高エネルギー陽子加速器で生成される放射性核種に対する内部被ばく線量係数; ICRP Publicationに収録されていない核種の係数

Material type: 文書・図像類

Author: 河合勝雄ほか

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Publication date: 2002-05

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Note (General)：: Effective dose coefficients by inhalation and ingestion have been calculated for 334 nuclides, including (1) nuclides with half-lives $\ge$ 10min and ...

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Summary, etc.：: Effective dose coefficients by inhalation and ingestion have been calculated for 334 nuclides, including (1) nuclides with half-lives $\ge$ 10min and ...

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Material Type: 文書・図像類
Title: 高エネルギー陽子加速器で生成される放射性核種に対する内部被ばく線量係数; ICRP Publicationに収録されていない核種の係数
Author/Editor: 河合勝雄
遠藤章
野口宏
Author Heading: 河合勝雄
遠藤章
野口宏
Publication Date: 2002-05
Publication Date (W3CDTF): 2002-05
Alternative Title: Dose coefficients for radionuclides produced in high energy proton accelerator facilities; Coefficients for radionuclides not listed in ICRP publications
Periodical title: JAERI-Data/Code 2002-013
Text Language Code: eng
Target Audience: 一般
Note (General): Effective dose coefficients by inhalation and ingestion have been calculated for 334 nuclides, including (1) nuclides with half-lives $\ge$ 10min and their daughters that are not listed in ICRP Publications and (2) nuclides with half-lives $<$ 10min that are produced in a spallation target. Dose calculation was carried out using a nuclear decay database DECDC and a decay data library newly compiled from the ENSDF. The dose coefficients were calculated with the computer code DOCAP based on the respiratory tract model and biokinetic model of ICRP. The calculated results are presented as tables, which are the same forms as those in ICRP Publs.68 and 72. The complete listings of the dose coefficients are arranged on a CD-ROM, DoseCD, as indexed tables for inhalation of ten particle sizes, ingestion and injection into blood for workers and members of the public. The dose coefficients calculated in the present study are useful to calculate internal doses for a variety of radionuclides produced in high energy proton accelerator facilities.
半減期10分以上の核種とそれらの娘核種の中でICRP Publicationに収録されていない核種、及び、核破砕中性子ターゲット中に生成される半減期10分未満の核種等、計334核種に対して、単位摂取量あたりの預託実効線量(線量係数)等を計算した。線量計算には、原研において既に整備されているDECDC、また、核破砕ターゲット中に生成される核種に対して、評価済核構造データファイル(ENSDF)から新たに編集した崩壊データライブラリを用いた。線量係数の計算は、ICRPの呼吸気道モデル及び体内動態モデルに基づいた計算コード“DOCAP"を用いて行った。計算した線量係数等は、ICRP Publ.68及び72と同一形式の表にまとめた。さらに、核種ごとに、作業者及び公衆の各年齢群について、10種類の粒径に対する吸入摂取,経口摂取,血液注入に対して計算した線量係数等の表をCD-ROM“DoseCD"に収録し、検索・閲覧できるように整備した。本研究により計算された線量係数等を、ICRPにより既に整備されている線量係数等と併せることにより、大強度陽子加速器施設において生成される多様な核種に対する内部被ばく線量評価に対応することが可能となった。
Source: /JAERI-Data-Code-2002-013-DoseCD.pdf （fulltext）
https://jopss.jaea.go.jp/pdfdata/JAERI-Data-Code-2002-013-DoseCD.pdf
Access Restrictions: 限定公開
Data Provider (Database): 国立情報学研究所 : 学術機関リポジトリデータベース（IRDB）（機関リポジトリ）
https://irdb.nii.ac.jp
Original Data Provider (Database): 日本原子力研究開発機構 : JOPSS:JAEA Originated Papers Searching System