Tritium release behavior from liquid tritium breeding materials for fusion reactor blanket under neutron irradiation

1998 ◽  
Vol 32 (1-2) ◽  
pp. 97-112 ◽  
Author(s):  
Takayuki Terai ◽  
Satoru Tanaka
2013 ◽  
Vol 442 (1-3) ◽  
pp. S490-S493 ◽  
Author(s):  
Aigars Vītiņš ◽  
Gunta Ķizāne ◽  
Andris Matīss ◽  
Elīna Pajuste ◽  
Vitālijs Zubkovs

2016 ◽  
Vol 697 ◽  
pp. 814-817 ◽  
Author(s):  
Mao Qiao Xiang ◽  
Ying Chun Zhang ◽  
Yun Zhang ◽  
Chao Fu Wang ◽  
Yong Hong Yu

Lithium-containing ceramic pebbles, the likeliest tritium breeders in the future, are needed in the fusion reactor blankets. Currently, lithium orthosilicate (Li4SiO4) has been widely studied for tritium breeding pebble as it has 1250 °C melting temperature, 0.54 g/cm3 lithium concentration, and excellent tritium release performance. For simplifying reaction mechanism and the preparation technology to tailor the properties, the Li4SiO4 breeders were produced with an agar-gel technology using stable and cheap lithium metasilicate and lithium carbonate as starting materials. In addition, the solid (the prepared powder and ager) and liquid (deionized water) weight ration of the green pebble was also evaluated. The crush load, density, and open porosity achieved 36 N, 89.3% TD, and 4.5 %, respectively.


2012 ◽  
Vol 87 (7-8) ◽  
pp. 1253-1257 ◽  
Author(s):  
Yoshinori Kawamura ◽  
Kentaro Ochiai ◽  
Tsuyoshi Hoshino ◽  
Keitaro Kondo ◽  
Yasunori Iwai ◽  
...  

1984 ◽  
Vol 86 (4) ◽  
pp. 405-409 ◽  
Author(s):  
H. Hasegawa ◽  
H. Nakashima ◽  
T. Matsui ◽  
M. Ohta

1995 ◽  
Vol 28 ◽  
pp. 708-715
Author(s):  
Chikara Konno ◽  
Yukio Oyama ◽  
Fujio Maekawa ◽  
Yujiro Ikeda ◽  
Kazuaki Kosako ◽  
...  

1989 ◽  
Vol 8 ◽  
pp. 407-413 ◽  
Author(s):  
J. Charpin ◽  
F. Botter ◽  
M. Briec ◽  
B. Rasneur ◽  
E. Roth ◽  
...  

1998 ◽  
Vol 25 (6) ◽  
pp. 359-375 ◽  
Author(s):  
Sanjay Gupta ◽  
Suresh Garg ◽  
Feroz Ahmed

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