1. Preliminary design for a China ITER test blanket module
- Author
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Feng, K.M., Pan, C.H., Zhang, G.S., Luo, D.L., Zhou, Z.W., Yang, Y.W., Wang, X.Y., Hu, G., Yuan, T., Chen, Z., Wang, H.Y., Chen, C.A., Li, Z.X., Zhao, Z., and Li, Z.Q.
- Subjects
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NUCLEAR reactor design & construction , *CONSTRUCTION materials , *HELIUM , *TRITIUM - Abstract
Abstract: Preliminary design and analysis for China helium-cooled solid breeder (CH HC-SB) test blanket module (TBM) for testing in ITER device have been carried out recently. In this paper, the design description, the performance analysis and the related ancillary systems for CH TBM are given. The key features of the design are based upon the breeder-outside-tube (BOT) concept, on the use of solid breeder ceramic material, of helium as coolant and tritium purge gas, of ferrite–martensite steel as structural material and of beryllium as neutron multiplier. Results show that the proposed TBM concept has the advantages of higher tritium breeding ratio (TBR), simple structure design and engineering feasibility. [Copyright &y& Elsevier]
- Published
- 2006
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