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Dependence of Fast Reactor Fuel Burnup Characteristics on Nuclear Data Libraries

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大木 繁夫; 神 智之*

Oki, Shigeo; Jin, Tomoyuki*

高速炉の重金属組成に関する燃焼計算及び核データ感度解析を実施した。次の核データライブラリを比較した: JEF-2.2, ENDF/B-VI Release 5, JENDL-3.2, JENDL-3.3。主要重金属核種(235U, 238U, 239Pu, 240Pu, 241Pu)についての相違は、それらの1サイクル燃焼後の個数密度がライブラリ間で1ないし2%を超えて変化せず、小さいものであった。マイナーアクチナイド核種については、特に236U, 237Np, 242mAm, 243Am, Cm同位体では、比較的大きな相違が見られた。それら核種の燃焼後の個数密度は、5%から50%にかけての顕著なライブラリ依存性を示した。一般化摂動理論に基づく燃焼感度解析システムにより、それら相違の原因核種・反応、エネルギー領域を定量的に明らかにした。

Burnup calculation and nuclear-data sensitivity analysis were carried out with respect to the heavy metal composition in fast reactors. The following nuclear data libraries were compared: JEF-2.2, ENDF/B-VI Release 5, JENDL-3.2, and JENDL-3.3. Differences for main heavy metal nuclides (235U, 238U, 239Pu, 240Pu, and 241Pu) were small since the number densities after 1-cycle burnup did not change over 1 or 2 % among those libraries. Relatively large differences were found for minor actinide nuclides, especially for 236U, 237Np, 242mAm, 243Am, and curium isotopes. The number densities for these nuclides after burnup showed remarkable library dependence over 5 % through 50 %. A burnup sensitivity analytical system based on the generalized perturbation theory enabled us to find out quantitatively the causative nuclides and reactions, as well as their energy regions.

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パーセンタイル:79.3

分野:Nuclear Science & Technology

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