Accurate dose assessment system for an exposed person utilising radiation transport calculation codes in emergency response to a radiological accident.
A system has been developed to assess radiation dose distribution inside the body of exposed persons in a radiological accident by utilising radiation transport calculation codes-MCNP and MCNPX. The system consists mainly of two parts, pre-processor and post-processor of the radiation transport calculation. Programs for the pre-processor are used to set up a 'problem-dependent' input file, which defines the accident condition and dosimetric quantities to be estimated. The program developed for the post-processor part can effectively indicate dose information based upon the output file of the code. All of the programs in the dosimetry system can be executed with a generally used personal computer and accurately give the dose profile to an exposed person in a radiological accident without complicated procedures. An experiment using a physical phantom was carried out to verify the availability of the dosimetry system with the developed programs in a gamma ray irradiation field.
Takahashi
F
F
Japan Atomic Energy Agency (JAEA), Shirakata 2-4, Tokai-mura, Ibaraki 319-1195, Japan. takahashi.fumiaki@jaea.go.jp
Shigemori
Y
Y
Seki
A
A
D004632:Emergency Medical Services / Q000379:methods*; D004781:Environmental Exposure / Q000032:analysis*; D006801:Humans; D009010:Monte Carlo Method; D011835:Radiation Protection / Q000379:methods*; D018788:Radioactive Hazard Release; D015203:Reproducibility of Results; D018570:Risk Assessment / Q000379:methods*; D012307:Risk Factors; D012680:Sensitivity and Specificity; D012984:Software