Styudy of precise measurement of neutron capture cross section for radioactive nuclear wastes
| Project/Area Number |
23561019
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| Research Category |
Grant-in-Aid for Scientific Research (C)
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| Allocation Type | Multi-year Fund |
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| Section | 一般 |
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| Research Field |
Nuclear engineering
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| Research Institution | Japan Atomic Energy Agency |
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Principal Investigator |
NAKAMURA Shoji 独立行政法人日本原子力研究開発機構, 原子力科学研究部門・原子力基礎工学研究センター, 研究副主幹 (90421461)
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| Project Period (FY) |
2011 – 2013
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| Project Status |
Completed (Fiscal Year 2013)
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| Budget Amount *help |
¥5,720,000 (Direct Cost: ¥4,400,000、Indirect Cost: ¥1,320,000)
Fiscal Year 2013: ¥390,000 (Direct Cost: ¥300,000、Indirect Cost: ¥90,000)
Fiscal Year 2012: ¥520,000 (Direct Cost: ¥400,000、Indirect Cost: ¥120,000)
Fiscal Year 2011: ¥4,810,000 (Direct Cost: ¥3,700,000、Indirect Cost: ¥1,110,000)
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| Keywords | 原子力ｴﾈﾙｷﾞｰ / 放射線 / 中性子捕獲断面積 / 放射性核種 / マイナーアクチニド / 核データ / ネプツニウム237 / 熱中性子捕獲断面積 / ガンマ線放出率 / プロトアクチニウム233 / 放射化法 / マイナーアクチノイド / アメリシウム243 / 同時計測 |
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| Research Abstract |
The neutron capture cross-section was measured by an activation method at Kyoto Reactor Research Institute. A Gd foil was used to set Cut-off energy as 0.13eV to pay attention in the 0.489-eV resonance of Np-237. The amount for Np-237 and Np-238 were measured from measurements of gamma-rays emitted from Pa-233 and Np-238. The neutron fluxes were monitored with Co/Al and Co/Al alloy wires. The thermal-neutron capture cross-section of Np-237 was derived from the production amount of Np-238 and neutron fluxes, and obtained as 198+-10(b). It was found that this result was about 10% larger than the evaluated value (178.1(b)).
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Report
(4 results)
Research Products
(8 results)
