RADIOISOTOPES
Online ISSN : 1884-4111
Print ISSN : 0033-8303
ISSN-L : 0033-8303
ポジトロンエミッショントモグラフィ測定におけるポジトロン放射ラジオアイソトープ搬送パイプの遮蔽
蜂谷 武憲羽上 栄一庄司 安明相沢 康夫菅野 巌上村 和夫半田 昌彦森 純一深川 明久
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1989 年 38 巻 9 号 p. 377-380

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In the unit housing of a compact cyclotron and positron emission CT (PET), positron emitting gas such as15O, 11C, C15O2, C15O etc. is supplied from a cyclotron to a PET room through a transportation pipe with an appropriate shield to reduce positron annihilation radiation. This paper discribes the effect of lead and concrete shields with various thickness.
Using lead or concrete shield blocks with various thicknesses, radiation leakage through the shield was measured by an ionization chamber type survey meter during continuous and constant supply of15Ogas of 1.85 GBq/min concentration which is the maximum dose for clinical use. The leakage radiation measured was 213.7, 56.0, 15.3, 5.0 μSv/week for lead shield with 1, 2, 3, and 4 cm thickness, respectively, and 193. 3, 30.5 and 5.1 μSv/ week for concrete shields with thickness of 10, 20, and 30 cm, respectively. The present study shows that to keep less than 300μSv/week, which is the permissible dose rate of the boundary zone around the radiation controlled area by Japan Science and Technology Agency, it is required to use more than 8 mm thick lead shield or 7 cm thick concrete for continuous supply of 1.85 GBq/min15Ogas.

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© 社団法人 日本アイソトープ協会
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