@inproceedings{oai:repo.qst.go.jp:00053088,
 author = {石榑, 信人 and 河内, 清光 and 遠藤, 章 and 山口, 恭弘 and 石榑 信人 and 河内 清光 and 遠藤 章 and 山口 恭弘},
 book = {ウラン加工工場臨界事故に対する環境測定・線量推定(放医研環境セミナーシリーズ ; no.28)},
 issue = {NIRS-M-150},
 month = {Nov},
 note = {The doses for the overexposed patients were estimated by measurement result of specific activity of 24Na in blood.  The present method is almost based on the documents of the International Atomic Energy Agency (IAEA) and the Oak Ridge National Laboratory.  The neutron energy spectrum obtained using ANISN code (Multigroup One-Dimensional Discrete Ordinates Transport Code System with Anisotropic Scattering) was assumed.  The values in ICRP Publication 74 were applied for the doses in each organ per unit neutron fluence.  Gamma-ray dose was indirectly estimated based on (a) the result of the environmental monitoring around the accident site and (b) a graph in IAEA manual which gives kerma ratio of neutron and g-rays as a function of critical volume or atomic ratio of hydrogen to 235U.  Further investigation is in progress to evaluate more accurately the non-uniformity of doses at skin, depth dose distribution, *-ray to neutron dose ratio, etc., where a Monte Carlo codes of MCNP-4B and MCNPX is applied to the critical system accompanied with mathematical phantoms with movable arms and legs whose positions and postures are carefully modeled after those of the patients at the exposure.},
 pages = {154--162},
 publisher = {放医研},
 title = {血中24Na等の分析による線量の推定},
 year = {2001}
}