FusionPapers
図版検索トレンドwiki日本の研究
© 2026 FUSIONPAPERS
About法務情報
トップに戻る

Three-dimensional neutronic analysis of the European ceramic BIT DEMO blanket

L. Giancarli, L. Petrizzi, C. Diop, V. Rado1991年Fusion Engineering and DesignIF 1.7出版社

AbstractThe present study concerns the 3-D geometry evaluations of the tritium breeding ration of the breeder-in-tube helium-cooled ceramic blanket performed at CEA and ENEA in the framework of the recently released DEMONET specifications. For the calculations the nuclear data have all been derived by the European Fusion File (EFF-1), but different Monte Carlo codes, and different design variants and geometrical models have been used. A benchmark calculation has been defined in order to better analyse the results; such an exercise has shown that TBR differences of a few percent could be due to the calculation methods. The determined global TBR ranges from 1.06 in the CEA results to 1.15 in the ENEA results, the expected difference being mainly due to the greater neutron coverage of the ENEA variant of the design. Heat deposition density and He production in beryllium are also given.

日本語訳

本論文は、CEAおよびENEAが、最近公開されたDEMONET仕様の枠組みの中で実施した、ヘリウム冷却セラミックブランケットのトリチウム増殖比に関する3次元幾何学評価について述べるものである。計算には、核データはすべて欧州核融合ファイル(EFF-1)から導出されたが、異なるモンテカルロコード、異なる設計バリアント、および異なる幾何学モデルが使用された。結果をより適切に分析するために、ベンチマーク計算が定義された。この取り組みにより、トリチウム増殖比の数パーセントの差異は計算方法に起因し得ることが示された。決定された全体トリチウム増殖比は、CEAの結果では1.06からENEAの結果では1.15の範囲であり、その差は主にENEAの設計バリアントにおける中性子カバレッジの向上によるものである。ベリリウム中の発熱密度とヘリウム生成量も併せて示す。

wiki

DEMODEMO blanket
この論文にはまだAI要約がありません。

関連論文

Helium induced swelling and tritium trapping mechanisms in irradiated beryllium: a comprehensive approach

1995Fusion Engineering and Design

Neutronic and photonic analysis of the single box water-cooled lithium lead blanket for a DEMO reactor

1998Fusion Engineering and Design

Assessment of the importance of neutron multiplication for tritium production

2017Nuclear Fusion

Fusion neutron source blanket: requirements for calculation accuracy and benchmark experiment precision

2017Nuclear Fusion

Conceptual design of solid-type PbxLiy eutectic alloy breeding blanket for CFETR

2023Nuclear Fusion

Analysis of a segmentation approach to breeder blanket design and the utilisation of FLiBe as a novel neutron reflector

2025Nuclear Fusion

Fusion nuclear systems design and analysis

1988Fusion Engineering and Design

Optimization process for the design of the DCLL blanket for the European DEMOnstration fusion reactor according to its nuclear performances

2017Nuclear Fusion

Neutronics analysis of the dual-cooled waste transmutation blanket for the FDS

2002Fusion Engineering and Design

Ceramic helium-cooled blanket test module

2000Fusion Engineering and Design