Improvement of neutronic performance of a catalyzed (D,D) driven hybrid reactor using various moderators and coolants materials

Arabian Journal for Science and Engineering

Volumn 23, Issue 1A, 1998, Pages 35-46

  Ünalan, Sebahattin ^a   Yapici, Hüseyin ^a   Özceyhan, Veysel ^a   Çürüttü, Ilyas ^b  

^a ERCIYES UNIVERSITY   (Turkey)

^b MUSTAFA KEMAL UNIVERSITY   (Turkey)

Author keywords

[No Author keywords available]

Indexed keywords

EID: 0032398605     PISSN: 2193567X     EISSN: 21914281     Source Type: Journal    
DOI: None     Document Type: Article

References (19)

1. J.A. Maniscalco et al., "Recent Progress in Fusion-Fission (Hybrid) Reactor Design Studies", Nuclear Technology/Fusion, 1(4) (1981), p. 419.
2. S. Şahin, T.A. Al-Kusayer, M. Al-Samair, and M.A. Raoof, "Neutronic Investigations of Experimental AYMAN Hybrid Blankets", Trans. Am. Nucl. Soc., 47 (1984), p. 151.
3. S. Şahin, S. Ünalan, and H. Yapici, "Decrease of the CANDU Spent Nuclear Waste Inventories in Fusion-Fission (Hybrid) Reactors", International Journal of Energy Environment Economics, 4(1) (1996), pp. 67-97.
4. S. Şahin and H. Yapici, "Rejuvenation of CANDU Spent Fuel in a Hybrid Blanket", Trans. Am. Nucl. Soc., 59 (1989), p. 105.
5. S. Şahin and H. Yapici, "Investigation of the Neutronic Potential of Moderated and Fast (D,T) Hybrid Blankets for Rejuvenation of CANDU Spent Fuel", Fusion Technol., 16 (1989), p. 331.
6. S. Şahin, H. Yapici, and E. Baltacioǧlu, "Heavy Water Reactor Spent Fuel Regeneration with Fusion Neutrons", Trans. Am. Nucl. Soc., 60 (1989), p. 176.
7. S. Şahin, T.A. Al-Kusayer, and M.A. Raoof, "Preliminary Design Studies of a Cylindrical Experimental Hybrid Blanket with Deuterium-Tritium Driver", Fusion Technol., 10 (1986), p. 84.
8. S. Şahin, H. Yapici, and E. Baltacioǧlu, "Rejuvenation of LWR Spent Fuel in a Catalyzed Fusion Hybrid Blanket", Kerntechnik, 59 (1994), p. 270.
9. J.D. Lee, "Waste Disposal Assessment of HYLIFE-II Structure", Fusion Technol., 26 (1994), p. 74.
10. W.W. Engle, Jr., ANISN, A One-Dimensional Discrete Ordinates Transport Code with Anisotropic Scattering. K1693, Oak Ridge National Laboratory, 1970.
11. R.E. MacFarlane, TRANSX-2, A Code for Interfacing MATXS Cross-Section Libraries to Nuclear Transport Codes. LANL, December 1993.
12. T.A. Al-Kusayer, S. Şahin, and 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.
13. R.J. Barrett and 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.
14. I.I. Bondarenko (Ed.), Group Constants for Nuclear Reactor Calculations. New York: Consultants Bureau, 1964.
15. S. Şahin, H. Yapici, S. Ünalan, ERDEMLI, A Computer Program to Process ANISN Output Data. Ankara, Turkey: Gazi University, 1991.
16. S. Şahin, R. Moir, S. Ünalan, "Neutronic Investigation of Inertial Fusion Energy Blankets For Hylife-II and Magneto-hydrodynamic Applications", Fusion Technol., 25(4) (1994), p. 388-397.
17. S. Şahin and M. Al-Eshaikh, "Fission Power Flattening in Hybrid Blankets Using Mixed Fuel", Fusion Technol., 12 (1987), p. 395.
18. S. Şahin, A. Erişen, and Y. Çebi, "A Fast Hybrid Blanket with Flat Fusion Power over a Long Operational Period", Trans. Am. Nucl. Soc., 54 (1987), p. 134.
19. S. Şahin, A. Erişen, and Y. Çebi, "Realization of a Flat Fission Power Density in a Hybrid Blanket over Long Operating Periods", Fusion Technol., 15 (1989), p. 37.