Calculation of Monitoring Quantities for 239Pu Using ICRP Dosimetric Models for Internal Exposure.

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  • ISHIGURE Nobuhito
    Division of Radiotoxicology and Protection, National Institute of Radiological Sciences
  • NAKANO Takashi
    Division of Radiotoxicology and Protection, National Institute of Radiological Sciences
  • ENOMOTO Hiroko
    Division of Radiotoxicology and Protection, National Institute of Radiological Sciences
  • INABA Jiro
    National Institute of Radiological Sciences

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Other Title
  • ＩＣＲＰの内部被ばく線量評価モデルに基づく｀２３９´Ｐｕのモニタリング量の計算
  • ICRP ノ ナイブ ヒバクセンリョウ ヒョウカ モデル ニ モトズク 239Pu ノ モニタリングリョウ ノ ケイサン

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Abstract

Plutonium (Pu) is one of the most important elements from the viewpoint of radiotoxicology and protection. The International Commission on Radiological Protection (ICRP) recently revised the respiratory tract model and biokinetic models for selected elements, including Pu. The monitoring quantities for inhaled 239Pu such as lung retention and daily excretion rate have been computed. The aerosols of 5μm Activity Median Aerodynamic Diameter (AMAD) and 1μm AMAD were treated by using these new models. The conversion coefficients from the monitoring quantities to the effective dose of 239Pu have been obtained. Besides the graphical representation, the computed monitoring quantities have been approximately represented by a summation of exponential functions. The present results provide useful data for the design of monitoring programs and for the interpretation of the monitoring results in occupational exposure.

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