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

Materials analysis of the TITAN-I reversed-field-pinch fusion power core

Shahram Sharafat, Nasr M. Ghoniem, Patrick I.H. Cooke, Rodger C. Martin, Clement P.C. Wong1993年Fusion Engineering and DesignIF 1.7出版社

AbstractThe operating conditions of a compact, high-neutron-wall-loading fusion reactor severely limit the choices for structural, shield, insulator, and breeder materials. In particular the response of plasma-facing materials to radiation, thermal and pressure stresses, and their compatibility with coolants are of primary concern. Material selection issues are investigated for the compact, high mass-power-density TITAN-I reactor design study. In this paper the major findings regarding material performance are discussed. The retention of mechanical strength at relatively high temperatures, low thermal stresses, and compatibility with liquid lithium make vanadium-base alloys a promising material for structural components. Based on limited data, the thermal creep behaviour of V3TiISi and V15Cr5Ti alloys is approximated using the modified minimum committment method. In addition, the effects of irradiation and helium generation are superimposed on the creep behavior of V3Ti1Si. Coolant compatibility issues are investigated. The liquid lithium compatibility of the two vanadium alloys, V15Cr5Ti and V3Ti1Si, are compared, and the latter was chosen as the primary structural-material candidate for the liquid-lithium-cooled TITAN-I reactor. Electrically insulating materials, capable of operating at high temperatures are necessary throughout the fusion reactor device. Electrical insulator-material issues of concern include irradiation induced swelling and conductivity. Both issues are investigated and operating temperatures for minimum swelling and dielectric breakdown strength are identified for spinel (MgAI2O4).

日本語訳

高コンパクトかつ高中性子壁負荷の核融合炉の運転条件は、構造材料、遮蔽材料、絶縁材料、増殖材料の選択肢を厳しく制限する。特に、プラズマ対向材料の放射線、熱応力、圧力応力に対する応答、および冷却材との適合性が主要な関心事となる。コンパクトで高質量出力密度のTITAN-I炉設計研究において、材料選択の問題を調査した。本論文では、材料性能に関する主要な知見について議論する。比較的高温での機械的強度の保持、低熱応力、液体リチウムとの適合性により、バナジウム基合金は構造部品の有望な材料となる。限られたデータに基づき、V-3Ti-1SiおよびV-15Cr-5Ti合金の熱クリープ挙動を、修正最小コミットメント法を用いて近似した。さらに、V-3Ti-1Siのクリープ挙動に対する照射およびヘリウム生成の影響を重畳した。冷却材適合性の問題を調査した。2つのバナジウム合金、V-15Cr-5TiおよびV-3Ti-1Siの液体リチウム適合性を比較し、後者が液体リチウム冷却TITAN-I炉の主要構造材料候補として選定された。核融合炉装置全体において、高温で動作可能な電気絶縁材料が必要である。電気絶縁材料の懸念事項には、照射誘起スエリングおよび導電性が含まれる。両方の課題を調査し、スピネル(MgAl2O4)について、最小スエリングおよび誘電破壊強度のための動作温度を特定した。

wiki

Reversed field pinch
この論文にはまだAI要約がありません。

関連論文

Material selection for the titan reversed-field pinch reactor

1989Fusion Engineering and Design

Properties of V4Cr4Ti for application as fusion reactor structural components

1995Fusion Engineering and Design

European structural materials development for fusion applications

2000Fusion Engineering and Design

Materials selection criteria and performance analysis for the TITAN-II reversed-field-pinch fusion power core

1993Fusion Engineering and Design

Development of advanced high heat flux and plasma-facing materials

2017Nuclear Fusion

Development of vanadium-base alloys for fusion first-wall—blanket applications

1995Fusion Engineering and Design

Thermal-hydraulic and structural design for the lithium-cooled TITAN-I reversed-feeld-pinch reactor

1989Fusion Engineering and Design

The TITAN-II reversed-field-pinch fusion-power-core design

1993Fusion Engineering and Design

Lithium cooled blanket of RF DEMO reactor

2000Fusion Engineering and Design

Thermal-hydraulic and structural design of the TITAN-I reversed-field-pinch fusion power core

1993Fusion Engineering and Design