9/13/2005
CURRICULUM VITAE
Ralph W. Moir
Personal
Information
Born Bellingham, Washington, January
21, 1940
Vallecitos Research Associates: 607 E. Vallecitos Rd.
Livermore, CA 94550-9637
(925) 447-8804 Phone/Fax
RMoir@Pacbell.net
Lawrence
Livermore National Laboratory
P.O. Box 808, L-637
Livermore, CA 94551-0808
(925) 422-9808
FAX (925) 424-6401
Moir1@LLNL.GOV
Three children
Education
B.S. 1962--Engineering Physics,
University of California, Berkeley
Sc.D. 1967--Nuclear Engineering, MIT,
Cambridge, Mass.
Post graduate studies on fusion,
1967-68 at Fontenay-Aux-Roses, France
Summer 1961 Richmond Field Station, University of California, Boiling Water
Reactor Safety Experiments
Summer 1962 Lawrence Livermore Laboratory, mechanical engineer at the swimming
pool reactor
Summer 1964 Lawrence Livermore Laboratory, plasma physicist, fusion research,
Baseball coil design, TIBRO orbit code
1968 to present Lawrence Livermore Laboratory, plasma physicist, associate program
leader for Hybrid Reactor Technology, Fusion Reactor Technology and Conceptual
Design Program, Group Leader; Fusion Research and Development, specialist in
fusion reactor studies and development of direct energy conversion
1989 to 2000 Project leader for IFE Power Production-The HYLIFE-II study
1/30/2000 retired
2000 to present Research on magnetic and inertial fusion energy power plant technology
and molten salt fission power plant on thorium cycle
Professional Associations, Societies and Honors
Registered
Professional Nuclear Engineer in the State of California, Registration number
NU782.
American
Physical Society, Fellow 1981, Plasma Physics Division
American
Nuclear Society, Fellow 1989, Fusion Energy Division, Chairman June 1993 to
June 1994.
American
Association for the Advancement of Science
Fusion
Power Associates
Others Activities
Society
of Sigma Xi
Joliot
Curie Fellowship 1967-1968
Atomic
Energy Commission Fellowship, 1962-1966
Board
of Directors of Interfaith Housing (for Elderly Low Income) (1984 to present);
VP 89-90, Pres. 91-94
Board
of Directors of Batzer Vacuum Technology Associates, Inc. (1987 to 1993)
Associate
Editor of Journal of Fusion Energy 1984 to 1993
Eagle
Scout
Member of World Future Society, Negative Population Growth
Society, Zero Population Growth Society, American for Energy Independence,
Americans For Nuclear Energy, Scientists and Engineers for Secure Energy
PUBLICATIONS
1. R. W. Moir and L. C. Pittenger,
"Baseball Fields", Lawrence Livermore Laboratory, Livermore, CA,
UCID-4750 (1964).
2. R. W. Moir, "A New Magnetic Well
Configuration, Importance of the Mirror Ratio and Electrostatic Containment of
Warm Plasma", Euratom Report, EUR-CEA-FC-496 (1968).
3. R. W. Moir and R. F. Post,
"Yin-Yang Minimum--B Magnetic Field Coil", Nuclear Fusion, 9,
253 (1969).
4. R. W. Moir, "Warm Plasma
Stabilization of the Convective Loss Cone Mode", Plasma Phys., 11,
169 (1969).
5. R. W. Moir and C. E. Taylor,
"Magnets for Open-Ended Fusion Reactor", In Energy 70, Proceedings of
the 5th Intersociety Energy Conversion Engineering Conference, Las Vegas,
Nevada, Sept. 21-25, 1970, Vol. 1, p. 80, American Nuclear Society, Hinsdale,
IL, 1970.
6. G. W. Hamilton and R. W. Moir,
"Conditions for Landau Damping and Wave Reflections in Open-Ended Magnetic
Well Plasmas", Lawrence Livermore Laboratory, Livermore, CA, UCRL-50900
(1970).
7. R. W. Moir, W. L. Barr and R. F. Post,
"Experimental Results on Electrostatic Stoppering", Phys. Fluids,
14, 2531 (1971).
8. R. W. Moir and L. M. Lidsky,
"Diffusion Resulting from Nonadiabatic Scattering on a Helically Perturbed
Field in a Torus", Plasma Physics, 13, 159 (1971).
9. R. W. Moir and C. E. Taylor,
"Magnets for Open-Ended Fusion Reactors, Technology of Controlled
Thermonuclear Fusion Experiments and the Engineering Aspects of Fusion
Reactors", CONF-721111, Conference held at Austin, Texas, Nov. 20-22,
1972.
11. W. L. Barr, et al., "A Preliminary
Engineering Design of a Venetian Blind Direct Energy Converter for Fusion
Reactors", IEEE Transactions of Plasma Science PS-2, 71 (1974).
12. R. W. Moir, "Physics of Mirror
Reactors and Devices", J. Nucl. Materials, 53, 66 (1974).
13. T. H.. Batzer, et. al., "Conceptual
Design of a Mirror Reactor for a Fusion Engineering Research Facilities
(FERF)", Lawrence Livermore Laboratory, Livermore, CA, UCRL-51617 (1974)
14. R. W. Moir and W. L. Barr,
"Experimental Results on the Two-Stage Venetian-Blind, Direct Energy
Converter", Lawrence Livermore Laboratory, Livermore, CA, UCID-16429
(1974).
15. R. W. Moir, "A Review of Direct
Energy Conversion: Experimental Results and Reactor Applications",
Proceedings of the First Topical Meeting on the Technology of Controlled
Nuclear Fusion, April 16-18, 1974, San Diego, Vol. 1, 432 (1974).
16. R. W. Moir, W. L. Barr and G. H. Miley,
"Surface Requirements for Electrostatic Direct Energy Converters", Journal
of Nuclear Materials, 53, 86 (1974).
17. R. W. Moir, "Conceptual Design
Consideration for D-T Mirror Reactors With and Without Fission Blanket",
Proceedings of the First Topical Meeting on the Technology of Controlled
Nuclear Fusion, April 16-18, 1974, p 373. UCRL-75596.
18. R. W. Werner et al., "The
Interesting Possibilities of Fusion-Fission," Proceedings of the Fifth
Conference on Plasma Physics and Controlled Nuclear Fusion Research, Lawrence
Livermore National Laboratory, Livermore, CA, UCRL-75527 (1974).
19. J. Hovingh and R. W. Moir,
"Efficiency of Injection of Neutral Beams into Thermonuclear
Reactors", Nuclear Fusion, 14, 629 (1974).
20. W. L. Barr, B. C. Howard, and R. W. Moir,
"Direct Converter Efficiency with a 100:1 Expander", Lawrence
Livermore Laboratory, Livermore, CA, UCID-16585 (1974).
21. R. W. Moir, et al., "Progress on the
Conceptual Design for a Mirror Hybrid Fusion-Fission Reactor", Lawrence
Livermore Laboratory, Livermore, CA, UCRL-51797 (1975)
22. G. A. Carlson and R. W. Moir,
"Mirror Fusion Reactor Study", Lawrence Livermore Laboratory,
Livermore, CA, UCRL-76985 (1975).
23. R. P. Freis and R. W. Moir,
"Properties Particle Orbits in an Average Minimum B Mirror
Configuration", Lawrence Livermore Laboratory, Livermore, CA, UCID-16707
(1975).
24. G. H. Miley and R. W. Moir, “The Effect
of Radiation Blistering on Voltage Holding,” Proceedings of the Sixth Symposium
on Engineering Problems of Fusion Research, Nov. 18-21, 1975, San Diego,
p172-177.
25. D. J. Bender, W. L. Barr, and R. W. Moir,
“Performance Analysis of In-Line Direct Converters for Neutral Beam Sources,”
Proceedings of the Sixth Symposium on Engineering Problems of Fusion Research,
Nov. 18-21, 1975, San Diego, p184-190.
26. R. W. Moir, "Mirror Reactor
Studies", Proceedings of the Sixth Plasma Physics and Controlled Nuclear
Fusion Research, Vol. III, p. 223, Berchtesgaden, Germany, Oct. 6-13, 1976.
27. K. D. Marx, R. W. Moir, W. L. Barr and C.
E. McDowell, Monte Carlo Calculation of Collisional Effects in a
Mirror-Confined Plasma, Sherwood Theory Meeting, Madison, Wisconsin, 1976.
28. K. D. Marx, "Trapping Rates and Loss
Rates for Electrons in Electrostatically Plugged Cusps", Bull. Am.
Phys. Soc. (1976). collaborative work.
29. W. L. Barr and R. W. Moir, "Beam
Direct Conversion of Neutral Beam Injectors", IEEE Meeting, Austin, Texas,
May 24-26, 1976.
30. R. W. Moir "Surface Bombardment
Rates for Mirror Fusion Reactor Designs", Journal of Nuclear Materials,
63, 21 (1976).
31. T. J. Dolan and R. W. Moir,
"Electrostatic Plugging of Cusps", Bull. Am. Phys. Soc.
(1976).
32. G. A. Carlson, J. N. Doggett and R. W.
Moir, "Progress on the Reference Mirror Fusion Reactor Design",
Lawrence Livermore Laboratory, Livermore, CA, UCID-17022 (1976).
33. R. W. Moir, "Direct Energy
Conversion in Fusion Reactors", Chapter 5-150 in Energy Technology
Handbook, Ed. D. M. Considine, McGraw-Hill, New York, 1977.
34. R. W. Moir, T. J. Dolan, and W. L. Barr,
“Design of an Electrostatic End-Plugged Plasma-Confinement Device,” Proceedings
of the Seventh Symposium on Engineering Problems of Fusion Research, Oct.
25-28, 1977, Knoxville, Vol. 1, p138-143.
35. W. L. Barr, J. N. Doggett, G. W.
Hamilton, J. D. Kinney, and R. W. Moir, “Engineering of Beam Direct Conversion
for a 120-kV, 1-MW Ion Beam,” Proceedings of the Seventh Symposium on
Engineering Problems of Fusion Research, Oct. 25-28, 1977, Knoxville, Vol. 1,
p308-314.
36. R. W. Moir and W. L. Barr,
"Experimental and Computational Results on Direct Energy Conversion for
Mirror Reactors", Nuclear Fusion, 17, 1015 (1977).
37. R. W. Moir et al., "Preliminary
Design Study of the Tandem Mirror Reactor (TMR)," Lawrence Livermore
National Laboratory, Livermore, CA, UCRL-52302(1977).
38. R. W. Moir, editor, "Standard Mirror
Fusion Reactor Design Study," Lawrence Livermore National Laboratory,
Livermore, CA, UCID-17644 (1978).
39. G. A. Carlson and R. W. Moir,
"Mirror Fusion Reactors” proceedings
of the Thirteenth Intersociety Energy Conversion Engineering Conference, vol. 2
p1343, Aug. 20-25, 1978-San Diego, Ca., Lawrence Livermore Laboratory,
Livermore, CA, UCRL-81149 (1978).
40. R. W. Moir, "Mirror Hybrid
Reactors", International School of Fusion Reactor Technology, Erice
(Sicily) Italy September 18-26, 1978.
41. R. W. Moir, Editor, "Interim Report
on the Tandem Mirror Hybrid Design Study", Lawrence Livermore National
Laboratory, Livermore, CA, UCID-18078 (1979).
42. R. W. Moir, et al., "Tandem Mirror
Hybrid Reactor Design Annual Report", Lawrence Livermore National
Laboratory, Livermore, CA, UCID-18808 (1980).
43. R. W. Moir, "Hybrid Reactors",
Proceedings of the 11th Symposium on Fusion Technology, p111, University of
Oxford, UK, Sept. 15-19, 1980, also Lawrence Livermore Laboratory, Livermore,
CA, UCRL-84826 (1980).
44. R. W. Moir, “Status Report on the Fusion
Breeder,” 3rd Miami International Conference on Alternate Energy Sources,
15-17, 1980, Miami Beach, Florida, UCRL-84436 (1980).
45. A. Blum, et al., "Design Study of a
120-keV, 3He Neutral Beam Injector", J. Fusion Energy, 1,
69 (1981).
46. R. W. Moir, "The Fusion-Fission Fuel
Factory, Chapter 15, p. 411-451, in Fusion, Vol. 1 Part B, edited by E.
Teller, Academic Press, New York (1981).
47. J. D. Lee and R. W. Moir,
"Fission-Suppressed Blanket for Fissile Fuel Breeding Fusion
Reactors", J. Fusion Energy, 1, 299 (1981).
48. W. L. Barr and R. W. Moir, "Measured
and Projected Performance of Plasma Direct Converters," Proceedings of the
IEEE-9th Symposium of Engineering Problems of Fusion Research, Palmer House,
Chicago, Illinois Oct. 26-29, 1981, p499-502, Lawrence Livermore National
Laboratory, Livermore, CA, UCRL-86026 Preprint.
49. R. W. Moir, C. E. Taylor, and M. A.
Hoffman, "Concept for a High-Power Beam Dump", Nuclear Engineering
and Design, 68, 265 (1981).
50. R. W. Moir, "Mirror-Reactor
Studies", submitted to the Proceedings of the Institute of Electrical and
Electronics Engineers, Lawrence Livermore Laboratory, Livermore, CA, UCRL-85850
(1981).
51. R. W. Moir, "The Tandem Mirror Hybrid
Reactor", Nuclear Eng. and Design 63 375 (1981).
52. R. W. Moir, "Hybrid Reactors",
submitted to Jahrestagung Kerntechnik '81 24-26 March 1981, Deutsches Atomforum
Dusseldorf, Federal Republic of Germany, Lawrence Livermore Laboratory,
Livermore, CA, UCRL-84826, rev. 1 (1981).
53. R. W. Moir et al., "Engineering
Problems of Tandem Mirror Reactors", IEEE-9th Symposium of Engineering
Problems of Fusion Research, Oct. 26-29, 1981, p1967-1971, Lawrence Livermore
Laboratory, Livermore, CA, UCRL-86810 (1981).
54. R. W. Moir et al., "Engineering
Problems of The Fusion Breeder", IEEE-9th Symposium of Engineering
Problems of Fusion Research, Oct. 26-29, 1981, p1822-1834, Lawrence Livermore
Laboratory, Livermore, CA, UCRL-86810 (1981).
55. R. W. Moir, "Feasibility Study of a
Fission Suppressed Blanket for a Tandem Mirror Hybrid Reactor", IAEA
Technical Committee Meeting 3rd Technical Committee & Workshop on Fusion
Reactor Design & Technology Tokyo, Japan, Oct. 5-16, 1981, Lawrence
Livermore Laboratory, Livermore, CA, UCRL-86756 (1981).
56. D. H. Berwald, J. A. Maniscalco, J. D.
Lee, and R. W. Moir, “Fission Suppressed Tandem Mirror Hybrid Reactor Options,”
Proceedings of the Fourth Topical Meeting on the Technology of Controlled
Nuclear Fusion, October 14-17, 1980, King of Prussia, Pennsylvania pages
1465-1474.
57. J. D. Lee, et al., "Feasibility
Study of a Fission-Suppressed Tandem-Mirror Hybrid Reactor", Lawrence
Livermore National Laboratory, Livermore, CA, UCID-19327 (1982).
58. D. H. Berwald, et al., "Fission-Suppressed
Hybrid Reactor--The Fusion Breeder", Lawrence Livermore National
Laboratory, Livermore, CA, UCID-19648 (1982).
59 R. W. Moir, "The Fusion Breeder", submitted to the
National Science Foundation Policy Workshop, Washington DC, March 4-5, 1982,
Lawrence Livermore Laboratory, Livermore, CA, UCRL-87290 (1982).
60. W. L. Barr and R. W. Moir, "Test
Resulted on Plasma Direct Converters", Nuclear Technology/Fusion, 3,
98 (1983).
61. D. L. Smith, et al., "Blanket
Comparison and Selection Study-Final Report", ANL/FPP-84-1 (1984).
62. J. A. Maniscalco, et al., "The
Fusion Breeder-An Early Application of Nuclear Fusion", Fusion
Technology, 6, 584 (1984).
63. R. W. Moir, et al., "Helium-Cooled
Molten Salt Fusion Breeder", Lawrence Livermore National Laboratory,
Livermore, CA, UCID-20153 (1984).
64. R. W. Moir, et al., "Feasibility
Study of a Fission-Suppressed Tokamak Fusion Breeder", Lawrence Livermore
National Laboratory, Livermore, CA, UCID-20154 (1984).
65. J. M. Beeston, L. G. Miller, E. L. Wood,
and R. W. Moir, "Comparison of Compression Properties and Swelling of
Beryllium Irradiated at Various Temperatures", J. Nucl. Materials,
Vol. 122 and 123, p. 802-809 (1984).
66. R. W. Moir, "Fissile Fuel From
Fusion" in Energy and Technology Review, Lawrence Livermore
National Laboratory, Livermore, CA, UCRL-52000-85-1 (1985).
67. G. F. Chapline and R. W. Moir, "Some
Thoughts on the Production of Muons for Fusion Catalysis," J. Fusion
Energy, 5 191 (1986).
68. R. W. Moir, et al., "Helium-Cooled,
Flibe Breeder, Beryllium Multiplier Blanket", Fusion Technology 8
133(1985).
69. R. W. Moir, et al., "Design of a
Helium-Cooled Molten Salt Fusion Breeder", Fusion Technology, Vol.
8, No. 1 Part 2(A) 465 (1985).
70. M. G. Adamson, D. Calef, and R. W. Moir,
"Lithium Nitrate As a Fusion Reactor Coolant Fluid?: A Thermochemical
Assessment", J. of Fusion Energy, 5 247 (1986).
71. D. L. Jassby, et al., "Fast-Fission
Tokamak Breeder Reactors", Fusion Energy 5, 171 (1986).
72. R. W. Moir, et al. "Fusion-fission
hybrid studies in the United States of America." Fusion Reactor Design and
Technology 1986. Proceedings of the Fourth Technical Committee Meeting and
Workshop (STI-PUB-754). Held: Yalta, USSR, 26 May- 6 June 1986. (Austria:
IAEA-TC-392.3/33, 1987. p. 527-48 vol. 1).
73. R. W. Moir and J. D. Lee,
"Helium-cooled , FLiBe-Breeder, Beryllium-Multiplier Blanket for
Minimars," Fusion Technology 10 619(1986).
74. R. W. Moir and G. F. Chapline,
"Production of Muons for Fusion Catalysis in a Magnetic Mirror
Configuration," Proc. of 4th International Conference on "Emerging
Nuclear Energy Systems, June 30-July 4, 1986, Madrid. Ed. G. Velarde and E. Minguez (World Scientific
Publishing Co., Singapore, 1987), 185-190.
75. R. W. Moir, "Rotating Liquid Blanket
for a Toroidal Fusion Reactor", Fusion Engineering and Design 5
269 (1987).
76. R. F. Bourque, K. R. Schultz and R. W.
Moir, a brochure: "Fusion In Our Future", 1987.
77. R. W. Moir, et al., "Study of a
Magnetic Fusion Production Reactor", A series of eight articles on tritium
production. J. Fusion Energy, 5, 255-331 (1986) and 6,
3-88 (1987).
78. D. H. Berwald, et al., "Updated
Reference Design of a Liquid Metal Cooled Tandem Mirror Fusion Breeder", Fusion
Technology 12 30 (1987).
79. J. E. Holzrichter, et al.,
"Applications of High Temperature Superconductors", Lawrence
Livermore Laboratory, Livermore, CA, UCRL-53855 (1988).
80. R. W. Moir, "Concept of a Blanket
First Wall Supported by Radial Tubes," Fusion Engineering and Design
5 379 (1988).
81. R. W. Moir, "Beryllium Usage in
Fusion Blankets and Beryllium Data Needs," Lawrence Livermore Laboratory,
Livermore, CA, UCRL-97426 (1988).
82. C. J. Call and R. W. Moir, "A Novel
Fusion Power Concept Based on Molten-Salt Technology: PACER Revisited," Nuclear
Science and Engineering 104 364 (1990).
83. R. W. Moir, "Pacer Revisited," Fusion
Technology 15 1114 (1989).
84. R. W. White, W. L. Barr, and R. W. Moir,
"DART: A Simulation Code for Charged Particle Beams," UCID-21330-Rev.
1 (1989).
85. R. W. Moir, "Rotating Liquid Blanket
with No First Wall for Fusion Reactor," Fusion Technology 15
674 (1989).
86. R. W. Moir, “Introduction to ‘Design for
a High Power-Density Astron Reactor’ by N. C. Christofilos,” J. Fusion
Energy 8 93-95 (1989).
87. R. W. Moir, "A Review of Inertial
Confinement Fusion (ICF), ICF Reactors, and the HYLIFE-II Concept Using Liquid
Flibe," Lawrence Livermore Laboratory, Livermore, CA, UCID-21748 (1989).
88. D. L. Correll and R. W. Moir, "The
Role of Lawrence Livermore National Laboratory in the Development of
Fusion," Revue Generale Nucleaire, No. 1 p78 (Jan.-Feb., 1991).
89. W. S. Neef , R. W. Moir, E. K. Opperman
and M. L. Hamilton, "Development of Pressurized Tube Specimen For Creep
Testing of Beryllium", PNL -SA-18937, also Semiannual Report 1991,
DOE-ER/0313/9. See also W. S. Neef
UCRL-ID-104441 (1990).
90. J. H. Pitts, R. O. Bangerter, D. D. Ho,
R. W. Moir and M. Tabak, "Cascade and HYLIFE ICF Reactor Concept
Revisions," submitted to 16th Symposium on Fusion Technology London Sept.
3-7, 1990.
91. R. W. Moir, "HYLIFE-II Inertial
Confinement Fusion Reactor Design", Fusion Technology 19 617 (1991).
93. R. W. Moir, "HYLIFE-II Inertial
Confinement Fusion Power Plant Design," Particle Accelerators, 37-38
467 (1992)
94. R. W. Moir, "Heavy Ion Beam and
Reactor Chamber Interface Design," Proceedings of the International
Symposium on Heavy Ion Inertial Particle Accelerators, 37-38 459
(1992).
95. R. W. Moir et al., "HYLIFE-II Progress Report," UCRL-ID-21816 (1991).
96. A. Szoke and R. W. Moir, "A
Practical Route to Fusion Power," Technology Review, 94 p 20- 27 (July
1991).
97. A. Szoke and R. W. Moir, "A
Realistic, Gradual and Economical Approach to Fusion Power," Fusion
Technology 20 1012 (1991).
98. T. H. Batzer, D. D. Lang, and R. W. Moir,
"Large all-metal-sealed, vacuum gate valves for fusion applications,"
J. Vac. Sc. Technol. A 10 3579 (1992).
99. R. W. Moir, "HYLIFE-II Inertial
Fusion Energy Power Plant Design," Fusion Technology 21 1475
(1992).
100. R. W. Moir, J. H. Hammer, C. W. Hartman, R.
L. Leber, B. G. Logan, R. W. Petzoldt, M. Tabak, and M. T. Tobin,
"Inertial Fusion Energy Power Plant Design Using the Compact Torus
Accelerator: HYLIFE-CT," Fusion Technology 21 1492 (1992).
101. S. E. K. Mattingly and Ralph W. Moir,
"Method to Prevent Ejecta from Damaging the Compact Torus Accelerator
Driver of an Inertial Fusion Energy Power Plant," Lawrence Livermore
Laboratory, Livermore, CA, UCRL-ID-112569 (1992).
102. R. W. Moir, "HYLIFE-II Inertial Fusion
Energy Power Plant Design," ICF Quarterly Report, Vol. 2, No. 3 April-June
1992 p 139, Lawrence Livermore Laboratory, Livermore, CA, UCRL-LR-105821-92-3.
103. R. W. Petzoldt and R. W. Moir, “Membrane
Support of Accelerated Fuel Capsules for Inertial Fusion Energy Reactors,”
Lawrence Livermore Laboratory, Livermore, CA, UCRL-ID-114020 (1993).
104. R. W. Moir, R. L. Bieri, X. M. Chen, T. J. Dolan, M. A. Hoffman, P.
A. House, R. L. Leber, J. D. Lee, Y. T.
Lee, J. C. Liu, G. R. Longhurst, W. R.
Meier, P. F. Peterson, R. W. Petzoldt,
V. E. Schrock, M. T. Tobin, W.
H. Williams, "HYLIFE-II: A Molten
Salt Inertial Fusion Energy Power Plant Design-Final Report," Fusion
Technology 25 (1994) 5-25.
105. S. Sahin, R. W. Moir, J. D. Lee, S. Unalan,
“Neutronic Investigation of IFE Blankets for HYLIFE-II and MHD Applications,”
UCRL-JC-109527 (1993), Fusion Technology 25 (1994) 388-397.
106. S. Sahin, R. W. Moir, and S. Unalan,
“Neutronic Investigation of a Power Plant Using Peaceful Nuclear Explosives,”
Lawrence Livermore Laboratory, Livermore, CA, UCRL-JC-116976 (1994), Fusion
Technology 26 (1994) 1311-1325.
107. R. W. Moir, “Direct Energy Conversion Beam
Dump for a 1.6-MeV Neutral Beam For the International Thermonuclear
Experimental Reactor,” Fusion Technology 25 129-136 (1994).
108. R. W. Moir, “Advantages of a Liquid Wall
Used in a Fusion Power Plant,” UCRL-JC-117123, submitted to Nature (April 1,
1994)-not accepted.
109. R. W. Moir, “The Logic Behind Thick,
Liquid-Walled, Fusion Concepts,” UCRL-JC-115748, submitted to the Third
International Symposium on Nuclear Technology, UCLA, June 27- July 1, 1994
(April 15, 1994), Nuclear Engineering and Design 29 (1995) 34-42.
110. Ralph W. Moir, ”Improvements to the
HYLIFE-II inertial fusion power plant design,” Lawrence Livermore National
Laboratory Livermore, California, Paper E048 UCRL-JC-115964 SUM (April 19,
1994), Submitted to 11th Topical Meeting on the Technology of Fusion Energy,
June 19-23, 1994 New Orleans, Fusion Technology 26 1169-1177
(1994).
111. R. W. Moir, R. L. Bieri, X. M. Chen, T. J.
Dolan, M. A. Hoffman, P. A. House, R. L. Leber, J. D. Lee, Y. T. Lee, J. C.
Liu, G. R. Longhurst, W. R. Meier, P. F. Peterson, R. W. Petzholdt, V. E.
Schrock, M. T. Tobin, and W. H. Williams, “HYLIFE-II, An Approach to
Long-lived, First-Wall Component for Inertial Fusion Power Plants,” Lawrence
Livermore National Laboratory, Livermore, California, UCRL-JC-117115,
proceedings of the 15th International Conference on Plasma Physics and
Controlled Nuclear Fusion Research, held by the International Atomic Energy
Agency in Seville, Spain, 26 Sept.-1 Oct. 1994, IAEA-F1-CN-60/F-7. Plasma
Physics and Controlled Nuclear Fusion Research, Vol. 2 of 4 volumes, (1995)
673-680.
112. R. W. Petzoldt and R. W. Moir, “Target
Injection Methods for Inertial Fusion Energy,” Submitted to 11th Topical
Meeting on the Technology of Fusion Energy, June 19-23, 1994 New Orleans, Fusion
Technology 26 (1994) 896-905.
113. B. G. Logan, R. W. Moir, and M. A. Hoffman,
“Requirements for Low Cost Electricity and Hydrogen Fuel Production from
Multi-Unit Inertial Fusion Energy Plants with a Shared Driver and Target
Factory,” Fusion Technology, 28 (1995) 1674-1696.
114. C. W. Hartman, J. L. Eddleman, R. W. Moir,
U. Shumlak, “A DT Fusion Reactor Based on the Flow–Through Z–Pinch,” Submitted
to 11th Topical Meeting on the Technology of Fusion Energy, June 19-23, 1994
New Orleans, Fusion Technology 26 (1994) 1203-1206.
115. Ralph W. Moir, “The High-Yield Lithium-Injection Fusion-Energy (HYLIFE)-II
inertial fusion energy (IFE) power plant concept and
implications for IFE,” Lawrence Livermore Laboratory, Livermore, CA,
UCRL-JC-119070 (1994), Physics of Plasmas 2 (6) 2447-2452 (1995).
116. R. W. Moir, “IFE Power Plant Requirements
on the Focused Beam, the Target, and the Chamber: the HYLIFE-II Example”,
submitted to Workshop on Intense Ion Beams and Target Physics, 13-17 March
1995, Les Houches, France, Lawrence Livermore Laboratory, Livermore, CA,
UCRL-JC-119612abs (1995).
117. R. W. Petzoldt and R. W. Moir, “Membrane
Support of Accelerated Fuel Capsules for Inertial Fusion Energy,” Lawrence
Livermore Laboratory, Livermore, CA, UCRL-JC-118850 (1995), Fusion
Technology 30 (1996) 73-82.
118. W. J.
Hogan, Sci. Editor, Energy from Inertial Fusion, STI/PUB/944, International
Atomic Energy Agency, Vienna, Austria (1995), section 4.4 Ion beam
driver-reactor chamber interfaces 328-340; section 8.2 Uses of IFE technology
involving implosions 424-440.
119. R. W. Petzoldt and R. W. Moir, “Target Injection, Tracking, and Beam Pointing Requirements and Feasibility Considerations for Inertial Fusion Energy, Lawrence Livermore Laboratory, Livermore, CA, UCRL-JC-120880 (1995), submitted to Fusion Engineering and Design.
120. Ralph W. Moir, “Liquid Wall IFE Power
Plants,” UCRL-JC-121588 Abs, International Symposium on Heavy Ion Inertial
Fusion, Sept. 6-9, 1995, Princeton, Fusion Engineering and Design 32-33 (1996)
93-104.
121. Ronald W. Petzoldt and Ralph W. Moir,
“Target Injection and Tracking for Inertial Fusion Energy,” UCRL-JC-122017,
International Symposium on Heavy Ion
Inertial Fusion, Sept. 6-9, 1995, Princeton, Fusion Engineering and Design
32-33 (1996) 113-121.
122. B. G. Logan, L. J. Perkins, R. W. Moir and
D. D. Ryutov, “The need for research and development in fusion: economical
energy for a sustainable future with low environmental impact,” Fusion
Technology, 28 (1995)
236-239.
123. R. W. Moir, “IFE Power Plant Design
Strategy,” Fusion Technology 30 (1996) 1613-1623.
124. R. W. Moir, “Liquid first walls for
magnetic fusion energy,” Lawrence Livermore Laboratory, Livermore, CA,
UCRL-ID-123902 (1996).
125. R. W. Moir, “Liquid First Walls for
Magnetic Fusion Energy Configurations,” Lawrence Livermore Laboratory, Livermore,
CA, UCRL-JC-125098, Nuclear Fusion 37 (1997) 557-566.
126. Sumer Sahin, R. W. Moir, A Sahinaslan and
H. M. Sahin, “Radiation damage in liquid-protected first-wall materials for
IFE-reactors,” Fusion Technology, 30 (1996) 1027-1035.
127. Wayne R. Meier, Ralph W. Moir, and
Mohamed A. Abdou, “Chamber technology concepts for inertial fusion energy—three
recent examples,” Lawrence Livermore Laboratory, Livermore, CA, UCRL-JC-125147
(1997), ISFNT-4, April 6-11, 1997, Tokyo. Fusion Engineering and Design 42
(1998) 537-548.
128. H. Moriyama, A. Sagara, S. Tanaka, R. W.
Moir, D. K. Sze, “Molten salts in fusion nuclear technology,” abstract
submitted to ISFNT-4, April 6-11, 1997, Tokyo. Fusion Engineering and Design
39-40 (1998) 627-637.
129. R. O. Bangerter, J. J. Barnard, A. Faltens, A. Friedman, J. Kwan, E. P. Lee, B. G. Logan, W. R. Meier, and R. W. Moir, “ The Inertial Fusion Energy Program in the US,” abstract submitted to ISFNT-4, April 6-11, 1997, Tokyo. Paper not written.
130. R. W.
Moir, “Protection of final optics with cryogenic liquid droplets, 13th
International conference on laser interaction and related plasma phenomenon,
Monterey, CA April 1997. Talk given; paper not written.
131. R. W. Moir, “Laser IFE Power Plant Options,” poster for IEEE meeting in Oct. 1997, San Diego. Poster presented; paper not written.
132. R. W. Moir, “IFE Reactor Perspective on Material Needs,” FESAC Review of the Fusion Materials Program, Westinghouse Science and Technology Center, Pittsburgh, March 2-3, 1998.
133. R. W.
Moir, “Inertial Fusion Energy Power Plants Based on Laser or Ion Beams,”
Proceedings of The Ninth International Conference on Emerging Nuclear Energy
Systems (ICENES-9), Tel-Aviv, Israel, June 28-July 2, 1998. Lawrence Livermore
Laboratory, Livermore, CA, UCRL-JC-129241 (1998).
134. Letter to Science commenting on Rostoker’s,
“Colliding beam fusion reactor,” article (1998), Science 278 (1997)
2033.
135. M. D. Lowenthal, E. Greenspan, R. Moir, W.
E. Kastenberg, T. K. Fowler, “Industrial ecology for inertial fusion energy:
selection of high-Z material for HYLIFE-II targets,” Fusion Technology 34
(1998) 619-628.
136. R.F. Mattas et al., “U.S. Assessment of
Advanced Limiter-divertor Plasma-facing Systems (ALPS) -Design, Analysis, and
R&D Needs,” to be published in Fusion Technology (1998).
137. T.K.
Fowler, D. D. Hua, E. B. Hooper, R.W. Moir, and L. D. Pearlstein, “Wall-
Confined, High-beta Spheromak,” UCRL-130151, U.S. Japan Workshop - Physics base
of DHe3 fusion, Seattle, WA, March 18-20, 1998. Comments on Plasma Phys. And
Controlled Fusion 1 Part C (1999) 83-98.
138. R. W. Moir, “Grazing incidence liquid metal
mirrors (GILMM) for radiation hardened final optics for laser inertial fusion
energy power plants,” The 5th International Symposium on Fusion
Nuclear Technology, September 19-24, 1999, Rome, Italy. Lawrence Livermore
Laboratory, Livermore, CA, UCRL-JC-132875 (June 18, 1999), Fusion
Engineering and Design 51-52 (2000) 1123-1130.
139. R. W. Moir, K. Gulec, B. Nelson, M.
Ohnishi, and T. Rognlien , “Liquid walls for MFE : Concepts and status of FRC,
ST, Spheromak,” Submitted to the 5th International Symposium on
Fusion Nuclear Technology, September 19-24, 1999, Rome, Italy. Lawrence
Livermore Laboratory, Livermore, CA, UCRL-JC-132875 Abs. (1/21/99). Combined into paper below:
140. K. Gulec, M. A. Abdou, R. W. Moir, N. B.
Morley, A. Ying, “Novel liquid blanket configuration and their hydrodynamic
analyses for innovative confinement concepts,” Submitted to the 5th
International Symposium on Fusion Nuclear Technology, September 19-24, 1999,
Rome, Italy. Fusion Engineering and Design 49-50 (2000) 567-576.
143. Ralph W. Moir, “Chamber, target and final
focus integrated design,” Heavy Ion Fusion International Symposium, March
13-17, 2000, in San Diego, USA. UCRL-JC-136793 (2000). Nuclear Instruments
and Methods in Physics Research A (2001). http://dx.doi.org/10.1016/S0168-9002(01)00025-0,
also www.osti.gov/servlets/purl/790913-IJYY4m/native/
144. R. W. Moir, R. H. Bulmer, K. Gulec, P. Fogarty, B. Nelson, M. Ohnishi, M. Rensink, T. D. Rognlien, J. F. Santarius, and D. K. Sze, “Thick liquid-walled, field-reversed configuration-magnetic fusion power plant,” Fusion Technology 39 (2001) 758-767. www.osti.gov/servlets/purl/15013268-ae0jy9/native/
145. R. W. Moir, M. Rensink, and T. D. Rognlien,
“EDGE-PLASMA ANALYSIS FOR LIQUID-WALL MFE CONCEPTS,” UCRl-JC-137801, 18th IAEA
Fusion Energy Conference, Sorrento, Italy, 4 - 10 October 2000.
www.osti.gov/servlets/purl/15006141-V2LtXb/native/
146. R. W. Moir, “Final optics protection in laser inertial fusion with cryogenic liquid droplets,” Lawrence Livermore Laboratory, Livermore, CA, UCRL-ID-140559 (2000). www.osti.gov/servlets/purl/15006438-GPyAkM/native/
147. R. W. Moir, “Flibe coolant cleanup and processing in the HYLIFE-II inertial fusion energy power plant,” UCRL-ID-143228 (2001). www.osti.gov/servlets/purl/15006180-1kse4O/native/
148. R. W. Moir, “Cost of electricity from
molten salt reactors (MSR),” Nuclear Technology 138 (2002) 93-95.
155. R. W. Moir and T. D.
Rognlien, “Axisymmetric tandem mirror magnetic fusion energy power plant with
thick liquid-walls,” Draft (2005)
1. Electromagnetic
Apparatus for Producing and Containing High Temperature Plasma (Yin-Yang
Magnet), #3,582,849, June 1, 1971, with R. F. Post.
2. Apparatus
for Conversion of High Temperature Plasma Energy Into Electrical Energy (EXB
Direct Converter), #3,668,065, June 6, 1972.
3. Energetic
Neutral Particle Injection System for Controlled Fusion Reactor, #3,713,967,
Jan. 30, 1973, with G. W. Hamilton, J. E. Osher, and R. F. Post.
4. Plasma
Energy to Electrical Converter (Venetian Blind Direct Converter) #3,816,771,
June 11, 1974.
5. Mirror Plasma Apparatus (Rotating liquid blanket with no solid first wall and a halo plasma gas pumping), #4,260,455, April 7, 1981.
INVENTION
DISCLOSURES
1. Pulse generator using hydrogen thyratrons, with
Offenberger and Lidsky, Dec. 199(6?)6
2. Linear Accelerator Type In-Line Direct
Converter, 1976, IL-5908.
3. Lithium Walls for Mirror Plasma Apparatus with
Blanket Plasma, 2/24/77, IL-6217.
4. Shielding of Mirror Plasma by ARC Discharge,
2/24/77, IL-6216.
5. High Power Beam Dump, 9/21/80, IL-6704 with
Clyde Taylor.
6. Fission Suppressed Blanket Using Solid Salt
Balls,, 9/11/80, IL-6744.
7. Radial Tube Reactor Blanket, 5/24/82, IL-6994.
8. Rotating Liquid Blanket for a Toroidal Fusion
Reactor, 1986, IL-7668.
9. Impermeable Wall for Charged Particle
Deposition in a Plasma Fusion Apparatus, 4/20/84, IL-7407, with William Barr.
10. Fusion Power from Peaceful Nuclear Explosions,
5/25/88, IL-8023.
11. Oscillating Liquid Flow in an ICF Reactor,
9/7/90, IL-8604, with Ron Petzoldt.
12. Pulsed Flow ICF Reactor, 9/26/90, IL-8610.
13. Fast Neutron Molten Fluid (Liquid) Fission
Power Plant Concept 4/6/1993, IL-9248.
14. A Neutron Attenuator to Protect Beam Ports for
Inertial Fusion Power Plants, 2/16/94, IL-9480.
15. A New Steam Generator Design for Molten Salt
Power Systems, 5/25/95, IL-9774.
16. Grazing Incidence Liquid Metal Mirror (GILMM),
May 4, 1998, IL-10343.
17. Beam Line Protection Vortex, with Palmer
House, March 11, 1999, IL-10506.
18 Heat transfer enhancement by droplet injection
for liquid walls for magnetic fusion energy, January 26, 2000, IL-10651.
19. Flat Plate Heat Exchanger with SiC barriers,
Oct. 10, 2003, IL-11272.
20. Enhanced heat transfer at the free surface of a rotating liquid by vortex pair injection, Oct. 10, 2003, IL-11273.