Integral data for most important materials, namely lithium, beryllium, lead and uranium in infinite medium per fusion neutron

Energy Conversion and Management

Volumn 45, Issue 9-10, 2004, Pages 1443-1456

  Yapici, Hüseyin ^a   Özceyhan, Veysel ^a  

^a ERCIYES UNIVERSITY   (Turkey)

Author keywords

Fissile fuel breeding; Fusion neutron; Heat release; Infinite medium calculations; Neutron gain; Neutron multiplication

Indexed keywords

ENERGY UTILIZATION; HEAT LOSSES; LITHIUM; NATURAL RESOURCES; NEUTRON EMISSION; NUCLEAR ENERGY; NUCLEAR FUELS; NUCLEAR REACTORS; RADIOACTIVE WASTES; RENEWABLE ENERGY RESOURCES; SUPERCONDUCTING MAGNETS; URANIUM;

FISSILE FUEL BREEDING; FUSION NEUTRON; HEAT RELEASE; INFINITE MEDIUM CALCULATIONS; NEUTRON GAIN; NEUTRON MULTIPLICATION;

HIGH ENERGY PHYSICS;

EID: 0442327466     PISSN: 01968904     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.enconman.2003.09.008     Document Type: Article

References (30)

1. Waris A., Sekimoto H. Basic study on characteristics of some important equilibrium fuel cycles of PWR. Ann. Nucl. Energy. 28:2001;153-167. Technical Note.
2. IAEA, Sustainable development and nuclear power. International Atomic Energy Agency 1997, Vienna, p. 8-10.
3. Pease R.S. Global energy scenarios and the potential role of fusion energy in the 21st century. J. Nucl. Mater. (North-Holland). 7(14):1992;191-194.
4. Kulcinki G., et al. Fusion power from lunar resources. Fusion Technol. 1992;21.
5. Lee J.D. Waste disposal assessment of HYLIEE-II structure. Fusion Technol. 26(4):1994;174.
6. Fink JK, Chasanov MG, Leibowitz L. Properties for Reactor Safety Analysis. ANL-CEN-RSD-80-3 1981, Argonne National Laboratory Report.
7. Greenspan E. Fusion-fission hybrid reactor. Advances in nuclear science and technology. 1984;16 Plenum Press, New York.
8. Hatayama A., Ogasawara M., et al. Basic requirements for a 1000-MW(electric) class Tokamak fusion-fission hybrid reactor and its blanket concept. Fusion Technol. 26:1994;27-45.
9. Şahin S., Erişen A., Çebi Y. Realization of a flat fission power density in a hybrid blanket over long operation periods. Fusion Technol. 15:1989;37.
10. Şahin S., Ozceyhan V., Yapici H. Proliferation hardening and power flattening of a thorium fusion breeder with triple mixed oxide fuel. Ann. Nucl. Energy. 28(3):2001;203-223.
11. Yapici H., Ipek O., Özceyhan V. Temperature distribution in nuclear fuel rod and variation of the neutronic performance parameters in (D-T) driven hybrid reactor system. Ann. Nucl. Energy. 28(28):2001;1825-1850.
12. 2) and different coolants for various volume fraction. Ann. Nucl. Energy. 27:2000;279-294.
13. Yapici H., Cürtüttü I., Özceyhan V., Kirbiyik M. Potential of a fusion-fission hybrid reactor using for various coolants to breed fissile fuel for LWRs. Ann. Nucl. Energy. 26:1999;821-832.
14. 2. The Arabian J. Sci. Eng. 25(2A):2000;95-109.
15. Yapici H., Akansu S.O., Ozceyhan V. Neutronic analysis of a moderated (D,T) fusion driven hybrid blanket. Ann. Nucl. Energy. 27(13):2000;1237-1244.
16. Maniscalo J.A., et al. Recent progress in fusion-fission (hybrid) reactor design studies. Nucl. Technol./Fusion. 1(4):1981;419.
17. Şahin S., Unalan U., Yapici H. Decrease of the CANDU spent nuclear waste inventories in fusion-fission (hybrid) reactors. Int. J. Energy Environ. Econ. 4(1):1996;67-97.
18. Şahin S., Al-Kusayer T.A., Raoof M.A. Preliminarily design studies of a cylindrical experimental hybrid blanket with deuterium-tritium driver. Fusion Technol. 10:1986;84.
19. Abdul K.S., Haldy P.A., Kumar A. Blanket design and calculated performance for the LOTUS fusion-fission hybrid test facility. Nucl. Technol./Fusion. 5:1984;189.
20. Harker YD, et al. TFTR Lithium Blanket Module Program Final Design Report 1984;7/ EGG-PBS-6808.
21. Leggert R.D., Omeerg R.P. Mixed oxide fuel development. Proceedings of the International Conference on Fast Breeder System: Experience Gained and Path To Economical Power Generation. 1987;13-17 American Nuclear Society, Riceland, WA.
22. Teller E. Fusion, Magnetic Confinement. vol. 1, Part B:1981;Academic Press, London.
23. Şahin S., Yapici H., Özceyhan V. Pertinent integral data per fusion neutron in infinite medium. The Arabian J. Sci. Eng. 24(2A):1999;149.
24. Şahin S., Yapici H., Özceyhan V. Evaluation of the integral quantities for incident fusion source neutrons in infinite medium. Ann. Nucl. Energy. 25(18):1998;1503.
25. Cassell J.S., Williams M.M.R. The infinite medium Green's function in space and angle for the Integro-differential form of the neutron transport equation with isotopic scattering. Ann. Nucl. Energy. 27:2000;11-19.
26. Hong S.G., Cho N.Z. The infinite medium Green's function method for multi-group discrete ordinates transport problems in multi-layered slab geometry. Ann. Nucl. Energy. 28:2001;1102-1114.
27. Ipek O. Investigation of the infinite medium integral neutronic data for incident fusion Source. Ann. Nucl. Energy. 29:2002;1505-1523.
28. Ipek O. Analysis of the neutronic data in infinite medium using fusion neutron source for various material compositions. Energy Convers. Manage. 44:2003;439-458.
29. Yapici H., Ozceyhan V., Ipek O. Integral data for incident fusion source neutrons in infinite medium. Ann. Nucl. Energy. 29:2002;1471-1481.
30. Briesmeister JF. MCNP - A General Monte Carlo N-Particle Transport Code, Version 4B 1997; LA-12625-M, Los Alamos National Laboratory.