOSURE; PHOTON; QUANTITATIVE ANALYSIS; RADIATION DOSE DISTRIBUTION; RADIATION EXPOSURE; RADIATION FIELD; RADIATION MONITORING; RELIABILITY; SIMULATION; WORKPLACE;

BODY BURDEN; CALIBRATION; COMPUTER SIMULATION; COMPUTER-AIDED DESIGN; EQUIPMENT FAILURE ANALYSIS; FRANCE; INTERNATIONALITY; MODELS, STATISTICAL; MONTE CARLO METHOD; NEUTRONS; NUCLEAR REACTORS; OCCUPATIONAL EXPOSURE; PHOTONS; RADIATION DOSAGE; RADIATION PROTECTION; RADIOISOTOPES; RADIOMETRY; REFERENCE STANDARDS; RELATIVE BIOLOGICAL EFFECTIVENESS; REPRODUCIBILITY OF RESULTS; SCATTERING, RADIATION; SENSITIVITY AND SPECIFICITY; URANIUM;

EID: 4644240514     PISSN: 01448420     EISSN: None     Source Type: Journal    
DOI: 10.1093/rpd/nch190     Document Type: Article

References (11)

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