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論文

Evaluation of neutron capture cross section on $$^{205}$$Pb with photonuclear data

岩本 信之; 静間 俊行*

EPJ Web of Conferences, 178, p.06004_1 - 06004_3, 2018/05

 被引用回数:0 パーセンタイル:0(Optics)

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 $$^{205}$$Pb, which is a long-lived radioactive nuclide with half-life of 1.7$$times$$10$$^{7}$$ years and thus has long-lasting radiotoxicity. $$^{205}$$Pb is produced by the neutron capture reaction on $$^{204}$$Pb. In order to evaluate the accumulated amount of $$^{205}$$Pb, the neutron capture cross section of $$^{205}$$Pb 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 ($$gamma$$,$$gamma$$) reaction and photoneutron cross sections were used to evaluate photon strength function of $$^{206}$$Pb. The ($$gamma$$,$$gamma$$) 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 $$^{205}$$Pb. The resulting cross section is smaller than the data of $$^{204}$$Pb in the relevant energy region.

論文

Developing reliable reaction gamma-ray data

Dimitriou, P.*; Belgya, T.*; Cho, Y.-S.*; Filipescu, D.*; Firestone, R.*; Goriely, S.*; 岩本 信之; 河野 俊彦*; Kopecky, J.*; Krticka, M.*; et al.

EPJ Web of Conferences, 178, p.06005_1 - 06005_3, 2018/05

 被引用回数:2 パーセンタイル:74.73(Optics)

測定や既存のデータ評価・編集、また基礎科学や応用への利用に向けた巨大双極子共鳴パラメータ等のテーブル作成を基にした光核反応断面積や光子強度関数の開発について報告する。

口頭

Measurements of the $$(n,gamma)$$ cross-section of long-lived fission products as part of the ImPACT Project

Hales, B. P.; 中村 詔司; 木村 敦; 岩本 修

no journal, , 

Nuclear data on the $$(n,gamma)$$ cross-sections of long-lived fission products (LLFPs) is vital for the development of a nuclear transmutation system for the conversion of nuclear waste into stable or more quickly decaying isotopes. As part of the ImPACT Project, research into the $$(n,gamma)$$ cross-sections of the LLFPs $$^{135}$$Cs and $$^{79}$$Se is ongoing, using the neutron time-of-flight (nTOF) method at the ANNRI/MLF/J-PARC facility. nTOF experiments have been conducted to measure the $$(n,gamma)$$ cross-section of stable $$^{133}$$Cs, LLFP $$^{135}$$Cs, and stable $$^{77,78,80}$$Se. (No experiment for LLFP $$^{79}$$Se has yet been conducted.) Analysis of experimental data and the cross-section has been derived for stable $$^{133}$$Cs. Analysis of experimental data is ongoing for LLFP $$^{135}$$Cs, as well as for stable $$^{77,78,80}$$Se. Details of the above experiments and analysis, as well as details on future plans, will be presented.

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