-
1
-
-
0343391108
-
Basic study on characteristics of some important equilibrium fuel cycles of PWR
-
Technical Note
-
Waris A., Sekimoto H. Basic study on characteristics of some important equilibrium fuel cycles of PWR. Technical Note, Ann Nucl Energy. 28:2001;153-167.
-
(2001)
Ann Nucl Energy
, vol.28
, pp. 153-167
-
-
Waris, A.1
Sekimoto, H.2
-
2
-
-
0035254619
-
Proliferation hardening and power flattening of a thorium fusion breeder with triple mixed oxide fuel
-
Şahin S., Özceyhan V., Yapici H. Proliferation hardening and power flattening of a thorium fusion breeder with triple mixed oxide fuel. Ann Nucl Energy. 28:2001;204-223.
-
(2001)
Ann Nucl Energy
, vol.28
, pp. 204-223
-
-
Şahin, S.1
Özceyhan, V.2
Yapici, H.3
-
3
-
-
0004055594
-
-
International Atomic Energy Agency, Vienna
-
IAEA. Sustainable Development and Nuclear Power. International Atomic Energy Agency, Vienna, 1997. p. 8-10.
-
(1997)
Sustainable Development and Nuclear Power
, pp. 8-10
-
-
-
4
-
-
17044460297
-
Global energy scenarios and the potential role of fusion energy in the 21st century
-
Pease R.S. Global energy scenarios and the potential role of fusion energy in the 21st century. J Nucl Mater. 191-194:1992;7-14.
-
(1992)
J Nucl Mater
, vol.191-194
, pp. 7-14
-
-
Pease, R.S.1
-
5
-
-
0026897752
-
Fusion power from lunar resources
-
Kulcinki G. et al. Fusion power from lunar resources. Fusion Technol. 21:1992;2221-2229.
-
(1992)
Fusion Technol
, vol.21
, pp. 2221-2229
-
-
Kulcinki, G.1
-
6
-
-
0001242820
-
Waste disposal assessment of HYLIEE-II structure
-
Lee J.D. Waste disposal assessment of HYLIEE-II structure. Fusion Technol. 26(4):1994;174.
-
(1994)
Fusion Technol
, vol.26
, Issue.4
, pp. 174
-
-
Lee, J.D.1
-
9
-
-
0028484578
-
Basic requirements for a 1000-MW (electric) class tokamak fusion-fission hybrid reactor and its blanket concept
-
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.
-
(1994)
Fusion Technol
, vol.26
, pp. 27-45
-
-
Hatayama, A.1
Ogasawara, M.2
-
10
-
-
0032340192
-
Evaluation of the integral quantities for incident fusion source neutrons in infinite medium
-
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.
-
(1998)
Ann Nucl Energy
, vol.25
, Issue.18
, pp. 1503
-
-
Şahin, S.1
Yapci, H.2
Özceyhan, V.3
-
14
-
-
0033692734
-
Neutronic analysis of flux dispersion in a multi-layered, (D-T) driven hybrid blanket
-
TUBITAK
-
Ipek O. Neutronic analysis of flux dispersion in a multi-layered, (D-T) driven hybrid blanket. Turkish J Engng Environ Sci, TUBITAK. 24:2000;373-382.
-
(2000)
Turkish J Engng Environ Sci
, vol.24
, pp. 373-382
-
-
Ipek, O.1
-
15
-
-
0019623224
-
Recent progress in fusion-fission (hybrid) reactor design studies
-
Maniscalo J.A. et al. Recent progress in fusion-fission (hybrid) reactor design studies. Nucl Technol/Fusion. 1(4):1981;419.
-
(1981)
Nucl Technol/Fusion
, vol.1
, Issue.4
, pp. 419
-
-
Maniscalo, J.A.1
-
16
-
-
0003167471
-
Decrease of the LWR spent nuclear waste inventories and cumulative fissile fuel enrichment in hybrid reactor system, ICONE-8348
-
April 2-6, Baltimore, MD USA Copyright © 2000 ASME
-
Ipek O. Decrease of the LWR spent nuclear waste inventories and cumulative fissile fuel enrichment in hybrid reactor system, ICONE-8348. In: Proceeding of ICONE 8, 8th International Conference on Nuclear Engineering, April 2-6, Baltimore, MD USA Copyright © 2000 ASME, 2000.
-
(2000)
Proceeding of ICONE 8, 8th International Conference on Nuclear Engineering
-
-
Ipek, O.1
-
17
-
-
0035546628
-
Temperature distribution in nuclear fuel rod and variation of the neutronic performance parameters in (D-T) driven hybrid reactor system
-
Pergamon
-
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. Pergamon, Ann Nucl Energy. 2B:2001;1825-1850.
-
(2001)
Ann Nucl Energy
, vol.2 B
, pp. 1825-1850
-
-
Yapici, H.1
Ipek, O.2
Özceyhan, V.3
-
18
-
-
0002338364
-
Decrease of the CANDU spent nuclear waste inventories in fusion-fission (hybrid) reactors
-
Şahin S., Unalan U., Yapici H. Decrease of the CANDU spent nuclear waste inventories in fusion-fission (hybrid) reactors. Int J Energy Environ Econom. 4(1):1996;67-97.
-
(1996)
Int J Energy Environ Econom
, vol.4
, Issue.1
, pp. 67-97
-
-
Şahin, S.1
Unalan, U.2
Yapici, H.3
-
19
-
-
0022752722
-
Preliminarily design studies of a cylindrical experimental hybrid blanket with deuterium-tritium driven
-
Şahin S., Al-Kusayer T.A., Raoof M.A. Preliminarily design studies of a cylindrical experimental hybrid blanket with deuterium-tritium driven. Fusion Technol. 10:1986;84.
-
(1986)
Fusion Technol
, vol.10
, pp. 84
-
-
Şahin, S.1
Al-Kusayer, T.A.2
Raoof, M.A.3
-
20
-
-
0010728883
-
Potential of a fusion-fission hybrid reactor using for various coolants to breed fissile fuel for LWRs
-
Elsevier Pergamon, Received 23 July, accepted 27 October, UK
-
Yaipci H., Cürtüttü I., Özceyhan V., et al. Potential of a fusion-fission hybrid reactor using for various coolants to breed fissile fuel for LWRs. Ann Nucl Energy, Elsevier Pergamon, Received 23 July, accepted 27 October, UK, 1998.
-
(1998)
Ann Nucl Energy
-
-
Yaipci, H.1
Cürtüttü, I.2
Özceyhan, V.3
-
21
-
-
0021389767
-
Blanket design and calculated performance for the LOTUS fusion-fission hybrid test facility
-
Abdul K.S., Haldy P.A., Kumar A. Blanket design and calculated performance for the LOTUS fusion-fission hybrid test facility. Nucl Tech/Fusion. 5:1984;189.
-
(1984)
Nucl Tech/Fusion
, vol.5
, pp. 189
-
-
Abdul, K.S.1
Haldy, P.A.2
Kumar, A.3
-
23
-
-
0003245917
-
Mixed oxide fuel development
-
Riceland, Washington, American Nuclear Society, Lagange Park, September 13-17
-
Leggert R.D., Omeerg R.P. Mixed oxide fuel development. In: Proceedings of International Conference on Fast Breeder System: Experience Gained and Path To Economical Power Generation, Riceland, Washington, American Nuclear Society, Lagange Park, September 13-17, 1987.
-
(1987)
Proceedings of International Conference on Fast Breeder System: Experience Gained and Path to Economical Power Generation
-
-
Leggert, R.D.1
Omeerg, R.P.2
-
25
-
-
0024305136
-
Realization of a flat fission power density in a hybrid blanket over long operation periods
-
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.
-
(1989)
Fusion Technol
, vol.15
, pp. 37
-
-
Şahin, S.1
Erişen, A.2
Çebi, Y.3
-
26
-
-
0033241679
-
Pertinent integral data per fusion neutron in infinite medium
-
Şahin S., Yapici H., Özceyhan V. Pertinent integral data per fusion neutron in infinite medium. Arab J Sci Engng. 24(2A):1999;149-163.
-
(1999)
Arab J Sci Engng
, vol.24
, Issue.2 A
, pp. 149-163
-
-
Şahin, S.1
Yapici, H.2
Özceyhan, V.3
-
27
-
-
0001664844
-
The infinite medium Green's function in space and angle for the integro-differential form of the neutron transport equation with isotopic scattering
-
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. 27:2001;11-19.
-
(2001)
Ann Nucl Energy
, vol.27
, pp. 11-19
-
-
Cassell, J.S.1
Williams, M.M.R.2
-
28
-
-
0035400952
-
The infinite medium Green's function method for multi-group discrete ordinates transport problems in multi-layered slab geometry
-
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.
-
(2001)
Ann Nucl Energy
, vol.28
, pp. 1102-1114
-
-
Hong, S.G.1
Cho, N.Z.2
|