-
2
-
-
0004140799
-
-
Kucrhatov Institute of Atomic Energy, Moscow, UCRL-Trans-11288
-
L.V. Blinkin, M.V. Novikov, Optimal Symbiotic Molten Salt Fission-Fusion System, Kucrhatov Institute of Atomic Energy, 1 AE-2819, Moscow, UCRL-Trans-11288, 1977.
-
(1977)
Optimal Symbiotic Molten Salt Fission-Fusion System
, vol.1 AE-2819
-
-
Blinkin, L.V.1
Novikov, M.V.2
-
6
-
-
0003246553
-
Analysis of acceleration breeder concepts with LMFBR, GCFF and molten salt type blankets
-
Upton, January 18-19, New York
-
F.R. Mynat, Analysis of acceleration breeder concepts with LMFBR, GCFF and molten salt type blankets, in: Proceedings of the Information Management Accelerator Breeding, Upton, January 18-19, New York, 1977.
-
(1977)
Proceedings of the Information Management Accelerator Breeding
-
-
Mynat, F.R.1
-
9
-
-
0032115508
-
Fusion breeder with enhanced safeguarding capabilities against nuclear weapon proliferation
-
Şahin S., Yapici H., Baltacioglu E. Fusion breeder with enhanced safeguarding capabilities against nuclear weapon proliferation. Energy Conversion Manage. 39:1998;899.
-
(1998)
Energy Conversion Manage.
, vol.39
, pp. 899
-
-
Şahin, S.1
Yapici, H.2
Baltacioglu, E.3
-
10
-
-
0032734932
-
Neutronic analysis of a thorium fusion breeder with enhanced protection against nuclear weapon proliferation
-
Şahin S., Yapici H. Neutronic analysis of a thorium fusion breeder with enhanced protection against nuclear weapon proliferation. Ann. Nucl. Energy. 26:1999;13.
-
(1999)
Ann. Nucl. Energy
, vol.26
, pp. 13
-
-
Şahin, S.1
Yapici, H.2
-
11
-
-
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;203.
-
(2001)
Ann. Nucl. Energy
, vol.28
, pp. 203
-
-
Şahin, S.1
Özceyhan, V.2
Yapici, H.3
-
12
-
-
0035252623
-
Neutronic performance of proliferation hardened thorium fusion breeders
-
Şahin S., Yapici H., Şahin N. Neutronic performance of proliferation hardened thorium fusion breeders. Fusion Eng. Des. 54:2001;63.
-
(2001)
Fusion Eng. Des.
, vol.54
, pp. 63
-
-
Şahin, S.1
Yapici, H.2
Şahin, N.3
-
13
-
-
0023386614
-
Updated reference design of a liquid metal cooled tandem mirror fusion breeder
-
Berwald D.H., Whitley R.H., Garner J.K., et al. Updated reference design of a liquid metal cooled tandem mirror fusion breeder. Fusion Technol. 12:1987;30.
-
(1987)
Fusion Technol.
, vol.12
, pp. 30
-
-
Berwald, D.H.1
Whitley, R.H.2
Garner, J.K.3
-
16
-
-
0020762609
-
Investigation of neutronics of some (D, T)-driven experimental thorium hybrid blankets with actinide multipliers
-
Kumar A., Şahin S. Investigation of neutronics of some (D, T)-driven experimental thorium hybrid blankets with actinide multipliers. J. Fusion Energy. 3:1983;185.
-
(1983)
J. Fusion Energy
, vol.3
, pp. 185
-
-
Kumar, A.1
Şahin, S.2
-
17
-
-
0021522298
-
The fusion breeder - An early application of nuclear fusion
-
Maniscalco J.A., Berwald D.H., Moir R.W., Lee J.D., Teller E. The fusion breeder - an early application of nuclear fusion. Fusion Technol. 6:1984;584.
-
(1984)
Fusion Technol.
, vol.6
, pp. 584
-
-
Maniscalco, J.A.1
Berwald, D.H.2
Moir, R.W.3
Lee, J.D.4
Teller, E.5
-
18
-
-
0003314255
-
The fusion breeder
-
Washington, DC, March 4-5, Lawrence Livermore Laboratory, CA
-
R.W. Moir, The Fusion Breeder, National Science Foundation Policy Workshop, Washington, DC, March 4-5, Lawrence Livermore Laboratory, CA, UCRL-87290, 1982.
-
(1982)
National Science Foundation Policy Workshop
, vol.UCRL-87290
-
-
Moir, R.W.1
-
19
-
-
0003276651
-
Fissile fuel from fusion
-
Lawrence Livermore National Laboratory, CA
-
R.W. Moir, Fissile fuel from fusion, in: Energy and Technology Review, Lawrence Livermore National Laboratory, CA, UCRL-52000-85-1, 1985.
-
(1985)
Energy and Technology Review
, vol.UCRL-52000-85-1
-
-
Moir, R.W.1
-
20
-
-
0004049226
-
-
Lawrence Livermore National Laboratory, CA
-
R.W. Moir, J.D. Lee, F.J. Fulton, et al., Helium-cooled Molten Salt Fusion Breeder, Lawrence Livermore National Laboratory, CA, UCID-20153, 1984.
-
(1984)
Helium-cooled Molten Salt Fusion Breeder
, vol.UCID-20153
-
-
Moir, R.W.1
Lee, J.D.2
Fulton, F.J.3
-
21
-
-
0004036837
-
-
Lawrence Livermore National Laboratory, CA
-
R.W. Moir, J.D. Lee, W.S. Neef, et al., Feasibility Study of a Fission-suppressed Tokamak Fusion Breeder, Lawrence Livermore National Laboratory, CA, UCID-20154, 1984.
-
(1984)
Feasibility Study of a Fission-suppressed Tokamak Fusion Breeder
, vol.UCID-20154
-
-
Moir, R.W.1
Lee, J.D.2
Neef, W.S.3
-
22
-
-
0022092939
-
Helium-cooled, FLiBe breeder, beryllium multiplier blanket
-
Moir R.W., Lee J.D., Maninger R.C., et al. Helium-cooled, FLiBe breeder, beryllium multiplier blanket. Fusion Technol. 8:1985;133.
-
(1985)
Fusion Technol.
, vol.8
, pp. 133
-
-
Moir, R.W.1
Lee, J.D.2
Maninger, R.C.3
-
23
-
-
0022101495
-
Design of a helium-cooled molten salt fusion breeder, Part 2(A)
-
Moir R.W., Lee J.D., Fulton F.J., et al. Design of a helium-cooled molten salt fusion breeder, Part 2(A). Fusion Technol. 8:(1):1985;465.
-
(1985)
Fusion Technol.
, vol.8
, Issue.1
, pp. 465
-
-
Moir, R.W.1
Lee, J.D.2
Fulton, F.J.3
-
24
-
-
0022806348
-
Helium-cooled, FLiBe-breeder, beryllium-multiplier blanket for minimars
-
Moir R.W., Lee J.D. Helium-cooled, FLiBe-breeder, beryllium-multiplier blanket for minimars. Fusion Technol. 10:1986;619.
-
(1986)
Fusion Technol.
, vol.10
, pp. 619
-
-
Moir, R.W.1
Lee, J.D.2
-
25
-
-
0024650227
-
Power flattening in a hybrid blanket using nuclear waste actinides
-
Şahin S. Power flattening in a hybrid blanket using nuclear waste actinides. Kerntechnik. 53:1989;285.
-
(1989)
Kerntechnik
, vol.53
, pp. 285
-
-
Şahin, S.1
-
27
-
-
0001054348
-
Neutronic performance of (deuterium-deuterium)-driven experimental thorium hybrid blankets
-
Şahin S., Al-Kusayer T.A., Abdul-Raoof M. Neutronic performance of (deuterium-deuterium)-driven experimental thorium hybrid blankets. Trans. Am. Nucl. Soc. 1985 Annu. Meeting. 49:(1985):1985;102.
-
(1985)
Trans. Am. Nucl. Soc. 1985 Annu. Meeting
, vol.49
, Issue.1985
, pp. 102
-
-
Şahin, S.1
Al-Kusayer, T.A.2
Abdul-Raoof, M.3
-
28
-
-
0022752722
-
Preliminary design studies of a cylindrical experimental hybrid blanket with deuterium-tritium driver
-
Şahin S., Al-Kusayer T.A., Raoof M.A. Preliminary design studies of a cylindrical experimental hybrid blanket with deuterium-tritium driver. Fusion Technol. 10:1986;84.
-
(1986)
Fusion Technol.
, vol.10
, pp. 84
-
-
Şahin, S.1
Al-Kusayer, T.A.2
Raoof, M.A.3
-
29
-
-
0022806425
-
2 hybrid blanket driven by a (deuterium-tritium) source
-
2 hybrid blanket driven by a (deuterium-tritium) source. Fusion Technol. 10:1986;1297.
-
(1986)
Fusion Technol.
, vol.10
, pp. 1297
-
-
Şahin, S.1
Al-Kusayer, T.2
-
30
-
-
0024769818
-
Investigation of the neutronic potential of moderated and fast (D, T) hybrid blankets for rejuvenation of CANDU spent fuel
-
Şahin S., Yapici H. Investigation of the neutronic potential of moderated and fast (D, T) hybrid blankets for rejuvenation of CANDU spent fuel. Fusion Technol. 16:1989;331.
-
(1989)
Fusion Technol.
, vol.16
, pp. 331
-
-
Şahin, S.1
Yapici, H.2
-
31
-
-
0000404855
-
Rejuvenation of CANDU spent fuel in a hybrid blanket
-
Şahin S., Yapici H. Rejuvenation of CANDU spent fuel in a hybrid blanket. Trans. Am. Nucl. Soc. 59:1989;105.
-
(1989)
Trans. Am. Nucl. Soc.
, vol.59
, pp. 105
-
-
Şahin, S.1
Yapici, H.2
-
32
-
-
0001295105
-
A hybrid reactor design concept driven by cold (D, T) fusion neutrons and fueled with metallic thorium
-
Şahin S., Yapici H., Baltacioglu E., Al-Kusayer T.A. A hybrid reactor design concept driven by cold (D, T) fusion neutrons and fueled with metallic thorium. Int. J. Energy Environ. Econ. 1:1991;167.
-
(1991)
Int. J. Energy Environ. Econ.
, vol.1
, pp. 167
-
-
Şahin, S.1
Yapici, H.2
Baltacioglu, E.3
Al-Kusayer, T.A.4
-
33
-
-
0026202353
-
Potential of a catalysed fusion-driven hybrid reactor for the regeneration of CANDU spent fuel
-
Şahin S., Baltacioglu E., Yapici H. Potential of a catalysed fusion-driven hybrid reactor for the regeneration of CANDU spent fuel. Fusion Technol. 20:1991;26.
-
(1991)
Fusion Technol.
, vol.20
, pp. 26
-
-
Şahin, S.1
Baltacioglu, E.2
Yapici, H.3
-
34
-
-
0001953960
-
Rejuvenation of LWR spent fuel in a catalyzed fusion hybrid blanket
-
Şahin S., Yapici H., Baltacioglu E. Rejuvenation of LWR spent fuel in a catalyzed fusion hybrid blanket. Kerntechnik. 59:1994;270.
-
(1994)
Kerntechnik
, vol.59
, pp. 270
-
-
Şahin, S.1
Yapici, H.2
Baltacioglu, E.3
-
35
-
-
0032210824
-
Rejuvenation of LWR fuel in fusion blankets
-
Şahin S., Yapici H. Rejuvenation of LWR Fuel in fusion blankets. Ann. Nucl. Energy. 25:1998;1317.
-
(1998)
Ann. Nucl. Energy
, vol.25
, pp. 1317
-
-
Şahin, S.1
Yapici, H.2
-
36
-
-
0002170547
-
Spent mixed oxide fuel rejuvenation in fusion breeders
-
Şahin S., Yapici H., Bayrak M. Spent mixed oxide fuel rejuvenation in fusion breeders. Fusion Eng. Des. 47:1999;9.
-
(1999)
Fusion Eng. Des.
, vol.47
, pp. 9
-
-
Şahin, S.1
Yapici, H.2
Bayrak, M.3
-
37
-
-
0033149883
-
Potential of a fusion-fission hybrid reactor using various coolants to breeder fissile fuel for LWRs
-
Yapici H., Çürüttü I., Özceyhan V., Kirbiyik M. Potential of a fusion-fission hybrid reactor using various coolants to breeder fissile fuel for LWRs. Ann. Nucl. Energy. 26:1999;821.
-
(1999)
Ann. Nucl. Energy
, vol.26
, pp. 821
-
-
Yapici, H.1
Çürüttü, I.2
Özceyhan, V.3
Kirbiyik, M.4
-
39
-
-
0033737352
-
Neutronic analysis of a moderated (D, T) fusion-driven hybrid blanket
-
Yapici H., Akansu S.O., Özceyhan V. Neutronic analysis of a moderated (D, T) fusion-driven hybrid blanket. Ann. Nucl. Energy. 27:2000;1237.
-
(2000)
Ann. Nucl. Energy
, vol.27
, pp. 1237
-
-
Yapici, H.1
Akansu, S.O.2
Özceyhan, V.3
-
40
-
-
0033890157
-
Investigation of neutronic potential of a moderated (D-T) fusion-driven hybrid reactor fueled with thorium to breed fissile fuel for LWRs
-
Yapici H., Şahin N., Bayrak M. Investigation of neutronic potential of a moderated (D-T) fusion-driven hybrid reactor fueled with thorium to breed fissile fuel for LWRs. Energy Conversion Manage. 41:2000;435.
-
(2000)
Energy Conversion Manage.
, vol.41
, pp. 435
-
-
Yapici, H.1
Şahin, N.2
Bayrak, M.3
-
43
-
-
0003353219
-
Inertial fusion energy reactor design studies, prometheus-L & prometheus-H
-
MDC 92E0008/DOE/ER-54101
-
L.M. Waganer, et al., Inertial Fusion Energy Reactor Design Studies, Prometheus-L & Prometheus-H, McDonnel Douglas Company Report, MDC 92E0008/DOE/ER-54101, 1992.
-
(1992)
McDonnel Douglas Company Report
-
-
Waganer, L.M.1
-
47
-
-
0035333272
-
f/SiC-based fusion power cores
-
f/SiC-based fusion power cores. Fusion Eng. Des. 55:2001;55.
-
(2001)
Fusion Eng. Des.
, vol.55
, pp. 55
-
-
Raffray, A.R.1
Jones, R.2
Aiello, G.3
Billone, M.4
Giancarli, L.5
Golfier, H.6
Hasegawa, A.7
Katoh, Y.8
Kohyama, A.9
Nishio, S.10
Ricardi, B.11
Tillack, M.S.12
-
48
-
-
0003618343
-
-
Final report, UCLA-PPG-1323, UCLA, CA
-
F. Najmabadi, R. Conn, et al., The ARIES-I Tokamak reactor study, Final report, UCLA-PPG-1323, UCLA, CA, 1991.
-
(1991)
The ARIES-I Tokamak Reactor Study
-
-
Najmabadi, F.1
Conn, R.2
-
49
-
-
0003331601
-
The ARIES-II and ARIES-IV second stability Tokamak reactors study
-
La Grange Park, IL
-
F. Najmabadi, R. Conn, The Aries Team, The ARIES-II and ARIES-IV second stability Tokamak reactors study, in: Proceedings TMTFE-10, La Grange Park, IL, 1992.
-
(1992)
Proceedings TMTFE-10
-
-
Najmabadi, F.1
Conn, R.2
-
50
-
-
0003228607
-
Progress on the TAURO blanket system
-
H. Gofier, et al., Progress on the TAURO blanket system, in: Proceedings of the SOFT-21, 2000.
-
(2000)
Proceedings of the SOFT-21
-
-
Gofier, H.1
-
51
-
-
0032475097
-
Improved Tokamak concept focusing on easy maintenance
-
Nishio S., Ueda S., Aoki I., Kurihare R., et al. Improved Tokamak concept focusing on easy maintenance. Fusion Eng. Des. 41:1998;165.
-
(1998)
Fusion Eng. Des.
, vol.41
, pp. 165
-
-
Nishio, S.1
Ueda, S.2
Aoki, I.3
Kurihare, R.4
-
52
-
-
0000313079
-
The HTR with SiC technology
-
Schulten R. The HTR with SiC technology. Nucl. Eng. Des. 140:1993;261.
-
(1993)
Nucl. Eng. Des.
, vol.140
, pp. 261
-
-
Schulten, R.1
-
53
-
-
0034818737
-
Investigation of the use of ceramic materials in innovative light water reactor-fuel rod concepts
-
Lippmann W., Knorr J., Nöring R., Umbeit M. Investigation of the use of ceramic materials in innovative light water reactor-fuel rod concepts. Nucl. Eng. Des. 205:2001;13.
-
(2001)
Nucl. Eng. Des.
, vol.205
, pp. 13
-
-
Lippmann, W.1
Knorr, J.2
Nöring, R.3
Umbeit, M.4
|