Published Work:
|1-10||11-20||21-30|31-40|41-50|51-60|61-70|71-80|81-90|91-100|
|101-110|111-120|121-130|131-140|141-150|151-160|161-170|171-180|
 180.
Sze, D. K.;Herring, S.;Sawan, M.;ARIES Team, "Tritium production,
management and its impact on safety for a D-3He fusion reactor",
ANS 4th Topical Meeting on Tritium Technology in Fission, Fusion,
and Isotopic Applications, Albuquerque, NM, Sep 30 - Oct 4, 1991 ANL/CP-72699.
179.
Sze, D. K.;Herring, S.;Sawan, M.;ARIES Team, "Tritium production,
management and its impact on safety for a D-He3 fusion reactor",
ANS;Canadian Nuclear Society;European Nuclear Society;Japan Nuclear
Society 4th Topical Meeting on Tritium Technology in Fission, Fusion,
and Isotopic Applications, Albuquerque, NM, Sep 29 - Oct 4, 1991.
178.
Sze, D.K.;Hua, T. Q.;Dagher, M. A.;Waganer, L. M.;Abdou, M. A.,
"Tritium processing system for the ITER Li/V blanket test module", 4th
International Symposium on Fusion Nuclear Technology, Meiji Kinenkan
Tokyo, Japan, Apr 6-11, 1997 ANL/TD/CP-93186.
177.
Sze, D.K.;Hua, T. Q.;Dagher, M. A.;Waganer, L. M.;Abdou, M. A.,
"Tritium processing for the ITER Li/V blanket test module", 4th International
Symposium on Fusion Nuclear Technology, Tokyo, Japan, Apr 6-11, 1997.
176.
Sze, D.K., "Tritium issue on IFE", Aries Project Meeting, Madison,
WI, Jun 19-21, 2000.
175.
Sze, D.K., "The Tritium/Chemistry Facility, its capability and role
in the US-Monbusho collaboration", Japan Monbusho - USDOE Collaboration in
Planning Workshop, Tokyo, Japan, Feb 23-25, 2000.
174.
Sze, D. K.;Mattas, R. F.;Tanaka, S., "The progress and issues of tritium
recovery from lithium", Joint Research Centre 6th International Conference
on Fusion Reactor Materials, Stresa, Italy, Sep 27 - Oct 1, 1993.
173.
Sze, D.K., "The development of Sn-Li coolant/breeding material for
APEX/ALPS applications", 5th International Symposium on Fusion Nuclear
Technology, Rome, Italy, Sep 19-24, 1999 ANL/TD/CP-98298.
172.
Sze, D.K., "The development of Sn-Li coolant/breeding material for
APEX/ALPS applications", Italian Agency for New Technologies, Energy and
Environment 5th International Symposium on Fusion Nuclear Technology, Rome,
Italy, Sep 19-24, 1999.
171.
Sze, D.K.;Tillack, M.;Pulsifer, J.;El-Guebaly, L.;Malang, S.,
"The ARIES-ST blanket design", Annual Meeting of the American Nuclear
Society, Nashville, TN, Jun 7-12, 1998.
170.
Sze, D.K.;Billone, M. C.;Hua, T. Q.;Tillack, M.;Najmabadi, F.;Wang,
X.;Malang, S.;El-Guebaly, L. A.;Sviatoslavsky, I. N.;Blanchard, J. P.;
Crowell, J. A.;Khater, H. Y.;Mogahed, E. A.;Waganer, L. M.;Lee, D.;Cole, D.,
"The ARIES-RS power core-recent development in Li/V designs", 4th International
Symposium on Fusion Nuclear Technology, Tokyo, Japan, Apr 6-11, 1997
ANL/TD/CP-91083.
169.
Sze, D.K.;Billone, M. C.;Hua, T. Q.;Tillack, M.;Najmabadi, F.;Wang,
X.;Malang, S.;El-Guebaly, L. A.;Sviatoslavsky, I. N.;Blanchard, J. P.;
Crowell, J. A.;Khater, H. Y.;Mogahed, E. A.;Waganer, L. M.;Lee, D.;Cole, D.,
"The ARIES-RS power core-recent development in Li/V designs", 4th International
Symposium on Fusion Technology, Tokyo, Japan, Apr 6-11, 1997.
168.
Sze, D.K.;Billone, M. C.;Hua, T. Q., "The ARIES-RS power core-recent
development in Li/V designs", 4th International Symposium on Fusion Nuclear
Technology, Tokyo, Japan, Apr 6-11, 1997.
167.
Sze, D.K.;Mattas, R.;Wang, Z.;Cheng, E. T.;Sawan, M.;Zinkle, S.;
McCarthy, K. A., "Sn-Li, a new coolant/breeding material for fusion
applications", ICFRM (9th International Conference on Fusion Reactor
Materials), Colorado Springs, CO, Oct 10-15, 1999 ANL/TD/CP-98464.
166.
Sze, D.K.;Brooks, J.;Rognlien, T.;Smolentsev, S., "Sn-CLIFF and
temperature window", APEX Meeting, Albuquerque, NM, Nov 15-17, 2000.
165.
Sze, D.K., "Recent designs for advanced fusion reactor blankets",
11th Topical Meeting on the Technology of Fusion Technology, New Orleans,
LA, Jun 19-23, 1994.
164.
Sze, D.K., "Recent designs for advanced fusion reactor blankets",
Fusion Technol., 26(3): 1061-68, Nov. 1994 11th Topical Meeting on the
Technology of Fusion Technology, New Orleans, LA, Jun 19-23, 1994 ANL/TD/CP-82097.
163.
Sze, D.K.;Sagara, A., "Program to develop flibe for fusion applications",
Italian Agency for New Technologies, Energy and Environment 5th
International Symposium on Fusion Nuclear Technology, Rome, Italy, Sep 19-24, 1999.
162.
Sze, D. K.;Finn, P. A.;Anderson, J.;Bartlit, J.;Sherman, R.,
"Possible design modifications of ITER fuel cycle", ANS;DOE;Argonne
National Lab. 9th Topical Meeting on Technology of Fusion Energy,
Oak Brook, IL, Oct 7-11, 1990.
161.
Mattas, R.;Sze, D. K., "Overview of design activities for Li/V blankets",
International Workshop on Liquid Metal Blanket Experimental Activities,
Paris, France, Sep 16-18, 1997.
160.
Sze, D. K.;Mattas, R. F., "Overview of design activities for Li/V blankets",
International Workshop on Liquid Metal Blanket Experimental Activities, Paris,
France, Sep 16-18, 1997 ANL/TD/CP-93894.
159.
Sze, D. K.;Sviatoslavsky, I.;Sawan, M.;Gierszewski, P.;Hollies, R.;
Sharafat, S.;Herring, S.;ARIES Team, "Organic coolant for ARIES-III",
ASME 2nd International Sympsoium on Fusion Nuclear Technology, Karlsruhe,
Germany, Jun 2-7, 1991 ANL/CP-71820.
158.
Sze, D. K.;Sviatoslavsky, I.;Sawan, M.;Gierszewski, P.;Hollies, R.;
Sharafat, S.;Herring, S.;ARIES Team, "Organic coolant for ARIES-III",
ASME 2nd International Sympsoium on Fusion Nuclear Technology, Karlsruhe,
Germany, Jun 2-7, 1991.
157.
Sze, D.K., "Opinions on key liquid wall issues", APEX Project
Meeting, Los Angeles, CA, Nov 8-11, 1999.
156.
Sze, D. K.;Mattas, R. F.;Hull, A. B.;Picologlou, B. F.;Smith, D. L.,
"MHD considerations for a self-cooled liquid lithium blanket", DOE;ANS
10th Topical Meeting on the Technology of Fusion Energy, Boston, MA,
Jun 7-12, 1992 ANL/CP-75362.
155.
Sze, D.K.;Gomes, I.;Gohar, Y.;Waganer, l.;McCarthy, K.;Abdou, M.;
Ying, A., "Lithium testing module for ITER with low lithium inventory",
Annual Meeting of the American Nuclear Society, Nashville, TN, Jun 7-12, 1998.
154.
Sze, D.K.;Cheng, E.;Gierszewski, P., "ITER EPP Tritium supply
and breeding improvement", 17th IEEE/NPSS Symposium on Fusion Engineering
(SOFE '97), San Diego, CA, Oct 6-10, 1997.
153.
Sze, D. K.;Sawan, M. E.;Cheng, E. T., "Impact of transmutations in fusion
environment on Flibe chemistry", Fusion Technol., 39(2, pt. 2): 789-92,
Mar. 2001 ANS 14th TOFE Meeting, Park City, Utah, Oct 16-19, 2000 ANL/TD/CP-103407.
152.
Sze, D. K., "Hydrogen permeability in different materials",
ARIES Project Meeting, Livermore, CA, Mar 8-9, 2001.
151.
Finn, P. A.;Sze, D. K., "Helium processing for deuterium/helium
burns in ITER's physics phase", Fusion Eng. Des., 18: 15-18, 1991
ASME 2nd International Symposium on Fusion Nuclear Technology,
Karlsruhe, Germany, Jun 2-7, 1991 ANL/CP-73018.
150.
Finn, P. A.;Sze, D. K., "Helium processing for D/{sup 3}HE burns in
ITER's physics phase", ASME 2nd International Symposium on Fusion
Nuclear Technology, Karlsruhe, Germany, Jun 2-7, 1991.
149.
Finn, P. A.;Sze, D. K., "Helium processing for D/{sup 3}HE burns in
ITER's physics phase", ASME 2nd International Symposium on Fusion
Nuclear Technology, Karlsruhe, Germany, Jun 2-7, 1991.
148.
Sze, D.K.;Bartlit, J.;Sherman, R.;Fisher, P.;Gierszewski, P.;
Ho, S. K.;Busigin, A., "Fuel cycle assessment for a D-He{sub 3} reactor",
2nd International Symposium on Fusion Nuclear Technology, Karlsruhe,
Germany, Jun 2-7, 1991.
147.
Sze, D.K., "Flibe usage in MFE and IFE", Lawrence Livermore National
Laboratory, Livermore, CA, Nov. 30, 1999.
146.
Sze, D.K., "Flibe tritium/chemistry experiment," Jupiter-II Workshop,
Washington, DC, Jun 1-2, 2000.
145.
Clemmer, R. G.;Sze, D. K.;Blackburn, P. E.;VanDeventer, E.;Maroni, V. A.,
"Flibe chemistry studies", ANS;DOE;Argonne National Lab. 9th Topical
Meeting on the Technology of Fusion Energy, Oak Brook, IL, Oct 7-11, 1990.
144.
Clemmer, R. G.;Sze, D. K.;Blackburn, P. E.;VanDeventer, E.;Maroni, V. A.,
"Flibe chemistry studies", Fusion Technol., 19(3, PtPt.2B): 1612-18,
May 1991 ANS;DOE;Argonne National Lab. 9th Topical Meeting on the
Technology of Fusion Energy, Oak Brook, IL, Oct 7-11, 1990.
143.
Sze, D.K. Japan Monbusho, "Flibe chemistry control", USDOE
Collaboration in Planning Workshop, Tokyo, Japan, Feb 23-25, 2000.
142.
Sze, D. K.;McCarthy, K.;Sawan, M.;Tillack, M.;Ying, A.;Zinkle, S.,
"Flibe assessments", Fusion Technol., 39(2, pt. 2): 746-52, Mar. 2001
ANS 14th TOBE Meeting, Park City, Utah, Oct 16-19, 2000 ANL/TD/CP-103408.
141.
Mattas, R. F.;Malang, S.;Khater, H.;Majumdar, S.;Mogahed, E.;Nelson, B.;
Sawan, M.;Sze, D. K, "EVOLVE - an advanced first wall/blanket system",
Fusion Eng. Des., 49: 613-620, Nov. 2000 Italian Agency for New Technologies,
Energy and Environment 5th International Symposium on Fusion Nuclear
Technology, Rome, Italy, Sep 19-24, 1999 ANL/TD/CP-98296.
140.
Tillack, M. S.;Billone, M.;El-Guebaly, L.;Sze, D. K.;Waganer, L. M.;
Wong, C.;Aries Team Collaboration, "Engineering options for the U.S.
fusion demo", 16th Symposium on Fusion Engineering, Champaign, IL,
Sep 30 - Oct 1, 1995 ANL/ET/CP-90986.
139.
Sze, D.K., "Engineering design of CLIFF-flibe and divertor
integration and flibe chemistry (convective liquid flow first-wall
concept)", APEX/HPD Workshop, Tokyo, Japan, Feb 21-23, 2000.
138.
Sze, D. K.;Wong, C.;Cheng, E.;Sawan, M. E.;Sviatoslavsky, I. N.;
Blanchard, J. P.;El-Guebaly, L. A.;Khater, H. U.;Mogahed, E. G.;
Gierszewski, P.;Hollies, R.;ARIES Team, "Engineering design of
ARIES-III", 2nd Wisconsin Symposium on Helium-3 and Fusion Power,
Madison, WI, Jul 19-21, 1993 ANL/EP/CP-79939.
137.
Sze, D. K.;Wong, C.;Cheng, E.;Sawan, M. E.;Sviatoslavsky, I. N.;
Blanchard, J. P.;El-Guebaly, L. A.;Khater, H. U.;Mogahed, E. G.;
Gierszewski, P.;Hollies, R.;ARIES Team, Engineering design of ARIES-III",
2nd Wisconsin Symposium on Helium-3 and Fusion Power, Madison, WI, Jul 19-21, 1993.
136.
Sze, D.K.;Natesan, K.;Park, J. H.;Reed, C. B.;Mattas, R. F.,
"Development of electrically insulating coatings on vanadium alloys
to mitigate MHD effects in lithium-cooled blankets", Italian Agency
for New Technologies, Energy and Environment 5th International
Symposium on Fusion Nuclear Technology, Rome, Italy, Sep 19-24, 1999.
135.
Sze, D. K.;Hassanein, A., "Design windows for a He cooled fusion reactor",
IEEE;Nuclear and Plasma Sciences Society Symposium on Fusion Engineering,
Hyannis, MA, Oct 11-15, 1993 ANL/EP/CP-79903.
134.
Sze, D. K.;Hassanein, A. "Design windows for a He cooled fusion reactor",
IEEE;Nuclear and Plasma Sciences Society Symposium on Fusion Engineering,
Hyannis, MA, Oct 11-15, 1993.
133.
Hua, T. Q.;Smith, D. L.;Sze, D. K.;Abdou, M. A.;Waganer, L.;Dagher, M.;
Kirillov, I. R.;Danilin, I. V., "Design and analysis of the ITER Li/V
test blanket system", 4th International Symposium on Fusion Nuclear
Technology, Tokyo, Japan, Apr 6-11, 1997.
132.
Finn, P. A.;Sze, D. K.;Clemmer, R. G., "Conceptual design description
for the tritium recovery system for the U.S. ITER Li{sub 2}O/Be water
cooled blanket", ANL/FPP/TM.
131.
Sze, D.K., "Comments on the US-Japan Monbusho collaboration proposal",
Japan Monbusho - USDOE Collaboration in Planning Workshop, Tokyo,
Japan, Feb 23-25, 2000.
130.
Sze, D.K., "Comments on Monbusho-DOE collaboration proposal",
US/Japan Workshop on Power Plant Studies and Advanced Technology, LaJolla,
CA, Mar 16-18, 2000.
129.
Sze, D. K., "Blankets and fuel cycle," MIT Fusion Power Plant Symposium,
Cambridge, MA, Jan 22, 2001.
128.
Sze, D.K.;Tillack, M. S.;Sviatoslavsky, I. N.;El-Guebaly, L. A.;
Wong, C. C. P.;Waganer, L. M., "Blanket selection for the starlite
project", 12th Topical Meeting on the Technology of Fusion Energy,
Reno, NV, Jun 16-20, 1996
127.
Sze, D. K.;Mattas, R. F.;Yoshida, H., "Assessment of different methods
for tritium recovery from lithium", 3rd International Symposium on Fusion
Nuclear Technology, Los Angeles, CA, Jun 27 - Jul 1, 1994
126.
Sze, D. K.;Tam, S. W.;Billone, M. C.;Hassanein, A. M.;Martin, R., "ARIES-I
tritium system", ANS;DOE;Argonne National Lab. 9th Topical Meeting on
Technology of Fusion Energy, Oak Brook, IL, Oct 7-11, 1990.
125.
Hassanein, A.;Smith, D. L.;Sze, D. K.;Reed, C. B., "Analysis of the
tritium-water (T-H{sub 2}O) system for a fusion material test facility",
ANL/FPP/TM-261 April 1992.
124.
Sze, D.K., "An Innovative flowing-bed blanket and divertor
concept", 17th IEEE/NPSS Symposium on Fusion Engineering (SOFE '97),
San Diego, CA, Oct 6-10, 1997.
123.
Sawan, M.E., Huang, Jin-Hua, Kulcinski, G.L., Li, Yaotong, Plute, K.E.,
Sviatoslavsky, I.N., Sze, D. K., Vogelsang, W.F., and White, A.,
"Response of a Liquid Metal Test Blanket for the MFTF-B+T Device",
September 7, 1982, UWFDM 485.
122.
Sviatoslavsky, I.N., Van Sciver, S.W., Kulcinski, G. L., Emmert, G.A.,
Anderson, D.T., Bailey, A.W., Callen, J.D., Derr, J.A., El-Guebaly, L.,
Lee, K.J., Shohet, J.L., Sze, D.K., Sanders, R.C., Tataronis, J.,
and Yuan, K. Y., (University of Wisconsin), Bathke, C.G., Miller, R.L.,
and Krakowski, R.A., (Los Alamos National Laboratory), "Progress in
Modular Stellarator Fusion Power Reactor Conceptual Designs", Night
International Conference on Plasma Physics and Controlled Nuclear Fusion
Research, IAEA Meeting, Baltimore, Mayland, September 1-8, 1982, paper
IAEA-CN-41/E-3.
121.
Badger, B., Arendt, F. Attaya, H. M., Audenaerde, K., Beyer, J. B.,
Bogusch, E., Bohme, D., Bruggink, D., Dietz, L. P., El-Guebaly, L.,
Emmert, G.A., Frey, H. Grant, G., Heinz, W., Kohler, W., Komarek, P.,
Kulcinski, G. L., Larsen, E.M., Lechtenberg, T., Li, X. Z., Maurer, W.,
Maynard, C.W., Montalov, E., Musicki, Z., Opperman, E., Osher, J.E.,
Perkins, L.J., Peterson, R.R., Plute, K.E., Santarius, J.F., Sawan, M.E.,
Scharer, J.E., Schluderberg, D.C., Suppan, A., Sviatoslavsky, I.N.,
Sze, D. K., Vogel, M.A., Vogelsang, W. F., White, A.M., Wolfer, W.G.,
Yuan, K.Y., and Young, D.B., "TASKA A Tandem Mirror Fusion Engineering
Facility", march 1982, UWFDM 500.
120.
Plute, K.E., and Sze, D.K., "A Modified Production Scheme to
Reduce the Tritium Inventory in an ICF Target Factory", Trans. Am.
Nucl. Soc. 43, 223, (1982).
119.
Badger, B., Arendt, F., Becker, K., Beckert K.,Bock, R., Bohne, D.,
Bozsik, I., Brezina, J., Dalle Donne, M., El-Guebaly, L., Engelstad,
R., Eyrich, W., Frohlick, R., Ghoniem, N., Goel, B., Hassanein, A.,
Henderson, D., Hobel, W., Hofmann, I., Hoyer, E., Keller, R., Kessler, G.,
Klein, A., Kreutz, R. Kulcinski, G., Larsen, E., Lee, K., Long, K.,
Lovell, E., Metzler, N., Meyer-ter- Vehn, J., von Mollendorff, U., Moritz, N.,
Moses, G., Muller, R., O¹Brien, K., Peterson, R., Plute, K., Spindler, T.,
Sviatoslavsky, I., Symon, K., Sze D., Tahir, N., Vogelsang, W., White, A.,
Witkowski, S., and Wollnik, H., "HIBALL A Conceptual Heavy Ion Beam
Driven Fusion Reactor Study", September 1981, UWFDM 450.
118.
S. P. Grotz, E. Cheng, M. Z. Hasan, J.S. Herring, F. Najmabadi,
E.E. Reis, Jr., S. Sharafat, D. K. Sze, M. Valenti, E. Vold,
C.P.C. Wong, and the ARIES Team, "Divertor Engineering for the
ARIES-I Tokamak Reactor" Fusion Technol., 19 No. 3 (1991).
Presented at the 9th Topical Meeting on the Technology of Fusion Energy.
117.
C.P.C Wong, E. T. Cheng, K. R. Schultz, S. P. Grotz, M. Z. Hasans,
F. Najmabadi, S. Sharafat, T. Kunugi, J.S. Herring, D. K. Sze and
the ARIES Team "ARIES-I SIC Composite Blanket Design"
Fusion Technol., 19, No. 3 (1991). Presnted at the 9th Topical Meeting
on the Technology of Fusion Energy, October 1990.
116.
J. Stephen Herring, Clement Wong, E. T. Cheng, D. K. Sze, S. P. Grotz,
and the ARIES Team, "Activation Product Safety in the ARIES-I Reactor
Design" Fusion Technol., 19, No.3 (1991). Presented at the 9th Topical
Meeting on the Technology of Fusion Energy, October 1990.
115.
P.A. Finn, M. Billone, Y. Gohar, D. K. Sze, R. Clemmer, and L. Greenwood,
"Design Description for the Tritium Recovery System for the U.S. Li2/Be
Blanket for ITER" Fusion Technol., 19, No. 3 (1991). Presented at the 9th
Topical Meeting on the Technology of Fusion Energy, October 1990.
114.
D. K. Sze, P. Finn, J. Anderson, J. Bartlit, and R. Sherman, "Possible
Design Modifications of ITER Fuel Cycle" Fusion Technol., 19. No. 3 (1991).
Presented at the 9th Topical Meeting on the Technology of Fusion Energy,
October 1990.
113.
D. K. Sze, S. W. Tam, R. Martin and the ARIES Team, "ARIES-I Tritium System",
Fusion Technol., 19 No. 3 (1991). Presented at the 9th Topical Meeting on
the Technology of Fusion Energy, October 1990.
112.
P.A. Finn, R. G. Clemmer, L. R. Greenwood, A. Lide, D. K. Sze,
J. L. Anderson, R. Sherman, J. R. Bartlit, Y. Naruse, and H. Yoshida,
"The Blanket Interface to TSTA: Requirements for an Aqueous Lithium
Salt Blanket," Fusion Technology, 15 (1989) 680-666.
111.
P.A. Finn, D. K. Sze, et. al., "Analysis of the Breeder Blanket Interface
for a Liquid Lithium Blanket," Fusion Eng. and Design, 11, (1989) 335-357.
110.
R. G. Clemmer, P.A. Finn, L. R. Greenwood, D. K. Sze, et. al., "The Breeder
Blanket Interface for a Solid Breeder Blanket Concept, "Argonne National
Laboratory Report ANL/FPP/TM-232 (1989).
109.
C. P. C. Wong, D. K. Sze, "The TITAN-II Reversed-field-pinch Fusion
power Core Design," Fusion Engineering and Design, 23, p. 173, Dec. 1993.
108.
F. Najmabadi, D. K. Sze, "The TITAN-II Reversed-field-pinch Fusion-power
Core Design". Fusion Engineering and Design, 23, P.81 Dec. 1993.
107.
F. Najmabadi, D. K. Sze, "Introductino and Synopsis of the TITAN
Reversed-field-pinch Fusion reactor Study", Fusion Engineering and
Design, 23, P.69, Dec 1993.
106.
D. K. Sze, A. Hasanein, "Design Window for a He-cooled Fusion Reactor",
Proceedings of 15 IEEE Symposiums on Fusion Engineering, Oct. 1993.
105.
M. Tillack, D. K. Sze, "Fusion Nuclear Technology and Materials, Statues
and R&D Needs, IAEA Technical Committee Meeting and Workshop on Fusion
Reactor Design and Technology, to be published in Fusion Engineering and Design.
104.
D. K. Sze, R. F. Mattas, A. B. Hull, B. Picologlou, and D. L. Smith,
"MHD Considerations for a Self-cooled Liquid Lithium Blanket",
Fusion Technology 21 (1992) 2099.
103.
E.T. Chang, D. K. Sze, J.A. Sommers, and D.T. Farmer, III,
"Materials Recycling Considerations for D-t Fusion Reactors",
Fusion Technology 21 (1992) 2001.
102.
D. K. Sze S. Herring, and M. Sawan, "Tritium Production, Management,
and its Impact on Safety for a D-3He Fusion Reactor", Fusion
Technology 21 (1992) 994.
101.
P.A. Finn, D. K. Sze and R. G. Clemmer, "Concept Design Description
for the Tritium Recovery System for the US ITER Li20/Be Water Cooled
Blanket, Revision 1.0.
100.
R.G. Clemmer, V.A. Maroni, P.E. Blackburn, E. VanDeventer,
and D.K., Sze, "Flibe Chemistry Stuidies", Fusion Technol.,
19 No. 3 (1991). Presented at the 9th Topical Meeting on the
Technology of Fusion Energy.
99.
Schluderberg, D.C., Huang, J.H., Pong, L., and Sze, D.K.,
"Thermal and Mechanical Design of a Double-Walled Steam Generator",
Fifth Topical Meeting on the Technology of Fusion Energy,
April 1983, Knoxville, Tennessee.
98.
Corradini, M.L., and Sze, D.K., "Modeling of
Lithium-Lead/Water Interactions", Fifth Topical Meeting on
the Technology of Fusion Energy, April 1983, Knoxville, Tennessee.
97.
Sze, D.K., and White, A., "Emergency Cooling of the
MARS Li-Pb Blanket and Shield", Fifth Topical Meeting on the
Technology of Fusion Energy, April 1983, Knoxville, Tennessee.
96.
Li, Y.T., Sze, D.K., and Sviatoslavsky, I.N., "Mechanical
and Thermal Design Aspects of the Blanket, and Maintenance
Considerations of the Central Cell in MARS", Fifth Topical
Meeting on the Technology of Fusion Energy, April 1983, Knoxville, Tennessee.
95.
Plute, K.E., Larsen, E.M., and Sze, D.K., "Tritium Recovery
from Liquid Lithium-Lead by Vacuum Degassing", Fifth Topical Meeting
on the Technology of Fusion Energy, April 1983, Knoxville, Tennessee.
94.
Sawan, M.E., Vogelsang, W.F., and Sze, D.K., "An Effective
Penetration Shield Design for ICF Reactors", Proceedings of Sixth
International Conference on Radiation Shielding, Tokyo, Japan, 16-20 May 1983.
93.
Sawan, M.E., Vogelsang, W.F., and Sze, D.K., "Radiation
Shielding Analysis of Beam Line Penertrations in HIBALL", Trans.
Am. Nucl. Soc. 39, 777, (1981).
92.
Sze, D.K., "Design Considerations of a Double-Walled Steam
Generator", Trans. Am. Nucl. Soc. 43, 199, (1982).
91.
Sze, D.K., "Design Considerations of a Double-Walled Steam
Generator", Trans. Am. Nucl. Soc. 43, 199, (1982).
90.
Sze, D.K., and Cheng, E.T., "Tritium Confinement and
Recovery Considerations for Li17Pb83 Fusion Blanket", Trans.
Am. Nucl. Soc. 39, 271, (1981).
89.
Badger, B., Svitoslavsky, I.N., Van Sciver, S.W., Kulcinski,
G. L., Emmert, G.A., Anderson, D.T., Bailey, A.W., Callen, J.D.,
Derr, J.A., El-Guebaly, L., Lee, K.J., Shohet, J.L., Sze, D.K.,
Sanders, R.C., Tataronis, J., and Yuan, K.Y., "UWTOR-M A Conceptual
Modular Stellarator Power Reactor", October 1982, UWFDM 550.
88.
J. Stephen Herring, Clement Wong, E.T. Cheng, D. K. Sze, S. P. Grotz,
and the ARIES Team
87.
D. K. Sze, P. Finn, J. Anderson, J. Bartlit, and R. Sherman,
"Possible Design Modifications of ITER Fuel Cycle" Fusion Technol.,
19, No.3 (1991). Presented at the 9th Topical Meeting on the Technology
of Fusion Energy, October 1990.
86.
D. K. Sze, S. W. Tam, R. Martin, and the ARIES Team, "ARIES-I
Tritium System" Fusion Technol., 19, No. 3 (1991). Presented at the
9th Topical Meeting on the Technology of Fusion Energy, October 1990.
85.
P.A. Finn, R. G. Ciemmer, L. R. Greenwood, A. Lide, D. K. Sze,
J. L. Anderson, R. Sherman, J. R. Bartlit, Y. Naruse, and H. Yoshida,
"The Blanket Interface to TSTA: Requirements for an Aqueous Lithium
Salt Blanket," Fusion Technology, 15 (1989) 680-686.
84.
P. A. Finn, D. K. Sze, et al, "Analysis of the Breeder Blanket
Interface for a Liquid Lithium Blanket," Fusion Eng. And Design, 11,
(1989) 335-357.
83.
R. G. Clemmer, P.A. Finn, L. R. Greenwood, D. K. Sze, et al.,
"The Breeder Blanket Interface for Solid Breeder Blanket Concept,"
Argonne National Laboratory Report ANL/FPP/TM-232 (1989).
82.
S. P Grotz, F. Najmabadi, L. Bromberg, R. L. Creedon, C.P.C. Wong,
R. A. Krakowski, and D. K. Sze, "Design Integration of the ARIES-I
Tokamak Reactor," Thirteenth Symposium on Fusion Engineering,
Knoxville, Tennessee, October 2-6, 1989.
81.
R. G. Clemmer, J. Anderson, J. Bartlit, R. Sherman, D. K. Sze,
P. Finn, R. Clemmer, Y. Naruse, H. Yoshida, K. Okuno, M. Enoeda,
"The Breeding Blanket Interface (BBI) and the Tritium System Test
Assembly (TSTA)," Thirteenth Symposium on Fusion Engineering, Knoxville,
Tennessee, October 2-6, 1989.
80.
C. P. C. Wong, E. T. Cheng, R. L. Creedon, K. R. Schultz, G. Thurston,
Y. Gohar, C. Baker, H. Attaya, M. Billone, A. Hassanein, C. Johnson,
S. Majumdar, R. Mattas, D. Smith, and D. K. Sze, "A Li-Particulate
Blanket Concept for ITER," Proc. Eighth ANS Topical Mtg. on
Technology of Fusion Energy, Salt Lake City, UT., October 9-13, 1988.
Fusion Technology, Vol. 15, March 1989.
79.
Y. Gohar, C. Baker, H. Attaya, M. Bilone, R. Clemmer, P. Finn,
A. Hassanein, C. Johnson, S. Majumdar, R. Mattas, D. L. Smith,
H. Stevens, D. K. Sze, and L. Turner, "Helium-Cooled Lithium
Compound Suspension Blanket Concept for ITER," Fusion Technol. 15,
876-880 (March 1989), (also Proc. Eighth Topical Mtg. On Technology
of Fusion Energy, Salt Lake City, UT., October 9-13, 1988.)
78.
Y. Gohar, C. C. Baker, H. Attaya, M. Billone, R. G. Clemmer,
P.A. Finn, A. Hassanein, C. E. Johnson, S. Majumdar, R. F. Mattas,
D. L. Smith, H. Stevens, D. K. Sze, and L. R. Turner, "Water-Cooled,
Solid-Breeder Blanket Concept for ITER," Fusion Tecnol. 15,
864-870 (March 1989). (Proc. Eighth Topical Mtg. On Technology
of Fusion Energy, Salt Lake City, UT., October 9-13, 1988.)
77.
D. K. Sze, P. A. Finn, J. Bartlit, S. Brereton, P. J. Gierszewski
and D. Jefford, "Cost Optimization of ITER Blanket Tritium System,"
abstract to be presented at the 8th Topical Meeting on the Technology
of Fusion Energy, Salt Lake City, UT., October 9-13, 1988.
76.
R. G. Clemmer, P.A. Finn, L. R. Greenwood, T. L. Grimm, D. K. Sze,
J. R. Bartlit, J. L. Anderson, H. Yoshida and Y. Naruse, "The
Requirements for Processing Tritium Recovered from Liquid Lithium
Blankets: The Blanket Interface," Argonne National Laboratory report,
ANL/FPP/TM-217, February 1988.
75.
D. K. Sze, J. Gordon, S. Piet, C. T. Chang, J. DeVan, and A. Klein,
"Engineering, Safety, Economics and R&D Evaluations of ASPIRE,"
to be presented at the International Symposium on Fusion Nuclear
Technology, Tokyo, Japan, April 10-19, 1988.
74.
D. K. Sze, P. Finn, R. Clemmer, J. Anderson, J. Bartlit (LANL),
Y. Naruse, H. Yoshida (JAERI), "The Role of a Blanket Tritium
System on the Fusion Fuel Cycle," to be submitted for presentation
at the International Symposium on Fusion Nuclear Technology, Tokyo,
Japan, April 10-19, 1988.
73.
D. K. Sze, P.A. Finn, J. Bartlit, S. Tanaka, T. Terai, and
M. Yamawaki, "Combined Gettering and Motlen Salt Process for
Tritium Recovery from Lithium, to be presented at the
International Symposium on Fusion Nuclear Technology, Tokyo,
JAPAN, April 10-19, 1988.
72.
D. Ehst, C. Baker, M. Billone, J. Brooks, Y. Cha, K. Evans,
P. Finn, Y. Gohar, A. Hassanein, Y. Liu, S. Majumdar, R. Mattas,
B. Picologlou, D. Smith, H. Stevens, D. Sze and S. Yang,
"Tokamak Power Systems Studies: A Second Stability Power Reactor,"
to be presented at the 12th Symposium on Fusion Engineering,
Monterey, CA, October 12-16, 1987.
71.
R. F. Mattas, C. C. Baker, Y. Cha, P.A. Finn, S. Majurndar,
F. B. Picologlou, D. Sze, H. Stevens, M. A. Abdou, A. Hadid,
R. Raffray, M.S. Tillack, M. Youssef, E. Cheng, R. L. Creedon,
B. A. Engholm, K. Schultz, C.P.C. Wond, L. Deutsch, J. Gordon,
S. Piet, R. Pugih, D. Steiner, Y. Watanabe, "Blanket Module
Testing in TIBER," abstract to be presented at the 12th
Symposium on Fusion Engineering, Monterey, CA, October 12-16, 1987.
70.
D. K. Sze, "An Assessment of Tritium Issues and Data Requirements
for Liquid Breeders," presented at the Tritium Technology Workshop
P89 Japan-U.S. Agreement on Fusion Energy Naka fusion Research
Establishment, JAERI, JAPAN.
69.
D. K. Sze, M. Abdou, M. Tillack, P. Gierszewski, and R. Puigh,
"Technical Requirements of Experiments and Facilities for Fusion
Blanket Development," presented at the International Symposium on
Fusion Reactor Blanket and Fuel Cycle Technology, October 27, 1986.
68.
D. K. Sze, Y. Cha, J. D. Gordon, J. K. Gamer, R. H. Whitley,
S. Piet, E. Cheng, J. DeVan, A. Klein, "ASPIRE-Advanced Safe Pool Immersed
Reactor," to be presented at the International Symposium on Fusion
Reactor Blanket and Fuel Cycle Technology, October 1986.
67.
D. K. Sze, A. G. Klein, "Fibe-Vanadium Alloy System Corrosion
Product Radiation Hazards Analysis," conference on the 7th
Topical Meeting on the Technology of Fusion Energy, MGM
Grand Hotel, Reno, Nevada, June 15-19, 1996.
66.
Y. Cha and D. K. Sze, contributors to "FINESSE Phase I Report
Technical Issues and Requirements of Experiments and Facilities
for Fusion Nuclear Technology," Univ. California Report PPG-909,
UCLA-ENG-85-39 (December 1985).
65.
D. K. Sze, contribution to "MINIMARS Conceptual Design: Report I,"
UCID-20559, Vol. 1 ( December 1995); J. D. Lee, Technical Editor.
64.
D. K. Sze, "Counter Current Extraction System for Tritium Recovery
from 17Li-87Pb," Fusion Technol. 8(1) Pt. 887 (1985).
63.
P.A. Finn and D. K. Sze, "Tritium Technology Review," Fusion Technol.
8(1), Pt. 698 (1985).
62.
D. K. Sze and E. T. Cheng, "A Molten Salt Cooling/17Li-83Pb Breeding
Blanket Concept," Fusion Technol. 8(1) Pt. 953 (1985).
61.
Y-S. Cha, Y. Gohar, A. M. Hassanein, S. Majurndar, B.F. Picologlou,
D. K. Sze, D. L. Smith, "Design of Self-Cooled, Liquid Metal Blankets
for Tokamak and Tandem Mirror Reactors," Fusion Technology 8(1), Pt. 90 (1985).
60.
D. L. Smith, C. C. Baker, D. K. Sze, G. D. Morgan, M.A. Abdou,
S. J. Piet, K. R. Schultz, R. W. Moir, J. D. Gordon, "Overview
of the Blanket Comparison and Selection Study," Fusion Technol, 8(1), Pt. 10 (1985).
59.
D. K. Sze, A. Hassanein (ANL), S. J. Piet (EG&G Idaho), C. Wong (GA),
and W. D. Bjorndahl (TRW), "An Assessment of Problems Associated with
Tritium Containment," Trans. Arn. Nucl. Soc. 46, 203 (1984) Abstract.
58.
D. K. Sze, Y.S. Cha, Y. Gohar, S. Majumdar, B. Picologiou, and D. L. Smith,
"Liquid-Metal Breeder/Coolant Blanket Concept," Trans. Am. Nucl.
Soc. 46, 199 (1984) Abstract.
57.
G.D. Morgan, D. Bowers, T. Hellwing, D. Ruester (MDAC), D. K. Sze,
C. Johnson, J. Jung, Y.Y. Liu, B. Misra (ANL), J. D. Gordon,
D. H. Berwald, J.K. Garner, and T. J. McCarville (TRW), "Water-Cooled
Liquid and Solid Breeder Blanket Concepts," Trans. Am. Nucl.
Soc. 46, 198 (1984) Abstract.
56.
Bohue, D., et al, "HIBALL A Conceftual Design Study of A
Heavy-Ion Driven Inertial Confinement Fusion Power Plant",
Nuclear Engineering and Design, 73, (1982), 195.
55.
Schluderberg, D.C., Huang, J.H., Pong, L., and Sze, D.K.,
"Thermal and Mechanical Design of a Double-Walled Steam Generator",
Fifth Topical Meeting on the Technology of Fusion Energy, April 1983,
Knoxville, Tennessee.
54.
Corradini, M.L., and Sze, D.K., "Modeling of the
Lithium-Lead/Water Interactions", Fifth Topical Meeting on
the Technology of Fusion Energy, April 1983, Knoxville, Tennessee.
53.
Sze, D.K., and White, A., "Emergency Cooling of the MARS
Li-Pb Blanket and Shield", Fifth Topical Meeting on the Technology
of Fusion Energy, April 1983, Knoxville, Tennessee.
52.
Li, Y.T., Sze, D.K., and Sviatoslavsky, I.N., "Mechanical
and Thermal Design Aspects of the Blanket, and Maintenance
Considerations of the Central Cell in MARS", Fifth Topical Meeting
on the Technology of Fusion Energy, April 1983, Knoxville, Tennessee.
51.
Plute, K.E., Larsen, E.M., and Sze, D.K., "Tritium Recovery
from Liquid Lithium-Lead by Vacuum Degassing", Fifth Topical
Meeting on the Technology of Fusion Energy, April 1983, Knoxville, Tennessee.
50.
Sawan, M.E., Vogelsang, W.F., and Sze, D.K., "An Effective
Penetration Shield Design for ICF Reactors", Proceedings of Sixth
International Conference on Radiation Shielding, Tokyo, Japan, 16-20 May 1983.
49.
Sawan, M.E., Vogelsang, W.F., and Sze, D.K., "Radiation
Shielding Analysis of Beam Line Penetrations in HIBALL", Trans.
Am. Nucl. Soc. 39, 777, (1981).
48.
Sze, D.K., "Design Considerations of a Double-Walled Steam
Generator", Trans. Am. Nucl. Soc. 43, 199, (1982).
47.
Sze, D.K., and Cheng, E.T., "Tritium Confinement and Recovery
Considerations for Li17Pb82 Fusion Blanket," Trans. Am. Nucl. Soc. 39, 271, (1981).
46.
Badger, B., Sviatoslavsky, I.N., Van Sciver, S.W., Kulcinski,
G.L., Emmert, G.A., Anderson, D.T., Bailey, A.W., Callen, J.D.,
Derr, J.A., El-Guebaly, L., Lee, K.J., Shohet, J.L., Sze, D.K.,
Sanders, R.C., Tataronis, J., and Yuan, J.Y., "UWTOR-M A Conceptual
Modular Stellarator Power Reactor", October 1982, UWFDM 550.
45.
Badger, B., Corradini, M.L., Emmert, G.A., Kulcinski, G.L.,
Larsen, E.M., Lovell, E.G., Maynard, C.W., Moses, G.A.,
Perkins, L.J., Peterson, R.R., Plute, K.E., Santarius, J.,
Sviatoslavsky, I.N., Sze, D.K., Von Sciver, S.W.,
Vogelsang, W.F., and Wolfer, W.G., "Fusion Power Status Report:
The Last Five Years", February 15, 1983, UWFDM 496.
44.
Sawan, M.E., Huang, Juh-Hua, Kulcinski, G.L., Li, Yaotong,
Plute, K.E., Sviatoslavsy, I.N., Sze, D.K.,
Vogelsang, W.F., and White, A., "Response of a Liquid Metal
Test Blanket for the MFTF-B+T Device", September 7, 1982, UWFDM 485.
43.
Sviatoslavsky, I.N., Van Sciver, S.W., Kulcinski, G.L.,
Emmert, G.A., Anderson, D.T., Bailey, A.W., Callen, J.D.,
Derr, J.A., El-Guebaly, L., Lee, K.J., Shohet, J.L., Sze, D.K.,
Sanders, R.C., Tataronis, J., and Yuan, K.Y., (University of Wisconsin),
Bathke, C.G., Miller, R.L., and Krakowski, R.A.,
(Los Alamos National Laboratory), "Progress in Modular
Stellarator Fusion Power Reactor Conceptual Designs",
Ninth International Conference on Plasma Physics and
Controlled Nuclear Fusion Research, IAEA Meeting, Baltimore,
Maryland, September 1-8, 1982, paper IAEA-CN-41/E-3.
42.
Badger, B., Arendt, F., Attaya, H.M., Audenaerde, K., Beyer, J.B.,
Bogusch, E., Bohme, D., Bruggink, D., Dietz, L.P., El-Guebaly, L.,
Emmert, G.A., Frey, H., Grant, G., Heinz, W., Kohler, W.,
Komarek, P., Kulcinski, G.L., Larsen, E.M., Lechtenberg, T.,
Li, X.Z., Maurer, W., Maynard, C.W., Montalvo, E., Musicki, Z.,
Opperman, E., Osher, J.E., Perkins, L.J., Peterson, R.R.,
Plute, K.E., Santarius, J.F., Sawan, M.E., Scharer, J.E.,
Schluderberg, D.C., Suppan, A., Sviatoslavsky, I.N., Sze, D.,
Vogel, M.A., Vogelsang, W., White, A., Wolfer, W.G.,
Yuan, K.Y., and Young, D.B., "TASKA A Tandem Mirror
Fusion Engineering Facilicy", March 1982, UWFDM 500.
41.
Plute, K.E., and Sze, D.K., "A Modified Production
Scheme to Reduce the Tritium Inventory in an ICF Target Factory",
Trans. Am. Nucl. Soc. 43, 223, (1982).
40.
Sze, D.K., "In-Situ Tritium Recovery from Li17 Pb83
Breeding Blanket", Proceedings of the Ninth Symposium on
Engineering Problems of Fusion Research, Chicago, Illinois, October 26-29, 1981.
39.
Sawan, M.E., Sze, D.K., and Kulcinski, G.L., "An Improved
Materials Testing Module for Magnetic Fusion", Proceedings of the
Chicago, Illinois, October, Illinois, October 26-29, 1981.
38.
Peterson, R.R., Sze, D.K., Hassanein, A.M., and Pong, L.,
"Gas Dynamics and Heat Transfer Phenomena in Liquid Metal ICF Reactor
First Surfaces", Proceedings of the Ninth Symposium on Engineering
Problems of Fusion Research, Chicago, Illinois, October 26-29, 1981.
37.
Sviatoslavsky, I.N., Van Sciver, S.W., Kulcinski, G.L.,
Anderson, D.T., Bailey, A.W., Callen, J.D., Derr, J.A.,
Emmert, G.A., ElGuebaly, L., Khalil, A., Shohet, J.L., Sze, D.K.,
Sanders, R.C., Tataronis, J., and Yuan, K., "Third Technical Committee
and Workshop on Fusion Reactor Design and Technology, Tokyo, Japan,
October 5-16, 1981.
36.
Badger, B., Arendt, F., Becker, K., Beckert, K., Bock, R., Bohne, D.,
Bozsik, I., Brezina, J., Dalle Donne, M., El-Guebaly, L.,
Engelstad, R., Eyrich, W., Frohlick, R., Ghoniem, N., Goel, B.,
Hassanein, A., Henderson, D., Hobel, W., Hofmann, I., Hoyer, E.,
Keller, R., Kessler, G., Klein, A., Kreutz, R., Kulcinski, G.,
Larsen, E., Lee, K., Long, K., Lovell, E., Metzler, N.,
Meyer-terVehn, J., von Mollendorff, U., Moritz, N., Moses, G.,
Muller, R., O¹Brien, K., Peterson, R., Plute, K., Pong, L.,
Sanders, R., Sapp, J., Sawan, M., Schretzmann, K., Spindler, T.,
Sviatoslavsky, I., Symon, K., Sze, D., Tahir, N., Vogelsang, W.,
White, A., Witkowski, S., and Wollnik, H., "HIBALL A Conceptual
Heavy Ion Beam Driven Fusion Reactor Study", September 1981, UWFDM 450.
35.
Kulcinski, G.L., Moses, G.A., Sapp, J., Sawan, M.,
Sviatoslavsky, I.N., Sze, D.K., and Vogelsang, W.F.,
"The INPORT Concept - An Improved Method to Protect ICF Reactor First Walls",
Second Topical Meeting on Fusion Reactor Materials, August 9-12, 1981,
Seattle, Washington.
34.
Badger, B., Audenaerde, K., Beyer, J.B., Braun, D., Callen, J.D.,
Emmert, G.A., Gilmore, J.M., Hoffman, N., Kesner, J.,
Kulcinski, G.L., Larbalestier, D.C., Larsen, E., Li, X.,
Maurer, W., Maynard, C.W., Ojalvo, I., Ortman, M., Perry, R.,
Ragheb, M., Santarius, J., Scharer, J., Schluderberg, D.,
Shaing, K., Sviatoslavsky, I.N., Sze, D.K.,
Vogelsang, W.F., White, A., Wilkes, P., and Yang, T.,
"WITAMIR-I, A University of Wisconsin Tandem Mirror Reactor
Design", September 1980, UWFDM 400.
33.
Sze, D.K., Homeyer, W.G., Creedon, R.L., Wong, C.P.,
and Kulcinski, G.L., "Thermal and Mechanical Design
Considerations for INTOR Divertor Plate", October 1980, UWFDM 388.
32.
Santarius, J., Audenaerde, K., Beyer, J.,Emmert, G.A.,
Kesner, J.,Kulcinski, G.L., Larbalestier, D.C., Maurer, W.,
Maynard, C.W. Perry, R.T., Scharer, J. Sviatoslavsky, I.N.,
and Sze, D.K., "WITAMIR-I, A Tandem Mirror Reactor
with Non-Zero Nu", Proceedings of the Eleventh SOFT
Conference, Oxford, England, 1980, P.1261.
31.
Sze, D.K., Clemmer, R., and Cheng, E.T., "LiPb, A
Novel Material for Fusion Applications", Proceedings of the
Fourth ANS Topical Meeting, King of Prussia, PA, October 1980.
30.
Sze, D.K., and Sviatoslavsky, I.N., "Thermal and Mechanical
Design of WITIMAR-I Blanket", Proceedings of the Fourth ANS Topical
Meeting, King of Prussia, PA, October 1980.
29.
Kulcinski, G.L., Emmert, G.A., Maynard, C.W., Audenaerde, K.,
Beyer, J., Braun, D.o Callen, J.D., Gilmore, J.M., Kesner, J.,
Larbalestier, D.C., Larsen, E, Li, X., Maurer, W., Ortman, M.,
Perry, R., Ragheb, M., Santarius, J., Scharer, J.,
Schluderberg, D., Shaing, K., Sviatoslavsky, I.N., Sze, D.K.,
Vogelsang, W.F., White, A., and Yang, T., "A Commercial Tandem Mirror
Reactor Design wit Thermal Barriers WITAMIR-I", Proceedings of the
Fourth ANS Topical Meeting, King of Prussia, PA, October 1980.
28.
Okula, K., and Sze, D.K., "Tritium Recovery from Solid
Breeders: Implications of the Existing Data", Proceedings of
Tritium Technology in Fission, Fusion and Isotopic Applications,
Dayton, Ohio, April 1980.
27.
Bauer, D.G., Stewart, W.E., Sviatoslavsky, I.N., and Sze, D.K.,
"Experiments on the Corrosion of 316 Stainless Steel by Liquid
Lithium", Proceedings of the Second International Conference on
Liquid Metal Technology in Energy Production, Richland, Washington, 1980.
26.
Conn, R.W., Sviatoslavsky, I.N., and Sze, D.K., "Limiter
Pumping System for Divertorless Tokamaks", Eighth Symposium on
Engineering Problems of Fusion Research, San Francisco, California, November 1979.
25.
Badger, B., Auderaerde, K., Avci, H., Beyer, J., Blackfield, D.,
Cameron, E., Cheng, E., Conn, R.W., Emmert, G.A., Gordinier, M.,
Hong, S., Kesner, J., Klein, A., Kulcinski, G.L., Lao, L.,
Larsen, E., Mai, L.P., Mau, T.K., Maynard, C.W.,
Michaelson, P., O¹Donnell, G., Ortman, M., Ragheb, M.,
Schrarer, J., Schluderberg, D.C., Sviatoslavsky, I.N., Sze, D.K.,
Thornton, T., Vogelsang, W.F., Wilkes, P., Willimas J., Wu, T.,
Wrazel, J., and Young, W.C., "NUWMAK A Tokamak Reactor Design
Study Chapter I (Design and Philosophy) & II (Overview and Summary)",
March 1979, UWFDM 330a.
24.
Badger, B., Auderaerde, K., Avci, H., Beyer, J., Blackfield, D.,
Boom, R.W., Cameron, E., Cheng, E., Conn, R.W., Emmert, G.A.,
Gordinier, M., Hong, S., Kesner, J., Klein, A., Kulcinski, G.L.,
Lao, L., Larsen, E., Mai, L.P., Mau, T.K., Maynard, C.W.,
Michaelson, P., O¹Donnell, G., Ortman, M., Ragheb, M.,
Schrarer, J., Schluderberg, D.C., Sviatoslavsky, I.N.,
Sze, D.K., Thornton, T., Vogelsang, W.F., Wilkes, P.,
Willimas J., Wu, T., Wrazel, J., and Young, W.C., "NUMAK
A Tokomak Reactor Design Study", March 1979, UWFDM 330.
23.
Badger, B., Kulcinski, G.L., Lao, L.L., Larbalestier, D.C.,
Larsen, E., Mai, L.P., Beyer, J., Callen, J.D., Conn, R.W.,
Emmert, G.A., Grotz, S., Hong, S., Kesner, J., Mau, T.K.,
Maynard, C.W., Ojalvo, I., Okula, K., Ortman, M., Perry, R.T,
Santarius, J., Schrarer, J., Shaing, K., Sviatoslavsky, I.N.,
Sze, D.K., Vogelsang, W.F., White, A., and Wilkes, P.,
"Preliminary Information on the University of Wisconsin Tandem
Mirror Reactor Design", November 1979, UWFDM 325.
22.
Thornton, T.A., Schluderberg, D.C., Zenz, F.A., and Sze, D.K.,
"Research in Microsphere Fabrication and Coolant Loop Technology for
Lithium Oxide Moving Bed Fusion Power Plant", First Topical Meeting
in Fusion Reactor Materials, Bal Harbour, Florida, January 1979.
21.
Sze, D.K., Schluderberg, D.C., "Load-Leveling Considerations
for a Pulsed Fusion Reactor", Trans. Am. Nucl. Soc. 302 68, 1978.
20.
Sze, D.K., "Blanket and Power Conversion System of NUWMAK",
Symposium on Fusion Technology, September 1978, Padova, Italy.
19.
Sze, D.K., et al., "A BWTR (Boiling Water Tokamak Reactor) Concept",
Proceedings of the Third Topical Meeting on the Technology of Controlled
Nuclear Fusion", May 1978, Santa Fe, New Mexico.
18.
Sze, D.K., Sviatoslavsky, I.N., Cheng, E.T., and Avci, H.I.,
"Thermal, Mechanical and Neutronic Design Considerations for a
Graphite Structure Li2O Cooled Blanket", Seventh Symposium on
Engineering Problems of Fusion Research, October, 1977, Knoxville, Tennessee.
17.
Cheng, E.T., Sung, T.Y., and Sze, D.K., "Neutronics
Studies of the Gas-Carried Lithium Oxide Cooling-Breeding Fusion
Reactor Blanket and Shield", Nuclear Technology, 34, 3, 362, June 1977.
16.
Sze, D.K., Sviatoslavsky, I.N., and Schluderberg, D.C.,
"Gravitational Circulated Solid Blanket Design for a Tokamak
Fusion Reactor", Proceedings of the Second Topical Meeting on
the Technology of Controlled Nuclear Fusion, September 1976, Richland, Washington.
15.
Sviatoslavsky, I.N. and Sze, D.K., "Therma Hydraulic and
Mechanical Design of the Blanket for UWMAK-II", Trans. Am. Nucl.
Soc., 39, 1, 73, 1976.
14.
Larsen, E,M., Clemmer, R.G., and Sze, D.K., "Tritium
Recovery and Handling in a Gas-Carried Li2O CTR Blanket", Trans.
Am. Nucl. Soc. 23, 56, June 1976.
13.
Cheng,.E.T., Sung, T.Y., and Sze, D.K., "Neutronics Studies
of the Gas-Carried Li2O Cooling/Breeding Fusion Reactor Blanket and
Shield", Trans. Am. Nucl. Soc. 23, 36, June 1976.
12.
Conn, R.W., et al., "Major Design Features of the Conceptual D-T
Tokamak Power Reactor, UWMAK-II", Fifth IAGA Conference on Plasma
Physics and Controlled Nuclear Fusion Research, Tokyo, Japan, 1974.
11.
Stewart, W.E., and Sze, D.K., "Transport Problems in
Lithium Cooling of Tokamak Reactors", AICHE Symposium Series, 168 (1977).
10.
Sze, D.K., Larsen, E.M., Cheng, E.T., and Clemmer, R.G.,
"A Gas-Carried Li2O Cooling/Breeding Fusion Reactor Blanket Concept",
Trans. Am. Nucl. Soc. 22, 21 (1975).
9.
Kulcinski, G.L., Conn, R.W., Avci, H.I., and Sze, D.K.,
"Protection of CTR Metallic First Walls by Neutron Spectral Shifting",
Trans. Am. Nucl. Soc. 21, 50 (1975).
8.
Sze, D.K. and Conn, R.W., "Heat Transfer and Neutronics of
Partial ISSEC and ISSEC Blanket Designs", Trans. Am. Nucl. Soc. 21, 34 (1975).
7.
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