Reducing beryllium content in mixed bed solid-type breeder blankets

作者: J. Shimwell , S. Lilley , L. Morgan , L. Packer , M. Kovari

DOI: 10.1016/J.FUSENGDES.2015.11.021

关键词:

摘要: Beryllium (Be) is a precious resource with many high value uses, the low energy threshold (n,2n) reaction makes Be an excellent neutron multiplier for use in fusion breeder blankets. Estimates of requirements and available resources suggest that this could represent major supply difficulty solid-type blanket concepts. Reducing quantity required by blankets would help to alleviate problem some extent. In addition, it important reduction does not diminish blanket's performance key aspects such as tritium breeding ratio (TBR), multiplication peak nuclear heating. Mixed pebble bed designs allow fraction be varied throughout blanket. This neutronics study used MCNP 6 investigate linear variations relation depth, order better utilise multiplying Be(n,2n) reactions. Blankets uniform showed little scope mass. varying fractions were able simultaneously 10% less Be, increase amplification 1%, reduce heating 7% maintaining sufficient TBR when compared achievable using composition.

参考文章(18)
Kris Dylst, John Seghers, Frank Druyts, Johan Braet, Removing Tritium and Other Impurities During Industrial Recycling of Beryllium from a Fusion Reactor Fusion Science and Technology. ,vol. 54, pp. 215- 218 ,(2008) , 10.13182/FST08-A1798
Ulrich Fischer, Optimal use of beryllium for fusion reactor blankets Fusion Technology. ,vol. 13, pp. 143- 152 ,(1988) , 10.13182/FST88-A25091
Hongli Chen, Min Li, Zhongliang Lv, Guangming Zhou, Qianwen Liu, Shuai Wang, Xiaoliang Wang, Jie Zheng, Minyou Ye, Conceptual design and analysis of the helium cooled solid breeder blanket for CFETR Fusion Engineering and Design. ,vol. 96, pp. 89- 94 ,(2015) , 10.1016/J.FUSENGDES.2015.02.045
Jong Sung Park, Sungjin Kwon, Kihak Im, Keeman Kim, Thomas Brown, George Neilson, None, Pre-conceptual design study on K-DEMO ceramic breeder blanket Fusion Engineering and Design. ,vol. 100, pp. 159- 165 ,(2015) , 10.1016/J.FUSENGDES.2015.05.018
F. Scaffidi-Argentina, M. Dalle Donne, H. Werle, Critical assessment of beryllium pebbles response under neutron irradiation: Mechanical performance and tritium release Journal of Nuclear Materials. ,vol. 258, pp. 595- 600 ,(1998) , 10.1016/S0022-3115(98)00287-6
Yu. Igitkhanov, B. Bazylev, I. Landman, L. Boccaccini, Applicability of tungsten/EUROFER blanket module for the DEMO first wall Journal of Nuclear Materials. ,vol. 438, ,(2013) , 10.1016/J.JNUCMAT.2013.01.089
H Kawamura, H Takahashi, N Yoshida, V Shestakov, Y Ito, M Uchida, H Yamada, M Nakamichi, E Ishitsuka, Application of beryllium intermetallic compounds to neutron multiplier of fusion blanket Fusion Engineering and Design. ,vol. 61, pp. 391- 397 ,(2002) , 10.1016/S0920-3796(02)00106-0
Zheng Shan-liang, Wu Yi-can, Huang Qun-ying, Neutronics Optimization of Tritium Breeding Blanket for the FDS Plasma Science and Technology. ,vol. 4, pp. 1221- 1226 ,(2002) , 10.1088/1009-0630/4/2/007
H Kawamura, E Ishitsuka, K Tsuchiya, M Nakamichi, M Uchida, H Yamada, K Nakamura, H Ito, T Nakazawa, H Takahashi, S Tanaka, N Yoshida, S Kato, Y Ito, Development of advanced blanket materials for a solid breeder blanket of a fusion reactor Nuclear Fusion. ,vol. 43, pp. 675- 680 ,(2003) , 10.1088/0029-5515/43/8/306
U. Fischer, P. Pereslavtsev, S. Hermsmeyer, Neutronic design optimisation of modular HCPB blankets for fusion power reactors symposium on fusion technology. ,vol. 75, pp. 751- 757 ,(2005) , 10.1016/J.FUSENGDES.2005.06.222