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ITER Nuclear Design

Water-Cooled Solid-Breeder Blanket Concept for ITERFootnotea

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Pages 864-870 | Published online: 10 Aug 2017

REFERENCES

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  • Y. GOHAR, “Nuclear Data Needs for Fusion Reactors,” Proceedings of the International Conference on Nuclear Data for Basic and Applied Science, Santa Fe, New Mexico, USA, Gordon and Breach science publishers, pp. 15–42 (1985).
  • R. D. O’DELL, F. W. BRINKLEY, D. R. MARR, “User’s Manual for ONEDANT: A Code Package for One-Dimensional Diffusion-Accelerated, Neutral-Particle Transport,” LA-9l84-M, Los Alamos National Laboratory Report (1982).
  • R. W. ROUSSIN et al., “The CTR Processes Multigroup Cross Section Library for Neutronics Studies,” ORNL/RSC-37, Oak Ridge National Laboratory (1979).
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  • Y. GOHAR et al., “Low Technology High Tritium Breeder Blanket Concept,” Fusion Technology ( to be published).
  • Y. GOHAR et al., “First Wall/Blanket/Shield Design and Optimization System,” paper presented at the International Symposium on Fusion Nuclear Technology, Tokyo, Japan, (1988).
  • U. S. ITER Nuclear Group, “ITER Shield and Blanket Work Package Report,” ANL/FPP/88-1, Argonne National Laboratory (1988).
  • P. M. S. JONES and R. GIBSON, “Hydrogen in Beryllium,” J. Nucl. Mater., 21 353 (1967).
  • W. R. WAMPLES, “Retention and Thermal Release of Deuterium Implanted in Beryllium,” J. Nucl. Mater., 122&123, 1598 (1984).

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