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Fusion Technology Volume 19, 1991 - Issue 3P2B
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ITER

Tritium Analysis for the US-ITER Solid Breeder Blanket

A. BadawiUniversity of California, Los Angeles, 6288 Boelter Hall, Los Angeles, CA 90024-1597
,
A.R. RaffrayUniversity of California, Los Angeles, 6288 Boelter Hall, Los Angeles, CA 90024-1597
,
A. YingUniversity of California, Los Angeles, 6288 Boelter Hall, Los Angeles, CA 90024-1597
&
M.A. AbdouUniversity of California, Los Angeles, 6288 Boelter Hall, Los Angeles, CA 90024-1597
Pages 1532-1537 | Published online: 10 Aug 2017

REFERENCES

  • U.S. Technical Report for the ITER Blanket/Shield, ITER-TN-BL-5-0-3, Garch., FRG, Jul.-Nov. 1990.
  • G. Federici, A.R. Raffray and M.A. Abdou, “MISTRAL: A Comprehensive Model for Tritium Transport in Lithium-Base Ceramics-Parts I and II”, Journal of Nuclear Materials, 173, 184–228, 1990.
  • M.C. Billone, personal communication, also “Input Parameters for Tritium Retention/Release Analysis of the US Blanket Concept for ITER”, ANL IntraLaboratory memo to Y. Gohar, April 30, 1990.
  • W.M. Jones, J. Chem. Phys., 17(11), 1062–1064, 1949.

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