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Evaluation of neutron capture cross section on Pb-205 with photonuclear data
https://repo.qst.go.jp/records/66583
https://repo.qst.go.jp/records/665831919e96c-2f18-4b3f-995d-b646661fb809
| Item type | 会議発表用資料 / Presentation(1) | |||||
|---|---|---|---|---|---|---|
| 公開日 | 2018-01-10 | |||||
| タイトル | ||||||
| タイトル | Evaluation of neutron capture cross section on Pb-205 with photonuclear data | |||||
| 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_c94f | |||||
| 資源タイプ | conference object | |||||
| 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 |
岩本, 信之
× 岩本, 信之× 静間, 俊行× 静間 俊行 |
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| 抄録 | ||||||
| 内容記述タイプ | Abstract | |||||
| 内容記述 | Transmutation and reduction of high level radioactive wastes (e.g. minor actinides) produced in nuclear reactors are expected by an accelerator driven system (ADS). Japan Atomic Energy Agency proposed that Pb and Bi are used as a spallation target and coolant. The neutronics design was performed without including 205Pb, which is a long-lived radioactive nuclide with half-life of 1.7×107 years and thus has long-lasting radiotoxicity. 205Pb is produced by the neutron capture reaction on 204Pb. In order to evaluate the accumulated amount of 205Pb, the neutron capture cross section of 205Pb is needed. However, it has not been measured in the keV to MeV neutron energy region. In the present work the calculations of cross sections were performed by the nuclear reaction calculation code, CCONE. Measured photonuclear data of (γ,γ) reaction and photoneutron cross sections were used to evaluate photon strength function of 206Pb. The (γ,γ) reaction data used were newly obtained by an experiment at HZDR. The fixed photon strength function was applied to calculate the neutron capture cross sections of 205Pb. The resulting cross section is smaller than the data of 204Pb in the relevant energy region. As a result, it is predicted that the accumulation of 205Pb is negligible unless the Pb-Bi target is used under the conditions of high neutron flux (>5×1016 n/cm2/s) and long-term use (>5 years). |
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| 会議概要（会議名, 開催地, 会期, 主催者等） | ||||||
| 内容記述タイプ | Other | |||||
| 内容記述 | 16th International Symposium on Capture Gamma-Ray Spectroscopy and Related Topics | |||||
| 発表年月日 | ||||||
| 日付 | 2017-09-21 | |||||
| 日付タイプ | Issued | |||||
