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Effect of radial zoning of $$^{241}$$Am content on homogenization of denatured Pu with broad range of neutron energy based on U irradiation test in the experimental fast reactor Joyo

幅広い中性子エネルギー環境を有する常陽でのU照射試験に基づくPu変質の均質化に対する$$^{241}$$Am径方向分散の影響

芝 知宙*; 相楽 洋*; 大西 貴士 ; 小山 真一 ; 前田 茂貴  ; Han, C. Y.*; 齊藤 正樹*

Shiba, Tomooki*; Sagara, Hiroshi*; Onishi, Takashi; Koyama, Shinichi; Maeda, Shigetaka; Han, C. Y.*; Saito, Masaki*

幅広い中性子エネルギーを有する高速実験炉「常陽」にて照射したUサンプルの化学分析試験を行った。Uサンプルの照射解析を行い、解析手法を構築した。本解析手法を利用して、Am-劣化ウランペレットの照射解析を行った。その結果、ペレットの内側と外側において$$^{241}$$Amを異なる濃度で添加することにより、ペレット全体で$$^{238}$$Pu濃度が均一となることを明らかにした。

The design consideration of DU-Am oxide fuel pin was performed for Pu denaturing in the framework of the protected plutonium production based on the irradiation analyses of the depleted U (DU) samples irradiated in the environment of broad range of neutron energy in the experimental fast reactor Joyo. From the results of irradiation analyses of DU, it was confirmed that there is a strong dependence of transmutation behavior of DU on the resonance neutron ratio even in a fast reactor. Also, it was confirmed that there is a strong effect of sample material form and shape on generated Pu nuclide inventory especially near the reflector area ($$>$$20% resonance neutron ratio), because of the intensive self-shielding of $$^{238}$$U, though less is expected for $$^{241}$$Am. Sensitivity study of hypothetical DU-Am oxide fuel pellet irradiation on neutron energy and burn-up was performed to evaluate significant gradient of radial $$^{238}$$Pu isotopic composition profile (e.g., from 12 to 18% distribution in 3% Am doping, in 30% resonance neutron ratio and in 4.0$$times$$10$$^{22}$$ [n/cm$$^{2}$$] of neutron fluence inside a large pellet with softened neutron spectrum), and vulnerability of the fuel pellet surface in terms of Pu denaturing was revealed. Design consideration of radial zoning of $$^{241}$$Am content was introduced to flatten the radial distribution of isotopic composition of Pu. The results of radial zoning of $$^{241}$$Am (4% and 3% of Am in the outer and inner zone of DU-Am oxide fuel pellet) in hypothetical irradiation neutronics analysis showed the radial profile of produced Pu is over 15 at.% of $$^{238}$$Pu isotopic composition in any zone and meets the criteria of Kimura et al. based on decay heat of Pu to impede utilization to fission explosive devices.

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