Status of research and development of the lead-alloy-cooled fast reactor

Journal of Nuclear Science and Technology

Volumn 40, Issue 8, 2003, Pages 614-627

  Loewen, Eric P ^a   Tokuhiro, Akira Thomas ^b  

^a IDAHO NATIONAL LABORATORY   (United States)

^b University of Missouri Rolla   (United States)

Author keywords

Actinide burning; Lead cooled reactors; Nuclear reactors

Indexed keywords

ACCIDENT PREVENTION; LEAD ALLOYS; LIQUID METALS; NUCLEAR FUEL CLADDING; NUCLEAR REACTOR ACCIDENTS; RADIOACTIVE WASTES; THERMAL EFFECTS; VAPOR PRESSURE;

CORROSIVENESS; ECONOMIC COMPETITIVENESS; LEAD ALLOY COOLED FAST REACTOR; NONPROLIFERATION ENHANCEMENT;

FAST REACTORS;

EID: 0142087569     PISSN: 00223131     EISSN: None     Source Type: Journal    
DOI: 10.1080/18811248.2003.9715398     Document Type: Article

References (109)

1. B. W. Spencer, “The Rush to Heavy Liquid Metal Reactor Coolants—Gimmick or Reasoned,” Proc. 8th Int. Conf. Nuclear Engineering (ICONE-8), Apr. 2-6, 2000, Baltimore, MD USA, (2000).
2. PE. MacDonald, et al., Design of an Actinide Burning, Lead or Lead-Bismuth Cooled Reactor That Produces Low Cost Electricity, INEEL/EXT-01-01376, MIT-ANP-PR-083, IN-EEL/MIT FY-01 Annual Report, (2001).
3. W. D. Manly, Anto de S. Brasunas, “Interim Report on Static Liquid-Metal Corrosion,” Report from ORNL Metallurgy Division, (1954).
4. V. V. Orlov, A. G. Sila-Novitsky, V. S. Smirnov, V. S. Tsikunov, A. I. Filin, V. N. Dobrovol’sky, Yu. I. Kazennov, B. D. Rogoskin, “Lead-cooled reactor core, its characteristic features,” Proc. ARS’94 Int. Topical Meeting Advanced Reactor Safety, Pittsburgh, Apr. 17-21, 1994, p. 516-520 (1994).
5. E. Adamov, V. Orlov, A. Filin, V. Leonov, A. Sila-Novitski, V. Smirnov, V. Tsikunov, “The Next Generation of Fast Reactors,” Nucl. Eng. Des., 173, 143-150 (1997).
6. E. Adamov, V. Orlov, “Nuclear power at the next stage: Cost-effective breeding, natural safety, radwastes, non-proliferation,” Nucl. Eng. Des., 173, 33-41 (1997).
7. G. I. Toshinsky, “LMFBR operation in the nuclear cycle without fuel reprocessing,” Proc. Int. Topical Meeting on Advanced Reactor Safety, Orlando, June 1997, Vol. 1, 39-44 (1997).
8. H. Sekimoto, Z. Su’ud, “Design study of lead and lead-bismuth-cooled small long-life nuclear power reactors using metallic and nitride fuels,” Nucl. Technol., 109, 307-313 (1995).
9. Z. Su’ud, H. Sekimoto, “Design and safety aspect of lead and lead-bismuth cooled long-life small safe fast reactors for various core configurations,” J. Nucl. Sci. Technol., 32, 8-19 (1995).
10. B. W. Spencer, R. N. Hill, D. C. Wade, D. J. Hill, J. J. Sienicki, H. S. Khalil, J. E. Cahalan, M. T. Farmer, V. A. Maroni, L. Leibowitz, “An advanced modular HLMC reactor concept featuring economy, safety, and proliferation resistance,” Proc. 8th Int. Conf. On Nuclear Engineering (ICONE-8), Baltimore, MD, (2000).
11. K. D. Weaver, J. S. Herring, P. E. MacDonald, “Performance modeling of metallic and nitride fuels in advanced lead-bismuth cooled fast reactors,” Proc. 8th Int. Conf. On Nuclear Engineering (ICONE-8), Baltimore, MD, (2000).
12. E. Greenspan, K. Aoki, E. Elias, W. E. Kastenberg, N. Stone, N. W. Brown, “Compact long fuel-life reactors for developing countries,” Proc. 9th Int. Conf. On Emerging Nuclear Energy Systems (ICENES’98), Herzelia, Israel, June 28-July 2, 1998, p. 74-83 (1998).
13. E. Greenspan, N. Z. Cho, S. G. Hong, T. H. Kim, W. E. Kastenberg, “Multi-recycling of spent fuel with low proliferation risk,” Proc. 9th Int. Conf. On Emerging Nuclear Energy Systems (ICENES’98), Herzelia, Israel, June 28-July 2, 1998, p. 455-464 (1998).
14. E. Greenspan, E. Elias, W. E. Kastenberg, N. Stone, NonProliferating Liquid Metal Cooled Reactors for Developing Countries, CNTWM98-2, Univ. Of California at Berkeley, (1998).
15. E. Greenspan, H. Shimada, D. C. Wade, M. D. Carelli, L. Conway, N. W. Brown, Q. Hossain, “The encapsulated nuclear reactor heat source reactor concept,” Proc. 8th Int. Conf. On Nuclear Engineering (ICONE-8), Baltimore, MD., June 28-July 2, 2000, p. 617-625 (2000).
16. S. Hwang, S. H. Jeong, B. G. Park, W. S. Yang, K. Y. Sub, C. H. Kim, “The concept of Proliferation-Resistant, Environment-Friendly, Accident-Tolerant, Continual and Economical Reactor (PEACER),” 3rd Int. Symp. On Global Environmental and Nuclear Energy Systems, Tokyo, Japan, Dec. 14-18, 1999.
17. R. N. Hill, J. E. Cahalan, H. S. Khalil, D. C. Wade, “Development of small, fast reactor core design using lead-based coolant,” Proc. Global’99 Int. Conf. On Future Nuclear Systems, Jackson Hole, WY, August 1999, (1999).
18. P Hejzlar, M. J. Driscoll, M. S. Kazimi, “Conceptual neu-tronic design of a lead-bismuth-cooled actinide burning reactor,” Nucl. Sci. Eng., 139, 1-18 (2001).
19. C. Fazio, G. Benarnati, C. Martini, G. Palombarini, J. Nucl. Mater., 296,(2001).
20. B. A. Gabaraev, A. Stanculescu, V. M. Poplavsky, “Summary Report,” Design and Predominance of Reactor and Subcritical Blanket Systems with Lead and Lead-Bismuth as Coolant and/or Target Material, Moscow, Russian Fed., Oct. 23-27, 2000, Int. Working Group on Fast Reactors.
21. U. Knebel, G. Muller, J. Konys, “Lead bismuth activities at the Karlsruhe Lead Laboratory KALLA,” Tenth Int. Conf. On Nuclear Engineering, Arlington, Virginia, Apr. 14-18, 2002.
22. W. S. Park, W. Hwang, Y. H. Kim, N. Tak, T. Y. Soug, “Design Progress of HYPER System,” Design and Performance of Reactor and Subcritical Blanket Systems with Lead and Lead-Bismuth as Coolant and/or Target Material, Moscow, Russian Fed., Oct. 23-27,2000.
23. P Satyamurthy, S. B. Degwekar, P. K. Nema, “Design of a molten heavy-metal coolant and target for Fast-Thermal Accelerator Driven Sub-Critical System (ADS),” Design and Performance of Reactor and Subcritical Blanket Systems with Lead and Lead-Bismuth as Coolant and/or Target Material, Moscow, Russian Fed., Oct. 23-27,2000, Int. Working Group on Fast Reactors.
24. Z. Zhixiang, L. Zhanglin, X. Yongli, D. Dazhao, “Study on ADS Pb (Pb/Bi) spallation target,” Design and Performance of Reactor and Subcritical Blanket Systems with Lead and Lead-Bismuth as Coolant and/or Target Material, Moscow.
25. Russian Fed., Oct. 23-27, 2000, Int. Working Group on Fast Reactors.
26. C. Rubbia, S. Bruno, Y. Kadi, J. A. Rubio, Fast Neutron Incineration in the Energy Amplifier As Alternative to Geologic Storage: The Case of Spain, European Organization for Nuclear Research, CERN/LHC/97-Dl (EET), (1997).
27. U.S. Department of Energy, A Roadmap for Developing Accelerator Transmutation of Waste (ATW) Technology, DOE Report to Congress, DOE/RW-0519, (1999).
28. P Hejzlar, N. E. Todreas, M. J. Driscoll, P E. MacDonald, J. Buongiorno, K. D. Weaver, “Design strategies for lead-alloy-cooled reactors for actinide burning and low-cost electricity production,” 10th Int. Conf. On Nuclear Engineering, Arlington, VA, Apr. 14-18, 2002, ICONE 10-22377, (2002).
29. P Hejzlar, M. Driscoll, M. Kazimi, Void Reactivity Performance in Lead-Bismuth-Cooled Reactors for Actinide Transmutation, MIT-ANP-TR-068, Massachusetts Institute of Technology, (1999).
30. P Hejzlar, M. Driscoll, M. Kazimi, “Neutronic design for a lead-Bi-cooled actinide burner fast reactor,” Trans. Am. Nucl. Soc., 81,271-273 (1999).
31. E. Buongiorno, N. E. Todreas, M. Kazimi, “Void fraction prediction for the Pb-Bi/water direct contact nuclear reactor,” Proc. Int. Conf. On Nuclear Engineering, Apr. 2-6, 2000, Baltimore, MD, (ICONE-8), (2000).
32. Barak, L. Blumenau, H. Branover, A. El-Boher, E. Greenspan, E. Spero, S. Sukoriansky, “Possibilities for improvements in liquid-metal reactors using liquid metal magnetohydrodynamic energy conversion,” Nucl. Technol., 89, 36-51 (1990).
33. H. Branover, A. El-Boher, E. Greenspan, A. Barak, “Promising applications of the liquid metal MHD energy conversion technology,” Proc. 24th Intersociety Energy Conversion Engineering Conf., Washington, D.C., Aug. 6-11, 1989, p. 1051-1058 (1989).
34. H. Branover, A. Barak, E. Golbraikh, E. Greenspan, S. Lesin, “High-efficiency energy conversion cycle for lead cooled reactors,” Proc. 9th Int. Conf. On Emerging Nuclear Energy Systems (ICENES'98), Herzlia, Israel, J, (1998).
35. E. Greenspan, A. Barak, L. Blumenau, H. Branover, A. El-Boher, E. Spero, S. Sukoriansky, “Liquid metal MHD conversion of nuclear energy to electricity-possibilities and implications,” Prog. Astronaut. Aeronaut., 111, 129-157 (1988).
36. E. Greenspan, A. Barak, A. Baron, H. Branover, A. El-Boher, A. Cohn, “On the synergism between the “Ominor actinide CON” liquid metal MHD and the FBC technologies,” Proc. Intersociety Energy Conversion Engineering Conf., Aug. 39, 1991, Vol. 3, 93-98 (1991).
37. Buongiorno, N. Todreas, M. Kazimi, Thermal Design of Lead-Bismuth Cooled Reactors for Actinide Burning and Power Production, MIT-ANP-TR-066, Massachusetts Institute of Technology, (1999).
38. Buongiorno, N. Todreas, M. Kazimi, M. Driscoll, P. Hejzlar, “Key features of an integrated lead-Bi-cooled reactor based on water/liquid metal direct heat transfer,” Trans. Am. Nucl. Soc., 81, 360-361 (1999).
39. R. L. Moore, et al, MOCUPMCNP-ORIGEN2 Coupled Utility Program, INEL-95/0523, Idaho National Engineering Laboratory, (1995).
40. F. Briesmeister, MCNP—A General Monte Carlo N-Particle Transport Code, Los Alamos National Laboratory, (1997).
41. G. Croff, A User's Manual for the ORIGEN2 Computer Code, Oak Ridge National Laboratory, (1980).
42. G. L. Hofman, L. C. Walters, “Metallic fast reactor fuels,” Mater. Sci. Technol., 10A, 1-44 (1994).
43. P E. MacDonald, J. Buongiorno, Design of an Actinide Bur-ing, Lead or Lead-Bismuth Cooled Reactor That Produces Low Cost Electricity: FY-01 Annual Report, INEEL/EXT-01-01376, MIT-ANP-TR-084, (2001).
44. Y. S. Tang, R. D. Coffield, Jr., R. A. Markley, Thermal Analysis of Liquid-Metal Fast Breeder Reactors, American Nuclear Society, (1978).
45. J. G. Yevick, A. Amorosi, Fast Reactor Technology: Plant Design, Cambridge, Massachusetts, The MIT Press, (1966).
46. J. L. O’toole, P. L. Silvestor, “Correlations of convective heat transfer in confined horizontal layers,” CEP Symp. Ser., 57, 32,81,(1961).
47. Taghavi, N. M. Ghoniem, “Transient thermal-hydraulics considerations of Tandem Mirror Li-Pb cooled blankets during start-up/shutdown operations,” Nucl. Eng. Des./Fusion, 1, 369-374 (1984).
48. T. Tokuhiro, Natural convection heat transfer enhancement in mercury with gas injection and in the presence of a transverse magnetic field, Ph.D. Thesis, Purdue University, West Lafayette, Indiana, USA, (1991).
49. D. Japikse, “Advances in thermosyphon technology,” Adv. Heat Transfer, 9, 1-111 (1973).
50. Y. Zvirin, “A review of natural circulation loops in pressurized water reactors and other systems,” Nucl. Eng. Des., 67, 203-225 (1981).
51. Mertol, R. Greif, “A review of natural circulation loops,” Natural Convection: Fundamentals and Applications, S. Kakac, W. Aung, R. Viskanta (eds), Hemisphere, New York, p. 1033-1071 (1985).
52. R. Greif, “Natural circulation loops,” J. Heat Transfer, 110, 243-1258 (1988).
53. C. D. Alstad, H. S. Isbin, N. R. Amundson, J. P. Silvers, The Transient Behaviour ofSingle-phase Natural Circulation Water Loop Systems, ANL-5409, (1956).
54. C. P. Agarwal, S. S. Alam, N. Gopalakrishna, “Heat transfer studies in a vertical tube of a closed-loop thermosyphon,” Trans. IChE, 21, 37 (1979).
55. B. J. Huang, R. Zelaya, “Heat transfer behaviour of a rectangular thermosyphon loop,” J. Heat Transfer, 110, 487-493 (1988).
56. G. G. Loomis, K. Soda, Results of the Semi-scale MOD-2A Natural Circulation Experiments, NUREG/CR-2335 and EGG-2200, (1982).
57. H. Ardron, V. S. Krishnan, “Two-phase natural circulation experiments in a pressurized water loop with figure-of-eight symmetry,” Proc. Experimental and Modeling Aspects of Small-breakLOCA Conf., IAEA, Budapest, Hungary, Oct. 1983,(1983).
58. H. H. Bau, K. E. Torrance, “Transient and steady behaviour of an open, symmetrically heated, free convection loop,” Int. J. Heat Mass Transfer, 24, 597-609 (1981).
59. V. Zhukov, A. P. Sorokin, P. A. Titov, P. A. Ushakov, “Thermohydraulic problems in lead-cooled reactors,” Power-Physics Inst. NIKIET, 71[2], 142-151 (1992).
60. V. Zhukov, A. P. Sorokin, M. V. Papandin, V. P. Smirnov, “Effect of a variable energy release on the heat-transfer coefficient in square lattices,” Power-Physics Inst. NIKIET, 74[3], 194-199 (1993).
61. B. Davis, A. S. Shieh, “Overview of the use of the ATHENA for thermal-hydraulic analysis of systems with lead-bismuth coolant,” Proc. 8th Int. Conf. On Nuclear Engineering (ICONE-8), Apr. 2-6, 2000, Baltimore MD, USA, (2000).
62. El-Boher, S. Lesin, Y. Unger, H. Branover, “Experimental studies of liquid metal two-phase flows in vertical pipes,” Proc. 1st World Conf. On Experimental Heat Transfer, Dubrovnik, Yugoslavia, (1988).
63. J. Hill, “SASSYS analysis ofEBR-II SHRT experiments,” Trans. Am. Nucl. Soc., 55, 421 (1987).
64. J. P. Herzog, “SASSYS validation with the EBR-II shutdown heat removal tests,” Trans. Am. Nucl. Soc., 60, 730 (1989).
65. J. Hill, “SASSYS validation studies,” Proc. Int. Topical Meeting on Safety of Next Generation Power Reactors, Seattle, WA, (1988).
66. J. E. Cahalan, F. E. Dunn, T. A. Taiwo, “Coupled reactor physics and coolant dynamics of heavy-liquid-metal-cooled systems,” Trans. Am. Nucl. Soc., 81, 276 (1999).
67. J. L. Everhart, E. L. Van Nuis, Liquid Metal Heat Transfer Fluid Unstressed Static Corrosion Tests, NP-1497, U.S. Atomic Energy Commission, (1950).
68. J. V. Cathcart, Mass Transfer in Dynamic Lead-Inconel Systems, ORNL 52-11-116, (1952).
69. J. V. Cathcart, W. D. Manly, A Technique for Corrosion Testing in Liquid Lead, ORNL-44960, (1954).
70. J. C. Clifford, “A Loop for Circulating Liquid Lead-Bismuth Mixtures: Corrosion Studies and Operation,” Dissertation, Iowa State University of Science and Technology, Ames Iowa, (1960).
71. J. Romano, C. J. Klamut, D. H. Gurinsky, The Investigation of Container Materials forBi and Lead Alloys Part I. Thermal Convection Loops, BNL 811 (T-313), Brookhaven National Laboratory, (1963).
72. Brasunas, W. D. Manly, Interim Report on Static Liquid-Metal Corrosion, ORNL-1647, (1954).
73. H. U. Borgstedt, G. Frees, G. Dreschsler, “Corrosion of stainless steel in flowing PbLi eutectic,” J. Nucl. Mater., 141-143, 561-565 (1986).
74. V. N. Efimov, I. Yu. Zhemkov, A. N. Kozolup, V. I. Polyakov, V. T. Stepanov, Yu. E. Stynda, “The BOR-60 loop-channel design for testing the BREST reactor fuel,” Design and Performance of Reactor and Subcritical Blanket Systems with Lead and Lead-Bismuth as Coolant and/or Target Material, Moscow, Russian Fed., Oct. 23-27,2000, International Working Group on Fast Reactors.
75. He, Xiaoyi, N. Li, M. Mineev, “A kinetic model for corrosion and precipitation in N on-isothermal LBE flow loop,” J. Nucl. Mater., 297, 214-219 (2001).
76. K. Kinoshita, “Liquid metal cooled small reactors (MDP and 4S) In CRIEPI,” International Seminar on Status and Prospects for Small and Medium Sized Reactors, Cairo, Egypt, May 27-31,2001.
77. Takahashi, I. Masayuki, T. Obara, H. Sekimoto, K. Kikuchi, K. Aoto, T. Kitano, “Draft: Studies on materials for heavy-liquid-metal-cooled reactors in Japan,” 10th Int. Conf. On Nuclear Engineering (ICONE10), Arlington, Virginia, Apr. 14-18, 2002, ICONE10-22166, (2002).
78. H. Glasbrenner, J. Konys, G. Mueller, A. Rusanov, “Corrosion investigations of steels in flowing lead,” J. Nucl. Mater., 296, 237-242 (2001).
79. R. Weeks, “Lead, bismuth, tin and their allows as nuclear coolants,” Nucl. Eng. Des., 15, 363-372 (1971).
80. L. Li, “Liquid lead-bismuth technology: Russian Nuclear Coolant Technology and its transfer and extension for ATW,” Slides at ATW Roadmap Working Group Meeting, Mar. 15, 1999.
81. F. Gromov, Y. S. Belomyttsev, V. A. Gubarev, A. G. Kalashnikov, M. P. Leonchuk, N. N. Novikova, Y. U. Orlov, “Inherently safe lead-bismuth-cooled reactors,” Atomic Energy, 76[4], (1994).
82. V Kuznetsov, H. Sekimoto, “Radioactive waste transmutation and safety potentials for the lead cooled fast reactor in the equilibrium state,” J. Nucl. Sci. Technol., 32[6], 507-516 (1995).
83. H. Lefhalm, I. U. Knebel, K. I. Mack, “Kinetics of gas phase oxygen control system (OCS) for stagnant and flowing Pb-Bi systems,” J. Nucl. Mater., 296, 301-304 (2001).
84. P. Loewen, C. B. Davis, P. E. MacDonald, “A technique for dynamic corrosion testing in liquid lead alloys,” ICONE-8, Baltimore, MD, Apr. 2000, Paper-8245 (2000).
85. P. Loewen, H. J. Yount, K. Volk, A. Kumar, “Corrosion tests of U.S. Steels in flowing lead-bismuth cutectic at 550 and 650°C,” Submitted to Nucl. Technol.,2002.
86. P. Loewen, P. E. MacDonald, “Heavy metal coolant corrosion testing using a gas lift apparatus,” ANS Annual Winter Meeting, Reno, NV, Nov. 2001.
87. P. Loewen, P. E. MacDonald, “Corrosion of zirconium, 316, 410SS, F-22, and HT-9 exposed to high temperature heavy metal coolant under extreme conditions,” American Nuclear Society Annual Winter Meeting, Reno, NV, Nov. 2001.
88. E. Carlson, P. A. Roth, V. H. Ransom, ATHENA Code Manual Vol. I: Code Structure, System Models, and Solution Methods, EGG-RTH-7397, INEL, (1986).
89. L. Li, “Active control of oxygen in molten lead-bismuth eutectic systems to prevent steel corrosion and coolant contamination,” J. Nucl. Mater., 300, 73-81 (2002).
90. Branover, S. Lesin, M. Tsirlin, “Some aspects of direct interaction of volatile liquids with hot liquid metals,” Proc. Int. Conf. On Future Nuclear Systems, Aug. 29-Sept. 3, 1999, Jackson Hole, WY, USA, (1999).
91. Y. Kurata, M. Futakawa, K. Kikuchi, S. Saito, T. Osugi, “Corrosion studies in liquid Pb-Bi alloy at JAERI: R&D program and first experimental results,” 2nd Int. Workshop on Materials for Hybrid Reactors and Related Technol., Apr. 18-20, 2001, Brasimone, Italy.
92. Takahashi, T. Suzuki, H. Sekimoto, “Corrosion of steels in a flowing nonisothermal Pb-Bi,” Trans. Am. Nucl. Soc., 85, 300 (2001).
93. Takahashi, H. Sekimoto, K. Ishikawa, T. Suzuki, K. Hata, S. Qiu, S. Yoshida, T. Yano, M. Imai, “Experimental study on flow technology and steel corrosion of lead-bismuth,” Proc. 10th Int. Conf. Nuclear Engineering (ICONE-10), Apr. 1418, 2002, Arlington, VA, (2002).
94. T. Takano, et al., Investigation of Corrosion, Water Reaction, Polonium EvaporationandBismuth Resource inLiquidMetal Lead-Bismuth Technology, JAERI-Review 2000-014, (2000).
95. Uranium Information Center, Small Nuclear Power Reactors, UIC Nuclear Issues, Briefing Paper #60, Melbourne, Australia, November 2002. As of 03/05/2003 at http://www.uic.com.au/nip60.htm.
96. “Study outlines reactor designs that may be ready for deployment by decade’s end,” Nuclear News, Operations Report, p. 25-33 (2001).
97. K. Kambe, “Conceptual design of a modular island core fast breeder reactor “RAPID-M,” J. Nucl. Sci. Technol., 39[11], 1169-1181 (2002).
98. U. Ueda, et al., “Current design status of sodium cooled super-safe, small and simple reactor,” 10th Int. Conf. On Nuclear Engineering (ICONE-10), Apr. 14-18,2002, Arlington, Virginia, USA.
99. U. Ueda, et al., “Passive safety features in sodium cooled super-safe, small and simple reactors, 10th Int. Conf. On Nuclear Engineering (ICONE-10), Apr. 14-18,2000, Arlington, Virginia, USA.
100. Nuclear Power Generation, Innovative FBR Technologies, Basic Tests for the Development of an Innovative Steam Generator for Fast Reactors, (CRIEPI) Annual Research Report, at http://criepi.denken.or.jp/eng/PR/Nenpo/1995E/seika95gen11E.html as of 03/2/03.
101. Kinoshita, Y. Nishi, “Heat transfer characteristics of a direct contact steam generator with low melting point alloy and water,” Proc. Tenth Int. Heat Transfer Conf., Brighton, U.K., Vol. 3,209(1994).
102. Kinoshita, Y. Nishi, M. Furuya, “Study on applicability of direct contact heat transfer steam generators for LMFBRS,” Proc. 8th Int. Conf. On Nuclear Engineering, Baltimore, USA., ICONE-8769, (2000).
103. Y. Nishi, I. Kinoshita, M. Furuya, N. Takenaka, M. Matsu-bayashi, “Visualization of direct contact heat transfer between molten alloy and waterby neutron radiography,” Proc. 11th Int. Heat Transfer Conf. (IHTC-11), Kyongju, Korea, Vol. 4, 47 (1998).
104. Furuya, K. Matsumura, I. Kinoshita, “A linear stability analysis of a vapor film in terms of the triggering of vapor explosions,” J. Nucl. Sci. Technol., 39[10], 1026-1032 (2002).
105. M. Furuya, I. Kinoshita, “Effects of polymer, surfactant, and salt additives to a coolant on the mitigation and the severity of vapor explosions,” Exp. Therm. Fluid Sci., 26, Issue 2-4, 213-219 (2002).
106. M. Furuya, I. Kinoshita, S. Nishimura, “Effects of surface property and thermo-physical property of hot liquid on the triggering of vapor explosions,” ASME Symposium Series, National Heat Transfer Conf., NTHC2000-12004 (CD-ROM Publication), Pittsburgh, USA, (2000).
107. M. Furuya, I. Kinoshita, Y. Nishi, “Vapor explosion in the droplet impingement system,” Proc. 11th Int. Heat Transfer Conf., Kyongju, Korea, Vol. 5,471-476 (1998).
108. Y. Nishi, I. Kinoshita, “Innovative heat exchanger for FBRs,” Proc. Tenth Int. Conf. On Emerging Nuclear Energy Systems (ICENES2000), Petten, The Netherlands, p. 270 (2000).
109. CRIEPI, Occurrence Conditions and Suppression Measures of Vapor Explosions, At http://criepi.denken.or.jp/eng/PR/ Nenpo/2000E/00seika49.pdf; as of Mar. 10, 2003.