Dose determination by Monte Carlo - A useful tool in gamma radiation process

Radiation Physics and Chemistry

Volumn 57, Issue 3-6, 2000, Pages 667-670

  Oliveira, C ^a   Salgado, J ^a   Botelho, M Luísa ^a   Ferreira, L M ^a  

^a INSTITUTO TECNOLÓGICO E NUCLEAR   (Portugal)

Author keywords

Amber perspex; Ceric cerous; Dosimetry; MCNP; Monte Carlo

Indexed keywords

COMPUTER SIMULATION; GAMMA RAYS; INDUSTRIAL PLANTS; MATHEMATICAL MODELS; MONTE CARLO METHODS;

AMBER PERSPEX; CERIC-CEROUS DOSIMETERS; PORTUGUESE GAMMA IRRADIATION FACILITY;

DOSIMETRY;

CALCULATION; CONFERENCE PAPER; GAMMA IRRADIATION; RADIATION DOSE DISTRIBUTION; RADIATION PROCESSING; RADIATION STERILIZATION; SIMULATION; SPECTROPHOTOMETRY; STANDARD; SYSTEM ANALYSIS;

EID: 0034102153     PISSN: 0969806X     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0969-806X(99)00459-4     Document Type: Conference Paper

References (5)

1. ASTM 1993. E1205-93. Standard Practice for use of a Ceric-Cerous Dosimetry System, vol. 12.02. Annual book of standards. ASTM, 100 Barr Harbor Drive, West Conshohoken, PA 19428, USA.
2. ASTM 1996. E1276-96. Standard Practice for use of a Polymethylmethacrylate Dosimetry System, vol. 12.02. Annual book of standards. ASTM, 100 Barr Harbor Drive, West Conshoken, PA 19428, USA.
3. Briesmeister J. MCNP™ - A General Monte Carlo N-Particle Transport Code, LA 12625-M, Version 4B. 1997;Los Alamos Laboratory, USA.
4. Cavaco M.C., Almeida J.C., Andrade M.E., Kovács A. Dosimetry commissioning for an industrial cobalt-60 gamma radiation facility. Appl. Radiat. Isot. 42:(12):1991;1185-1188.
5. ISO-11137. Sterilisation of health care products - Requirements for validation and routine control - Radiation sterilisation. 1995;International Organisation for Standardisation, Case Postal 56, CH-1211, Geneve 20, Switzerland.