Dose assessment from activated sodium within a body in criticality accidents.
Some data were derived using recent sophisticated methods to rapidly convert specific activity of induced 24Na to average dose over a whole body in criticality accidents. Monte Carlo calculations using the MCNP-4B code were performed to study energy spectra of neutrons and gamma rays for some criticality systems with fissile uranium. Absorbed dose to the human body and the activation of sodium were also analysed against external radiation by simulations using a MIRD-5 type phantom and the calculated energy spectra. It was found that the neutron dose assessment from induced 24Na would be important to give medical staff initial guidance for treatment of a victim. However, the energy distribution of incident neutrons to the human body did not significantly influence the conversion from the specific activity of 24Na to dose from gamma rays induced within a body. Analyses were made to clarify the dependence of conversion from 24Na specific activity to neutron dose on the orientation toward the source and the size of the human body. The total dose estimated based upon the obtained data ranged from 33 mGy to 514 mGy for a given specific activity of 1.4 kBq 24Na per g 23Na for some criticality assemblies. This study suggested that the size of uranium solution and material around the fuel should be defined to properly estimate the total dose, including the dose from external photons.
Takahashi
F
F
Japan Atomic Energy Research Institute, Shirakata-Shirane 2-4, Tokai-mura, Naka-gun, Ibaraki, 319-1195, Japan. taka2@popsvr.tokai.jaeri.go.jp
Endo
A
A
Yamaguchi
Y
Y
D004307:Dose-Response Relationship, Radiation; D005720:Gamma Rays; D006801:Humans; D009010:Monte Carlo Method; D009502:Neutrons; D019047:Phantoms, Imaging; D017785:Photons; D011829:Radiation Dosage; D011874:Radiometry / Q000379:methods*; D012964:Sodium
D012964:Sodium