-
1
-
-
0012064069
-
f/SiC composites
-
these proceedings, in press
-
f/SiC composites," these proceedings, Fusion Engineering and Design, in press.
-
Fusion Engineering and Design
-
-
Giancarli, L.1
Golfier, H.2
Nishio, S.3
Raffray, R.4
Wong, C.P.C.5
Yamada, R.6
-
2
-
-
0007609571
-
Conceptual design of advanced steady-state tokamak reactor
-
IAEA-CN-77/FTP2/14, Sorrento, Italy
-
S. Nishio, K. Ushigusa, S. Ueda, A. Polevoi, K. Tobita, R. Kurihara,et al., "Conceptual design of advanced steady-state tokamak reactor," Eighteenth IAEA Fusion Energy Conference, IAEA-CN-77/FTP2/14, Sorrento, Italy, 2000.
-
(2000)
Eighteenth IAEA Fusion Energy Conference
-
-
Nishio, S.1
Ushigusa, K.2
Ueda, S.3
Polevoi, A.4
Tobita, K.5
Kurihara, R.6
-
4
-
-
0012036367
-
Progress on the TAURO blanket system
-
these proceedings, in press
-
H. Golfier, G. Aiello, M. Futterer, L. Giancarli, A. Li-Puma, Y. Poitevin, J. Szczepanski, "Progress on the TAURO Blanket System," these proceedings, Fusion Engineering and Design, in press.
-
Fusion Engineering and Design
-
-
Golfier, H.1
Aiello, G.2
Futterer, M.3
Giancarli, L.4
Li-Puma, A.5
Poitevin, Y.6
Szczepanski, J.7
-
6
-
-
0035270364
-
ARIES-AT blanket and divertor
-
Raffray A.R., Tillack M.S., Wang X., El-Guebaly L., Sviatoslavsky I., Malang S. ARIES-AT blanket and divertor. Fusion Technology. 39:2001;429-433.
-
(2001)
Fusion Technology
, vol.39
, pp. 429-433
-
-
Raffray, A.R.1
Tillack, M.S.2
Wang, X.3
El-Guebaly, L.4
Sviatoslavsky, I.5
Malang, S.6
-
7
-
-
0029452142
-
Evaluation of US demo helium-cooled blanket options
-
September 30-October 5, Champaign, IL, Institute of Electrical and Electronics Engineers, Piscataway, NJ
-
C.P.C. Wong, B.W. McQuillan, R.W. Schleicher, E.T. Cheng and the ARIES Team, Evaluation of US demo helium-cooled blanket options, in: Proceedings of the 16th IEEE/NPSS Symposium on Fusion Engineering, September 30-October 5, 1995, Champaign, IL, vol. 2, Institute of Electrical and Electronics Engineers, Piscataway, NJ, 1996, p. 1145.
-
(1995)
Proceedings of the 16th IEEE/NPSS Symposium on Fusion Engineering
, vol.2
, pp. 1145
-
-
Wong, C.P.C.1
McQuillan, B.W.2
Schleicher, R.W.3
Cheng, E.T.4
-
8
-
-
0031642757
-
The low aspect ratio design concept-possibility of an acceptable fusion power system
-
October 6-10, San Diego, CA, Piscataway, NJ: Institute of Electrical and Electronics Engineers
-
Wong C.P.C., Cerbone R., Cheng E.T., Miller R.L. The low aspect ratio design concept-possibility of an acceptable fusion power system. Proceedings of the 17th IEEE/NPSS Symposium on Fusion Engineering, October 6-10, 1997, San Diego, CA. 2:1998;1051 Institute of Electrical and Electronics Engineers, Piscataway, NJ.
-
(1997)
Proceedings of the 17th IEEE/NPSS Symposium on Fusion Engineering
, vol.2
, pp. 1051
-
-
Wong, C.P.C.1
Cerbone, R.2
Cheng, E.T.3
Miller, R.L.4
-
9
-
-
0034315053
-
Helium-cooled refractory alloys first wall and blanket evaluation
-
Wong C.P.C., Nygren R.E., Baxi C.B., Fogarty P., Ghoniem N., Khater H., et al. Helium-cooled refractory alloys first wall and blanket evaluation. Fusion Engineering and Design. 49-50:2000;709-717.
-
(2000)
Fusion Engineering and Design
, vol.49-50
, pp. 709-717
-
-
Wong, C.P.C.1
Nygren, R.E.2
Baxi, C.B.3
Fogarty, P.4
Ghoniem, N.5
Khater, H.6
-
10
-
-
6644222462
-
Evaluation of the tungsten alloy vaporization lithium first wall and blanket concept
-
Wong C.P.C., Barleon L., Corradini M., Fogarty P., Ghoniem N., Majumdar S., et al. Evaluation of the tungsten alloy vaporization lithium first wall and blanket concept. Fusion Technology. 39:(Part 2):2001;815.
-
(2001)
Fusion Technology
, vol.39
, Issue.PART 2
, pp. 815
-
-
Wong, C.P.C.1
Barleon, L.2
Corradini, M.3
Fogarty, P.4
Ghoniem, N.5
Majumdar, S.6
-
11
-
-
0035270757
-
Comparison of the safety and environmental characteristics of refractory alloys under consideration in APEX
-
McCarthy K., Petti D.A., Khater K.Y. Comparison of the safety and environmental characteristics of refractory alloys under consideration in APEX. Fusion Technology. 39:2001;951-955.
-
(2001)
Fusion Technology
, vol.39
, pp. 951-955
-
-
McCarthy, K.1
Petti, D.A.2
Khater, K.Y.3
-
12
-
-
0034316667
-
Design and development of the Flibe blanket for helical-type fusion reactor FFHR
-
Sagara A., Yamanishi H., Imagawa S., Muroga T., Uda T., Noda T., et al. Design and development of the Flibe blanket for helical-type fusion reactor FFHR. Fusion Engineering and Design. 49-50:2000;661-666.
-
(2000)
Fusion Engineering and Design
, vol.49-50
, pp. 661-666
-
-
Sagara, A.1
Yamanishi, H.2
Imagawa, S.3
Muroga, T.4
Uda, T.5
Noda, T.6
-
13
-
-
0035270770
-
Heat transfer enhancement for a molten salt Flibe channel
-
S. Chiba, et al., Heat transfer enhancement for a molten salt Flibe channel, Fusion Technology, 39 (2001) 779-783.
-
(2001)
Fusion Technology
, vol.39
, pp. 779-783
-
-
Chiba, S.1
-
14
-
-
0035270662
-
Flibe assessment
-
Sze D.K., McCarthy K., Sawan M., Tillack M., Ying A., Zinkle S. Flibe assessment. Fusion Technology. 39:(Part 2):2001;747.
-
(2001)
Fusion Technology
, vol.39
, Issue.PART 2
, pp. 747
-
-
Sze, D.K.1
McCarthy, K.2
Sawan, M.3
Tillack, M.4
Ying, A.5
Zinkle, S.6
-
15
-
-
0034316858
-
Operating temperature windows for fusion reactor structural materials
-
Zinkle S.J., Ghoniem N.M. Operating temperature windows for fusion reactor structural materials. Fusion Engineering Design. 51-51:2000;55-71.
-
(2000)
Fusion Engineering Design
, vol.51
, Issue.51
, pp. 55-71
-
-
Zinkle, S.J.1
Ghoniem, N.M.2
-
17
-
-
0029767110
-
Results of an international study on a high-volume plasma-based neutron source for fusion blanket development
-
Abdou M., Berk S., Ying A., Peng Y.K.M., Sharafat S., Galambos J., Hollenberg G., et al. Results of an international study on a high-volume plasma-based neutron source for fusion blanket development. Fusion Technology. 29:1996;1-57.
-
(1996)
Fusion Technology
, vol.29
, pp. 1-57
-
-
Abdou, M.1
Berk, S.2
Ying, A.3
Peng, Y.K.M.4
Sharafat, S.5
Galambos, J.6
Hollenberg, G.7
-
18
-
-
0003233639
-
Progress on SiC/SiC structures joining techniques and modeling for design analysis
-
Marseille, France, Saint Paul Lez Durance: Association EURATOM-CEA
-
Gasse A., Aiello G., Giancarli L., Le Marois G., Salavy J.F., Szczepanski J. Progress on SiC/SiC structures joining techniques and modeling for design analysis. Proceedings of the 20th Symposium on Fusion Technology, 1998, Marseille, France. 1998;1235-1238 Association EURATOM-CEA, Saint Paul Lez Durance.
-
(1998)
Proceedings of the 20th Symposium on Fusion Technology, 1998
, pp. 1235-1238
-
-
Gasse, A.1
Aiello, G.2
Giancarli, L.3
Le Marois, G.4
Salavy, J.F.5
Szczepanski, J.6
-
19
-
-
0032178769
-
Fabrication of a 1200 kg ingot of V-4Cr-4Ti alloy for the DIII-D radiative divertor program
-
Johnson W.R., Smith J.P. Fabrication of a 1200 kg ingot of V-4Cr-4Ti alloy for the DIII-D radiative divertor program. Journal of Nuclear Material. 258-263:1998;1425-1430.
-
(1998)
Journal of Nuclear Material
, vol.258-263
, pp. 1425-1430
-
-
Johnson, W.R.1
Smith, J.P.2
-
20
-
-
0035494881
-
ITER FEAT - The future international burning plasma experiment overview
-
Aymar R. ITER FEAT - the future international burning plasma experiment overview. Nuclear Fusion. 41:(10):2001;1301.
-
(2001)
Nuclear Fusion
, vol.41
, Issue.10
, pp. 1301
-
-
Aymar, R.1
-
21
-
-
0035269330
-
Critical technology issues and development requirements for a fusion development facility
-
Wesley J., Stambaugh R.D. Critical technology issues and development requirements for a fusion development facility. Fusion Technology. 39:(10):2001;473.
-
(2001)
Fusion Technology
, vol.39
, Issue.10
, pp. 473
-
-
Wesley, J.1
Stambaugh, R.D.2
-
22
-
-
0034545511
-
Neutron wall loading of tokamak reactor
-
Wong C.P.C. Neutron wall loading of tokamak reactor. Journal of Nuclear Material. 283-287:2000;588-592.
-
(2000)
Journal of Nuclear Material
, vol.283-287
, pp. 588-592
-
-
Wong, C.P.C.1
-
23
-
-
0035270065
-
Activation, decay heat, and waste disposal analysis for the ARIES-AT power plant
-
D. Henderson, L. El-Guebaly, P. Wilson, A. Abdou, and the AIRES Team,Activation, decay heat, and waste disposal analysis for the ARIES-AT power plant, Fusion Technology 39 (2001) 444-448.
-
(2001)
Fusion Technology
, vol.39
, pp. 444-448
-
-
Henderson, D.1
El-Guebaly, L.2
Wilson, P.3
Abdou, A.4
-
24
-
-
0034317275
-
Application of SEAFP waste recycling and clearance strategies to ITER
-
Cheng E.T. Application of SEAFP waste recycling and clearance strategies to ITER. Fusion Engineering and Design. 51-52:2000;485-491.
-
(2000)
Fusion Engineering and Design
, vol.51-52
, pp. 485-491
-
-
Cheng, E.T.1
-
25
-
-
0035270036
-
An assessment of the Brayton cycle for high performance power plants
-
Schleicher R., et al. An assessment of the Brayton cycle for high performance power plants. Fusion Technology. 39:(Part 2):2001;823.
-
(2001)
Fusion Technology
, vol.39
, Issue.PART 2
, pp. 823
-
-
Schleicher, R.1
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