Materials integration issues for high performance fusion power systems

Journal of Nuclear Materials

Volumn 258-263, Issue PART 1 A, 1998, Pages 65-73

  Smith, D L ^a   Billone, M C ^a   Majumdar, S ^a   Mattas, R F ^a   Sze, D K ^a  

^a ARGONNE NATIONAL LABORATORY   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

ACCIDENT PREVENTION; BREEDING BLANKETS; COOLANTS; COST EFFECTIVENESS; ENVIRONMENTAL PROTECTION; HYDROGEN; MATERIALS SCIENCE; NEUTRONS; TRITIUM;

FUSION MATERIALS; PLASMA FACING MATERIALS;

FUSION REACTORS;

EID: 0032178502     PISSN: 00223115     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0022-3115(98)00355-9     Document Type: Article

References (30)

1. D.L. Smith et al., Fusion Technol. 8 (1) (1985) 10.
2. L. Giancarli et al., Fusion Eng. Design 27A (1995) 337.
3. M. Dalle Donne, Development of EU Helium-cooled pebble bed blanket, Fusion Eng. Design (in press).
4. L. Giancarli et al., Development of EU water-cooled Pb-17Li blanket, Fusion Eng. Design (in press).
5. H. Takatsu et al., Development of ceramic breeder blankets in Japan, Fusion Eng. Design (in press).
6. I.R. Kirillov et al., Liquid Lithium self-cooled breeding blanket design, Fusion Eng. Design (in press).
7. D.K. Sze et al., The ARIES-RS power core-recent developments in Li/V design, Fusion Eng. Design (in press).
8. R.F. Mattas, M.C. Billone, J. Nucl. Mater. 233-237 (1996) 72.
9. D.A. Petti et al., J. Nucl. Mater. 233-237 (1996) 37.
10. M. Saltmarsh et al., Final Report of the Advanced Technologies/Materials Working Group (unpublished).
11. L.L. Snead et al., J. Nucl. Mater. 233-237 (1996) 26.
12. S. Majumadar, P. Smith, Treatment of irradiation effects in structural design criteria for fusion reactors, Fusion Eng. Design (in press).
13. A. Kohyma et al., J. Nucl. Mater. 212-215 (1994) 684.
14. D.L. Smith et al., Progress in data from the vanadium alloy development for fusion applications, Fusion Eng. Design (in press).
15. D.K. Sze, personal communication (1997).
16. T.Q. Hua, Y. Gohar, Fusion Eng. Design 27 (1995) 696.
17. C.C. Baker et al., Tokomak Power Systems Study, ANL/ FPP-085-2, Argonne National Laboratory (1985).
18. J.H. Park, T.F. Kassner, J. Nucl. Mater. 233-237 (1996) 476.
19. H. Attaya et al., J. Nucl. Mater. 122&123 (1984) 96.
20. D.K. Sze et al., Tritium processing system for the ITER Li/ V blanket test module, Fusion Eng. Design (in press).
21. J.H. Park et al., Fusion Materials Semi-Annual Progress Report, December 31, 1995, DOE/ER-0313/16 (1994) p. 50.
22. J.H. DeVan et al., Fusion Materials Semi-annual Progress Report, March 31, 1994, DOE/ER-0313/16 (1994) p. 240.
23. M.C. Billone, J. Nucl. Mater. 233-237 (1996) 1462.
24. N. Roux et al., Fusion Eng. Design, 27 (1995) 154.
25. J.G. van der Laan et al., Analysis of performance data from ceramic breeder irradiation experiments, Fusion Eng. Design (in press).
26. T. Terai et al., Research and development of ceramic coatings for fusion reactor liquid blankets, Fusion Eng. Design (in press).
27. A. Perujo et al., The development of tritium permeation barriers for blankets, Fusion Eng. Design (in press).
28. H. Attaya, D. Smith, J. Nucl. Mater. 191-194 (1992) 1464.
29. D. Smith et al., Fusion Eng. Design, 27C (1995) 399.
30. G.J. Butterworth et al., J. Nucl. Mater. 212-215 (1994) 667.