WEKO3
アイテム
Measurement of natural radioactive nuclide concentrations in various metal ores used as industrial raw materials in Japan and estimation of dose received by workers handling them
https://repo.qst.go.jp/records/45630
https://repo.qst.go.jp/records/45630a68c13ce-be27-4bd9-b73d-c2ba767cf8fa
| Item type | 学術雑誌論文 / Journal Article(1) | |||||
|---|---|---|---|---|---|---|
| 公開日 | 2009-09-09 | |||||
| タイトル | ||||||
| タイトル | Measurement of natural radioactive nuclide concentrations in various metal ores used as industrial raw materials in Japan and estimation of dose received by workers handling them | |||||
| 言語 | ||||||
| 言語 | eng | |||||
| 資源タイプ | ||||||
| 資源タイプ識別子 | http://purl.org/coar/resource_type/c_6501 | |||||
| 資源タイプ | journal article | |||||
| アクセス権 | ||||||
| アクセス権 | metadata only access | |||||
| アクセス権URI | http://purl.org/coar/access_right/c_14cb | |||||
| 著者 |
Iwaoka, Kazuki
× Iwaoka, Kazuki× Tagami, Keiko× Yonehara, Hidenori× 岩岡 和輝× 田上 恵子× 米原 英典 |
|||||
| 抄録 | ||||||
| 内容記述タイプ | Abstract | |||||
| 内容記述 | Natural resources such as ores and rocks contain natural radioactive nuclides at various concentrations. If these resources contain high concentrations of natural radioactive nuclides, workers handling them might be exposed to significant levels of radiation. Therefore, it is important to investigate the radioactive activity in these resources. In this study, concentrations of radioactive nuclides in Th, Zr, Ti, Mo, Mn, Al, W, Zn, V, and Cr ores used as industrial raw materials in Japan were investigated. The concentrations of 238U and 232Th were determined by inductively coupled plasma mass spectrometry (ICP-MS), while those of 226Ra, 228Ra, and 40K were determined by gamma-ray spectrum. We found the concentrations of 238U series, 232Th series, and 40K in Ti, Mo, Mn, Al, W, Zn, V, and Cr ores to be lower than the critical values defined by regulatory requirements as described in the International Atomic Energy Agency (IAEA) Safety Guide. The doses received by workers handling these materials were estimated by using methods for dose assessment given in a report by the European Commission. In transport, indoor storage, and outdoor storage scenarios, an effective dose due to the use of Th ore was above 4.3  10−2 Sv y−1, which was higher than that of the other ores. The maximum value of effective doses for other ores was estimated to be about 4.5  10−4 Sv y−1, which was lower than intervention exemption levels (1.0  10−3 Sv y−1) given in International Commission of Radiological Protection (ICRP) Publication 82. | |||||
| 書誌情報 |
Journal of Environmental Radioactivity 巻 100, 号 11, p. 993-997, 発行日 2009-11 |
|||||
| ISSN | ||||||
| 収録物識別子タイプ | ISSN | |||||
| 収録物識別子 | 0265-931X | |||||
