Curriculum Vitae

Personal

Born Bellingham, Washington, January 21, 1940
Three children, seven grandchildren

Vallecitos Molten Salt Research
607 E. Vallecitos Rd.
Livermore, CA 94550-9637
(925) 447-8804 Phone/Fax
ralph@ralphmoir.com

Lawrence Livermore National Laboratory
P.O. Box 808, L-637
Livermore, CA 94551-0808
(925) 422-9808
Moir1@LLNL.GOV

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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

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Work Experience

Summer 1961Richmond Field Station, University of California, Boiling Water Reactor Safety Experiments

Summer 1962Lawrence Livermore Laboratory, mechanical engineer at the swimming pool reactor

1967 and 1968Worked on the magnetic fusion project at Fontenay-aux-Roses, France

Summer 1964Lawrence Livermore Laboratory, plasma physicist, fusion research, Baseball coil design, TIBRO orbit code

1968 to presentLawrence 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 2000Project leader for IFE Power Production-The HYLIFE-II study

1/30/2000Retired

2000 to presentResearch on magnetic and inertial fusion energy power plant technology and molten salt fission power plant on
thorium cycle

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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.
Fusion Power Associates

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Other 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 2014); 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

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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.

10. R. W. Moir and W. L. Barr, “Venetian-Blind Direct Energy Converter for Fusion Reactors,” Nuclear Fusion, 13, 35-45 (1973).

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), Journal of Fusion Energy 2, 251-367 (1982).

60. W. L. Barr and R. W. Moir, “Test results on Plasma Direct Converters,” Nuclear Technology/Fusion, 3, 98 (1983).

61. R. W. Moir, et al., “Fusion breeder reactor design studies,” Nuclear Technology/Fusion 4 (1983) 589-598.

62. D. L. Smith, et al., “Blanket Comparison and Selection Study-Final Report,” ANL/FPP-84-1 (1984).

63. J. A. Maniscalco, et al., “The Fusion Breeder-An Early Application of Nuclear Fusion,” Fusion Technology, 6, 584 (1984).

64. R. W. Moir, et al., “Helium-Cooled Molten Salt Fusion Breeder,” Lawrence Livermore National Laboratory, Livermore, CA, UCID-20153 (1984).

65. R. W. Moir, et al., “Feasibility Study of a Fission-Suppressed Tokamak Fusion Breeder,” Lawrence Livermore National Laboratory, Livermore, CA, UCID-20154 (1984).

66. 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).

67. R. W. Moir, “Fissile Fuel From Fusion” in Energy and Technology Review, Lawrence Livermore National Laboratory, Livermore, CA, UCRL-52000-85-1 (1985).

68. G. F. Chapline and R. W. Moir, “Some Thoughts on the Production of Muons for Fusion Catalysis,” J. Fusion Energy, 5 191 (1986).

69. R. W. Moir, et al., “Helium-Cooled, Flibe Breeder, Beryllium Multiplier Blanket,” Fusion Technology 8 133 (1985).

70. 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).

71. 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).

72. D. L. Jassby, et al., “Fast-Fission Tokamak Breeder Reactors,” Fusion Energy 5, 171 (1986).

73. 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).

74. R. W. Moir and J. D. Lee, “Helium-cooled , FLiBe-Breeder, Beryllium-Multiplier Blanket for Minimars,” Fusion Technology 10 619 (1986).

75. 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.

76. R. W. Moir, “Rotating Liquid Blanket for a Toroidal Fusion Reactor,” Fusion Engineering and Design 5 269 (1987).

77. R. F. Bourque, K. R. Schultz and R. W. Moir, a brochure: “Fusion In Our Future”, 1987.

78. 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).

79. D. H. Berwald, et al., “Updated Reference Design of a Liquid Metal Cooled Tandem Mirror Fusion Breeder,” Fusion Technology 12 30 (1987).

80. J. E. Holzrichter, et al., “Applications of High Temperature Superconductors,” Lawrence Livermore Laboratory, Livermore, CA, UCRL-53855 (1988).

81. R. W. Moir, “Concept of a Blanket First Wall Supported by Radial Tubes,” Fusion Engineering and Design 5 379 (1988).

82. R. W. Moir, “Beryllium Usage in Fusion Blankets and Beryllium Data Needs,” Lawrence Livermore Laboratory, Livermore, CA, UCRL-97426 (1988).

83. C. J. Call and R. W. Moir, “A Novel Fusion Power Concept Based on Molten-Salt Technology: PACER Revisited,” Nuclear Science and Engineering 104 (1990).

84. R. W. Moir, “Pacer Revisited,” Fusion Technology 15 (March 1989).

85. R. W. White, W. L. Barr, and R. W. Moir, “DART: A Simulation Code for Charged Particle Beams,” UCID-21330-Rev. 1 (1989).

86. R. W. Moir, “Rotating Liquid Blanket with No First Wall for Fusion Reactor,” Fusion Technology 15 674 (1989).

87. R. W. Moir, “Introduction to ‘Design for a High Power-Density Astron Reactor’ by N. C. Christofilos,” J. Fusion Energy 8 93-95 (1989).

88. 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).

89. 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).

90. 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).

91. 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.

92. R. W. Moir, “HYLIFE-II Inertial Confinement Fusion Reactor Design,” Fusion Technology 19 617 (1991).

93. B. G. Logan, R. W. Moir, M. Tabak, R. L. Bieri, J. H. Hammer, C. W. Hartman, M. A. Hoffman, R. L. Leber, R. W. Petzoldt, M. T. Tobin, “Compact Torus Driven Inertial Confinement Fusion Power Plant HYLIFE-CT,” UCRL-ID-106403 (1991). SRD

94. R. W. Moir, “HYLIFE-II Inertial Confinement Fusion Power Plant Design,” Particle Accelerators, 37-38 467 (1992)

95. 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).

96. R. W. Moir et al., “HYLIFE-II Progress Report,” UCRL-ID-21816 (1991).

97. A. Szoke and R. W. Moir, “A Practical Route to Fusion Power,” Technology Review, 94 20- 27 (July 1991).

98. A. Szoke and R. W. Moir, “A Realistic, Gradual and Economical Approach to Fusion Power,” Fusion Technology 20 1012 (Dec 1991).

99. T. H. Batzer, D. D. Lang, and R. W. Moir, “Large, all-metal-sealed, vacuum gate valve for fusion application,” J. Vac. Sc. Technol. A 10 3579 (1992).

100. R. W. Moir, “HYLIFE-II Inertial Fusion Energy Power Plant Design,” Fusion Technology 21 1475 (1992).

101. 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).

102. 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).

103. 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.

104. 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).

105. 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.

106. 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.

107. 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 (Dec 1994) 1311-1325.

108. 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).

109. 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.

110. 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.

111. 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).

112. 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.

113. 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.

114. 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.

115. 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.

116. 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).

117. 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).

118. 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.

119. 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.

120. 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.

121. 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.

122. 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.

123. 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.

124. R. W. Moir, “IFE Power Plant Design Strategy,” Fusion Technology 30 (1996) 1613-1623.

125. R. W. Moir, “Liquid first walls for magnetic fusion energy,” Lawrence Livermore Laboratory, Livermore, CA, UCRL-ID-123902 (1996).

126. 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.

127. 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.

128. 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.

129. 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.

130. 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.

131. 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.

132. R. W. Moir, “Laser IFE Power Plant Options,” poster for IEEE meeting in Oct. 1997, San Diego. Poster presented; paper not written.

133. 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.

134. 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).

135. Letter to Science commenting on Rostoker’s, “Colliding beam fusion reactor,” article (1998), Science 278 (1997) 2033.

136. 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.

137. 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).

138. 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.

139. 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.

140. 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:

141. 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.

142. R. W. Moir, “Grazing incidence liquid metal mirrors (GILMM) as the final optics for laser inertial fusion energy power plants.” Lawrence Livermore Laboratory, Livermore, CA, UCRL-ID-134612 (June 18, 1999).

143. R. W. Moir, “Liquid walls for fusion reaction chambers,” Lawrence Livermore Laboratory, Livermore, CA, UCRL-JC-135743 (Sept 16, 1999), Comments on Plasma Physics and Controlled Fusion, Comments on Modern Physics, 2 (2000) 99-111.

144. 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/

145. 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/

146. 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/

147. 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/

148. 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/

149. R. W. Moir, “Cost of electricity from molten salt reactors (MSR),” Nuclear Technology 138 (2002) 93-95.

150. R. W. Moir, “Marangoni convection induced ripple on grazing incidence liquid metal mirror (GILMM) used for laser inertial fusion energy,” Lawrence Livermore Laboratory, Livermore, CA, UCRL-ID-145529 (September 14, 2001). www.osti.gov/servlets/purl/15013419-Zb7vNq/native/

151. S. G. Durbin and R. W. Moir, “One-dimensional heat transfer analysis for thin films with applications in inertial fusion energy,” Lawrence Livermore Laboratory, Livermore, CA, UCRL-ID-145435 (October 15, 2001). www.osti.gov/servlets/purl/15006205-ePVNxi/native/

152. R. W. Moir, R. H. Bulmer, T. K. Fowler, T. D. Rognlien, M. Z. Youssef , “Thick liquid-walled spheromak magnetic fusion power plant ,” Lawrence Livermore Laboratory, Livermore, CA, UCRL-ID-148021 Rev.2 (April 28, 2003). www.osti.gov/servlets/purl/15004532-eoOVcT/native/

153. R. W. Moir, R. H. Bulmer, T. K. Fowler, T. D. Rognlien, & M. Z. Youssef, “Spheromak magnetic fusion energy power plant with thick liquid-walls,” Fusion Science and Technology 44 (2003) 317-326.

154. Ralph Moir and Edward Teller, “Safe, sustainable thorium and uranium fueled underground power plant based on molten salt technology,” Lawrence Livermore Laboratory, Livermore, CA, UCRL-JC-154577-DR (July 24, 2003). Submitted to SCIENCE-rejected.

155. Ralph Moir and Edward Teller, “Thorium fueled underground power plant based on molten salt technology,” Nuclear Technology 151 (2005) 334-340.

156. B. G. Logan, R. W. Moir, M. Tabak, R. L. Bieri, J. H. Hammer, C. W. Hartman, M. A. Hoffman, R. L. Leber, R. W. Petzoldt, M. T. Tobin, “Compact Torus Accelerator Driven Inertial Confinement Fusion Power Plant HYLIFE-CT,” UCRL-TR-211025 (2005). http://www.osti.gov/servlets/purl/15016028-yK40cw/native/

157. R. W. Moir and W. L. Barr, “Analysis of interstellar spacecraft cycling between the Sun and the near stars,” the Journal of the British Interplanetary Society 58, 232-241 (2005).

158. R. W. Moir and T. D. Rognlien, “Axisymmetric tandem mirror magnetic fusion energy power plant with thick liquid-walls,” Fusion Science and Technology 52, (2007) 408-416.

159. R.W. Moir, “Recommendations for a restart of molten salt reactor development,”Energy Conversion and Management 49(2008) 1849-1858 .

160. R. W. Moir, “Jets and droplets compared to a moving slab of liquid for divertor cooling for a tokamak magnetic fusion energy reactor”, 51 pages, Vallecitos Molten Salt Research Report No. 1 (2008).

161. R. W. Moir, H. F. Shaw, A. Caro, L. Kaufman, J. F. Latkowski. J. Powers, P.E.A. Turchi, “Molten salt fuel version of Laser Inertial Fusion Fission Energy (LIFE),” Fusion Science and Technology 56 (August 2009) 632-640.

162. R. W. Moir, C. A. Hagmann, H. R. Shaw. “Pu from weapons burning in a molten salt version of LIFE,” LLNL-TR-418362 (2009).

163. R. W. Moir. “U232 nonproliferation features,” Vallecitos Molten Salt ResearchReport No. 2 (June 25, 2010), 17 pages.

164. R. Hargraves and R. Moir. “Liquid fluoride thorium reactors,” American Scientist98 (July 1, 2010),10 pages.

165. R. W. Moir. “Production of U-232 and U-233 in a fusion-fission hybrid” Vallecitos Molten Salt Research Report No. 3 (December 21, 2010), 37 pages.

166. R. Hargraves and R. Moir. “Liquid Fuel Nuclear Reactors” APS Physics Forum on Physics & Society, Volume 40, Number 1 (January 2011).

167. R. W. Moir. “Fission-suppressed fusion, thorium-cycle breeder and nonproliferation,” 15th International Conference on Emerging Nuclear Energy Systems ICENES 2011 May 15-19, 2011 San Francisco, Transactions of Fusion Science and Technology, 61, 243-249 (January 2012).

168. R. W. Moir, N.N. Martovetsky, A.W. Molvik, D.D. Ryutov, T.C. Simonen.“Axisymmetric Magnetic Mirror Fusion-Fission Hybrid,” 15th International Conference on Emerging Nuclear Energy Systems ICENES 2011 May 15-19, 2011 San Francisco, Transactions of Fusion Science and Technology 61, 206-215 (January 2012).

169. R. W. Moir, N.N. Martovetsky, A.W. Molvik, D D. Ryutov, T C. Simonen.“Axisymmetric Magnetic Mirror Fusion-Fission Hybrid,” 6/7/2011, LLNL report LLNL-TR-484071, 63 pages.

170. R. W. Moir, N. N. Martovetsky, A. W. Molvik, D. D. Ryutov, T. C. Simonen, “Mirror-based hybrids of recent design,” FUNFI, Workshop on Fusion for Neutrons and Sub-critical Nuclear Fission, Villa Monastero, Varenna, Italy, September 12-15, 2011, AIP Conference Proceedings 1442, 43-54 ( 2012) and talk.

171. R. W. Moir, Fission-Suppressed Fusion Breeder on the Thorium Cycle and Nonproliferation,” FUNFI, Workshop on Fusion for Neutrons and Sub-critical Nuclear Fission, Villa Monastero, Varenna, Italy, September 12-15, 2011, AIP Conference Proceedings 1442, 346-355 (2012), Vallecitos Molten Salt Research Report No. 4 (2011) and talk.

172. T.C. Simonen, R.W. Moir, A.W. Molvik and D.D. Ryutov, “A 14MeV fusion neutron source for material and blanket development and fission fuel production,” Nucl. Fusion 53 No. 6 (2013).

173. Ralph W. Moir and Wallace Manheimer, Chapter 14. “Fusion Fission Hybrid Reactors” in T. J. Dolan et al., Magnetic Fusion Technology, Springer Verlag, London, 2013.

174. Moir, Ralph, “Nonproliferation role of 231Pa and 232U from a fusion breeder for the thorium molten salt reactor,” talk at Thorium Energy Alliance 2014 Conference (TEAC6) May 29, 2014, Chicago.

175. R.W. Moir, “231Pa and 232U production in a fusion breeder to aid nonproliferation with thorium fission fuel cycles,” Vallecitos Molten Salt Research Report No. 5 (July 16, 2014), Rev 1 (September 9, 2014).

176. R.W. Moir, “Nonproliferation role of 231Pa and 232U in a Molten Salt Reactor on the Th-233U fuel cycle,” Vallecitos Molten Salt Research Report No. 6 (July 16, 2014), Rev 1 (September 9, 2014).

 

Vallecitos Molten Salt Research Reports

1. R. W. Moir, “Jets and droplets compared to a moving slab of liquid for divertor cooling for a tokamak magnetic fusion energy reactor”, 51 pages, Vallecitos Molten Salt Research Report No. 1 (2008).

2. R. W. Moir. “U232 nonproliferation features,” Vallecitos Molten Salt Research Report No. 2 (June 25, 2010), 17 pages.

3. R. W. Moir. “Production of U-232 and U-233 in a fusion-fission hybridVallecitos Molten Salt Research Report No. 3 (December 21, 2010), 37 pages.

4. R. W. Moir, Fission-Suppressed Fusion Breeder on the Thorium Cycle and Nonproliferation,” FUNFI, Workshop on Fusion for Neutrons and Sub-critical Nuclear Fission, Villa Monastero, Varenna, Italy, September 12-15, 2011, AIP Conference Proceedings 1442, 346-355 (2012), Vallecitos Molten Salt Research Report No. 4 (2011) and talk.

5. R.W. Moir, “231Pa and 232U production in a fusion breeder to aid nonproliferation with thorium fission fuel cycles,” Vallecitos Molten Salt Research Report No. 5 (July 16, 2014). Rev 1 (September 9, 2014).

6. R.W. Moir, “Nonproliferation role of 231Pa and 232U in a Molten Salt Reactor on the Th-233U fuel cycle,” Vallecitos Molten Salt Research Report No. 6 (July 16, 2014). Rev 1 (September 9, 2014).

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Patents and Invention Disclosures

PATENTS

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.

6. Molten salt fuels with high plutonium solubility #8506855 B2, Aug 13, 2013, with Patrice E. A. Turchi, Henry F. Shaw and Larry Kaufman.

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.

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