Experimental and computational determination of neutron dose equivalent around radiotherapy accelerators

Radiation Protection Dosimetry

Volumn 107, Issue 4, 2003, Pages 225-232

  Waller, Edward J ^a,b   Jamieson, T J ^a,b   Cole, D ^a,b   Cousins, T ^a,b   Jammal, R B ^b,c  

^a SCIENCE APPLICATIONS INTERNATIONAL CORPORATION   (United States)

^b DEFENCE RESEARCH AND DEVELOPMENT CANADA   (Canada)

^c CANADIAN NUCLEAR SAFETY COMMISSION   (Canada)

Author keywords

[No Author keywords available]

Indexed keywords

ANALYTIC METHOD; ARTICLE; CANADA; CONTROLLED STUDY; EXPERIMENTATION; GAMMA RADIATION; LINEAR ACCELERATOR; MONTE CARLO METHOD; NEUTRON DOSIMETRY; RADIATION DETECTOR; RADIOSENSITIVITY; RADIOTHERAPY;

EID: 0942277188     PISSN: 01448420     EISSN: None     Source Type: Journal    
DOI: 10.1093/oxfordjournals.rpd.a006394     Document Type: Article

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