Rejuvenation of the LWR spent fuel in (D-T) driven hybrid reactors

Fusion Engineering and Design

Volumn 38, Issue 4, 1998, Pages 393-416

  Unalan S ^a  

^a ERCIYES UNIVERSITY   (Turkey)

Author keywords

[No Author keywords available]

Indexed keywords

CARBON DIOXIDE; COOLANTS; DEUTERIUM; HELIUM; LIGHT WATER REACTORS; LITHIUM; LITHIUM COMPOUNDS; NEUTRON IRRADIATION; NEUTRON SOURCES; RADIATION EFFECTS; SPENT FUELS; TRITIUM;

DEUTERIUM TRITIUM HYBRID REACTORS; FLIBE;

NUCLEAR FUEL REPROCESSING;

EID: 0031998295     PISSN: 09203796     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0920-3796(97)00120-8     Document Type: Article

References (39)

1. 2 hybrid blanket driven by a (deuteriumtritium) source, Fus. Technol. 10 (1986) 1297.
2. S. Şahïn, T.A. Al-Kusayer, Nuclear waste actinides as fissile fuel in hybrid blankets, in: 6th Miami Int. Conf. Alternative Energy Sources, Proceedings of the Extended Abstracts, Miami Beach, Florida, 12-14 December 1983, pp. 350-353.
3. S. Şahïn, M. Al-Eshaikh, A numerical-graphical power flattening method for fast hybrid blankets, in: Proc. 4th Int. Conf. Emerging Nuclear Energy Systems, Madrid, Spain, June 30-July 4, 1986, p. 59.
4. S. Şahïn, M. Al-Eshaikh, Fission power flattening in hybrid reactors using mixed fuel, Fus. Technol. 12 (1987) 395.
5. S. Şahïn, A. ErÏşen, Y. Çeby, A fast hybrid blanket with flat fusion power over a long operational period, Trans. Am. Nucl. Soc. 54 (1987) 134.
6. S. Şahïn, A. Erïşen, Y. Çeby, Realization of a flat fission power density in a hybrid blanket over long operation periods, Fus. Technol. 15 (1989) 37.
7. S. Şahïn, Power flattening in a catalyzed deuterium-deuterium fusion driven hybrid blanket using nuclear waste actinides, Nucl. Technol. 92 (1990) 93.
8. E. Greenspan, Fusion-fission hybrid reactors, in: J. Lewins, M. Becker (Eds.), Advances in Nuclear Science and Technology, Vol. 16, Plenum, New York, 1984, p. 289.
9. R.W. Conn, F. Kantrowitz, W.F. Vogelsang, Hybrids for direct enrichment and self-protected fissile fuel production, Nucl. Technol. 49 (1980) 458.
10. A. Kumar, S. Şahïn, Deuterium-deuterium driven experimental hybrid blankets and their neutronic analysis, Fus. Technol. 6 (1984) 225.
11. 2 blanket with (D,D) driver, Atomkernenerg. Kerntechn. 47 (1985) 259-266.
12. S. Şahïn, T.A. Al-Kusayer, M. Abdul Raoof, Neutronic performance of (deuterium-deuterium) driven experimental thorium hybrid blankets, in: Trans. Am. Nucl. Soc. 1985 Annual Meeting, Vol. 49, Boston, June 1985, pp. 102-104.
13. S. Şahïn, Physics of the fusion-fission (hybrid) reactors, in: 8th Int. Summer College on Physics and Contemporary Needs, Islamabad, Pakistan, 23 July-11 August, 1983, Invited paper.
14. S. Şahïn, H. Yapici, Rejuvenation of CANDU spent fuel in a hybrid blanket, Trans. Am. Nucl. Soc. 59 (1989) 105.
15. S. Şahïn, H. Yapici, Investigation of the neutronic potential of moderated and fast (D,T) hybrid blankets for rejuvenation of CANDU spent fuel, Fus. Technol. 16 (1989) 331.
16. S. Şahïn, H. Yapici, E. Baltaciodlu, Heavy water reactor spent fuel regeneration with fusion neutrons, Trans. Am. Nucl. Soc. 60 (1989) 176.
17. S. Şahïn, E. Baltacioglu, H. Yapici, Potential of a catalyzed fusion driven hybrid reactor for the regeneration of CANDU spent fuel, Fus. Technol. 20 (1991) 26.
18. S. Şahïn, T.A. Al-Kusayer, M. Al-Samair, M.A. Raoof, Neutronic investigations of experimental AYMAN hybrid blankets, Trans. Am. Nucl. Soc. 47 (1984) 151.
19. S. Şahïn, T.A. Al-Kusayer, M.A. Raoof, Preliminary design studies of a cylindrical experimental hybrid blanket with deuterium-tritium driver, Fus. Technol. 10 (1986) 84.
20. S. Şahïn, E. Baltaciodlu, H. Yapici, Rejuvenation of LWR spent fuel in a catalyzed fusion hybrid blanket, Kerntechnik 59 (6) (1994) 243-277.
21. V.K. Rohatgi, T. Vijayan, Technical issues in fusion reactors - A review, Fus. Technol. 16 (1989) 287.
22. J.J. Duderstadt, L.J. Hamilton, Nuclear Reactor Analysis, Department of Nuclear Engineering, The University of Michigan, Michigan, 1975, p. 570.
23. K.S. Krane, Introductory Nuclear Physics, Oregon State University, Oregon, 1988, pp. 485-494.
24. J.D. Lee, Waste disposal assessment of HYLIFE-II structure, Fus. Technol. 26 (1994) 7.
25. W.W. Engle Jr., ANISN, A One-Dimensional Discrete Ordinates Transport Code with Anisotropic Scattering, K1693, Oak Ridge National Laboratory, 1970.
26. R.E. MacFarlane, TRANSX-2, A Code for Interfacing MATXS Cross-Section Libraries to Nuclear Transport Codes, LANL, December 1993.
27. T.A. Al-Kusayer, S. Şahïn, A. Drira, CLAW-IV, Coupled 30 Neutrons, 12 Gamma Ray Group Cross Sections with Retrieval Programs for Radiation Transport Calculations, Radiation Shielding Information Center, RSIC Newsletter, Oak Ridge National Laboratory, May, 1988, p. 4.
28. R.J. Barrett, R.E. MacFarlane, CLAW, Coupled 30 Neutrons, 12 Gamma-Ray Group Cross Sections for Neutron Transport calculations, LA-7808-MS, Los Alamos Scientific Laboratory, April, 1979.
29. I.I. Bondarenko (Ed.), Group Constants for Nuclear Reactor Calculations, Consultants Bureau, New York, 1964.
30. S. Şahïn, Comparison of diffusion and transport theory for fast reactor shielding calculations, Atomkernenergie, 22, 1973.
31. S. Şahïn, H. Yapici, S. Ünalan, ERDEMLI, A Computer Program to Process ANISN Output Data, Gazi University, Ankara, Turkey, 1991.
32. N.M. Greene, L.M. Petrie, XSDRN-PM/SCALE 4.1, A One-Dimensional Discrete-Ordinates Code For Transport Analysis, Oak Ridge National Laboratory, 1983.
33. L.M. Petrie, SCALE 4.2-27 Group Neutron Burnup Library Based on ENDF-B Version 4 Data With ENDF-B Version 5 Fission Products, Oak Ridge National Laboratory, 1993.
34. R.G. Jaeger et al., (Eds.), Engineering Compendium on Radiation Shielding, Vol. I, Shielding Fundamentals and Methods, Springer Verlag, Berlin, 1968.
35. W. Meyer, S.K. Loyalka, W.E. Nelson, R.W. Williams, The homemade nuclear bomb syndrome, Nuclear Safety 18 (1977) 427.
36. S. Şahïn, J. Ligou, The effect of the spontaneous fission of plutonium-240 on the energy release in a nuclear explosive, Nucl. Technol. 50 (1) (1980) 88.
37. M.M. El-Wakil, Nuclear Heat Transport, ISBN: 0-7002-2309-6, International Textbook Company, University of Wisconsin, UK, 1971.
38. R.W. Moir et al., HYLIFE-II, A molten-salt inertial fusion energy power plant design-final report, Fusion Technol. 25 (5) (1994).
39. S. Şahïn, et al., Radiation Damages in Liquid Protected First Wall Materials for IFE-Reactors, 12th Topical Meeting on The Technology of Fusion Energy, Reno, Nevada, 1027, (1196).