Neutronic investigation and activation calculation for CFETR HCCB blankets

• Published in: Plasma science & technology Vol. 19; no. 12; pp. 139 - 145
• Main Author: 徐淑玲;雷明准;刘素梅;陆坤;徐坤;裴坤
• Format: Journal Article
• Language: English
• Published: IOP Publishing 01.12.2017
• Subjects: neutron flux; neutron-induced damages; radioactivity behavior; tritium breeding ratio
• ISSN: 1009-0630; 1009-0630
• DOI: 10.1088/2058-6272/aa8bfe

The neutronic calculations and activation behavior of the proposed helium cooled ceramic breeder（HCCB） blanket were predicted for the Chinese Fusion Engineering Testing Reactor（CFETR） design model using the MCNP multi-particle transport code and its associated data library. The tritium self-sufficiency behavior of the HCCB blanket was assessed, addressing several important breeding-related arrangements inside the blankets. Two candidate first wall armor materials were considered to obtain a proper tritium breeding ratio（TBR）. Presentations of other neutronic characteristics, including neutron flux, neutron-induced damages in terms of the accumulated dpa and helium production were also conducted. Activation, decay heat levels and contact dose rates of the components were calculated to estimate the neutron-induced radioactivity and personnel safety. The results indicate that neutron radiation is efficiently attenuated and slowed down by components placed between the plasma and toroidal field coil.The dominant nuclides and corresponding isotopes in the structural steel were discussed. A radioactivity comparison between pure beryllium and beryllium with specific impurities was also performed. After a millennium cooling time, the decay heat of all the concerned components and materials is less than 1？×？10-4 k W, and most associated in-vessel components qualify for recycling by remote handling. The results demonstrate that acceptable hands-on recycling and operation still require a further long waiting period to allow the activated products to decay.