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

Ceramic breeder material development

N. Roux, S. Tanaka, C. Johnson, R. Verrall1998年Fusion Engineering and DesignIF 1.7出版社

AbstractLithium-based ceramics have long been recognized as promising tritium-breeding materials for fusion reactor blankets. In particular, their high thermal stability and chemical inertness are favorable safety characteristics. The most important qualification for a candidate ceramic breeder material is most likely, the ability to withstand the rigors of long-term irradiation at high temperature and under large temperature gradients. As a group, the lithium-based ceramics have shown good irradiation behaviour and excellent tritium release characteristics. Individual materials performance will depend upon the actual application, namely, pebble bed versus pellet concept, higher versus lower cooling temperature, etc. Recently Li2ZrO3 and Li2TiO3 were selected as the breeder material for the ITER breeding blanket due to their excellent tritium release behaviour at low temperature. Issues being addressed in support of current blanket design studies will be highlighted.

日本語訳

リチウム基セラミックスは、核融合炉ブランケット用のトリチウム増殖材料として長年にわたり認識されてきた。特に、その高い熱安定性と化学的不活性性は、安全性の面で好ましい特性である。候補となるセラミック増殖材料にとって最も重要な資格は、高温かつ大きな温度勾配下での長期間の照射に耐える能力であると考えられる。リチウム基セラミックスは、グループとして、良好な照射挙動と優れたトリチウム放出特性を示してきた。個々の材料の性能は、実際の用途、すなわちペブルベッド方式かペレット方式か、冷却温度の高低などに依存する。最近では、Li2ZrO3およびLi2TiO3が、低温での優れたトリチウム放出挙動により、ITER増殖ブランケットの増殖材料として選定された。現在のブランケット設計研究を支援するために取り組まれている課題について、重点的に述べる。

装置

iter低精度(概要文一致)

wiki

Ceramic breeder
この論文にはまだAI要約がありません。

関連論文

Summary of experimental results for ceramic breeder materials

1995Fusion Engineering and Design

Ceramic pebble bed development for fusion blankets

1995Fusion Engineering and Design

Status of EC solid breeder-blanket designs and R&D for DEMO fusion reactors

1995Fusion Engineering and Design

Prospects of ceramic tritium breeder materials

1989Fusion Engineering and Design

Enhancement of tritium release from ceramic breeders with impregnated catalytic additives

2000Fusion Engineering and Design

ITER breeding blanket design for the enhanced performance phase

1998Fusion Engineering and Design

Comparison of lithium and the eutectic lead-lithium alloy, two candidate liquid metal breeder materials for self-cooled blankets

1995Fusion Engineering and Design

Tritium breeding capability of water cooled ceramic breeder blanket with different container designs

2019Fusion Engineering and Design

Experimental thermo-mechanical testing apparatus for a DEMO relevant blanket design of a ceramic cladded pin

1991Fusion Engineering and Design

Development of advanced blanket materials for a solid breeder blanket of a fusion reactor

2003Nuclear Fusion