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Research and Development

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Super Light Water Reactors and Super Fast Reactors

Abstract

This chapter summarizes the activities on the supercritical water-cooled reactors (SCWRs) worldwide. The activities in Japan are reviewed first followed by those in other countries and organizations. Generation-IV International Forum (GIF), International Atomic Energy Agency (IAEA), Coordinated Research Plan (CRP), and international symposiums are also briefly introduced.

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References

  1. Y. Oka, Y. Ishiwatari, et al., “Research Program on Super Fast Reactor,” Proc. ICAPP’06, Reno, NV, June 4–8, 2006, Paper No. 6353 (2006)

    Google Scholar 

  2. Y. Ishiwatari, Y. Yamakawa, et al., “Research and Development of a Super Fast Reactor (1) Overview and High-Temperature Structural Design,” Proc. 16th PBNC, Aomori, Japan, October 13–18, 2008, P16P1290 (2008)

    Google Scholar 

  3. Y. Ishiwatari, Y. Oka and K. Yamada, “Japanese R&D Projects on Pressure-Vessel Type SCWR,” Proc. 4th Int. Symp. on SCWR, Heidelberg, Germany, March 8–11, 2009, Paper No. 73 (2009)

    Google Scholar 

  4. H. Ju and L. Cao, “Research and Development of a Super Fast Reactor (3) Fuel Rod Analyses Under Normal Operating Condition,” Proc. 16th PBNC, Aomori, Japan, October 13–18, 2008, P16P1292 (2008)

    Google Scholar 

  5. H. Ju, L. Cao, et al., “Core Design and Fuel Rod Analyses of a Super Fast Reactor with High Power Density,” Proc. ICAPP’09, Tokyo, Japan, May 10–14, 2009, Paper No. 9264 (2009)

    Google Scholar 

  6. L. Cao, H. Lu, et al., “Research and Development of a Super Fast Reactor (4) Transmutation Analyses of Minor Actinides and Transuranium Elements,” Proc. 16PBNC, Aomori, Japan, October 13–18, 2008, P16P1293 (2008)

    Google Scholar 

  7. H. Lu, Y. Ishiwatari, et al., “Evaluation of Transmutation Performance of Long-Lived Fission Products with a Super Fast Reactor,” Proc. ICAPP’09, Tokyo, Japan, May 10–14, 2009, Paper No. 9263 (2009)

    Google Scholar 

  8. J. Gou, Y. Ishiwatari, et al., “Research and Development of a Super Fast Reactor (5) Thermal Hydraulic Analyses of Tight-Lattice Subchannels,” Proc. 16th PBNC, Aomori, Japan, October 13–18, 2008, P16P1294 (2008)

    Google Scholar 

  9. J. Gou, Y. Ishiwatari, et al., “CFD Analyses in Tight-Lattice Subchannels and Seven-Rods Bundle Geometries of a Super Fast Reactor,” Proc. ICAPP’09, Tokyo, Japan, May 10–14, 2009, Paper No. 9262 (2009)

    Google Scholar 

  10. W. Tian, Y. Ishiwatari, et al., “Numerical Computation on Thermally Controlled Steam Bubble Condensation Using MPS-MAFL,” Proc. 4th Int. Symp. on SCWR, Heidelberg, Germany, March 8–11, 2009, Paper No. 05 (2009)

    Google Scholar 

  11. S. Tanaka, Y. Shirai, et al., “Plant Concept of Supercritical Pressure Light Water Reactor,” Proc. ICONE-5, Nice, France, May 26–30, 1997, ICONE-5-2346 (1997)

    Google Scholar 

  12. S. Goto, Y. Ishiwatari and Y. Oka, “Considerations for the Reactor Characteristics of Super Fast Reactor,” Transactions of ANS/ENS 2007 Int. Conf. on Making the Renaissance Real, Washington, DC, November 7–15, 2007, 869–870 (2007)

    Google Scholar 

  13. S. Goto, Y. Ishiwatari and Y. Oka “Research and Development of a Super Fast Reactor (12) Considerations for the Reactor Characteristics,” Proc. 16th PBNC, Aomori, Japan, October 13–18, 2008, P16P1276 (2008)

    Google Scholar 

  14. A. Shioiri, K. Moriya, et al., “Development of Supercritical-Water Cooled Power Reactor Conducted by a Japanese Joint Team,” Proc. GENES4/ANP2003, Kyoto, Japan, September 15–19, 2003, Paper No. 1121 (2003)

    Google Scholar 

  15. Y. Oka and K. Yamada, “Research and Development of High Temperature Light Water Cooled Reactor Operating at Supercritical-Pressure in Japan,” Proc. ICAPP’04, Pittsburgh, PA, June 13–17, 2004, Paper No. 4233 (2004)

    Google Scholar 

  16. K. Yamada, M. Ookawa, et al., “Recent Activities and Future Plan of Thermal-Spectrum SCWR Development in Japan,” Proc. 3rd Int. Symp. on SCWR, Shanghai, China, March 12–15, 2007, Paper No. SCWR2007-P054 (2007)

    Google Scholar 

  17. S. Higuchi, S. Sakurai and T. Ishida, “A Study of Fuel Behavior in an SCWR Core with High Power Density,” Proc. ICAPP’07, Nice, France, May 13–18, 2007, Paper No. 7206 (2007)

    Google Scholar 

  18. S. Higuchi and S. Sakurai, “A Study on Thermo-Mechanical Behavior of Typical Fuel Rods in an SCWR Core,” Proc. 4th Int. Symp. on SCWR, Heidelberg, Germany, March 8–11, 2009, Paper No. 72 (2009)

    Google Scholar 

  19. S. Sakurai, N. Yoshida, et al., “Development of Supercritical-Water Cooled Power Reactor Core Design Study with 3-D Core Simulator,” Proc. GENES4/ANP2003, Kyoto, Japan, September 15–19, 2003, Paper No. 1115 (2003)

    Google Scholar 

  20. S. Sakurai, S. Higuchi and A. Shioiri, “Development of SCPR Fuel Design Criteria and Core Design Study,” Proc. Global 2003, New Orleans, LA, November 16–20, 2003, 1746–1753 (2003)

    Google Scholar 

  21. M. Ookawa, S. Sakurai and K. Yamada, “Optimization Method for Design of the Supercritical-Water-Cooled Reactor Fuel Assembly,” Proc. ICAPP’05, Seoul, Korea, May 15–19, 2005, Paper No. 5216 (2005)

    Google Scholar 

  22. S. Sakurai, “SCWR Fuel and Core Design Study,” Proc. Global 2009, Paris, France, September 6–11, Paper No. 9373 (2009)

    Google Scholar 

  23. K. Kitou, K. Nishida, et al., “Investigation of Fuel Assembly by Using Subchannel Analysis for Supercritical-Water Cooled Power Reactor,” Proc. GENES4/ANP2003, Kyoto, Japan, September 15–19, 2003, Paper No. 1100 (2003)

    Google Scholar 

  24. S. Yoshida and H. Mori, “Heat Transfer to Supercritical Pressure Fluids Flowing in Tubes,” Proc. 1st Int. Symp. on SCWR, Tokyo, Japan, November 6–8, 2000, Paper No. 106 (2000)

    Google Scholar 

  25. T. Yamashita, S. Yoshida, et al., “Heat Transfer Study Under Supercritical Pressure Conditions,” Proc. GENES4/ANP2003, Kyoto, Japan, September 15–19, 2003, Paper No. 1119 (2003)

    Google Scholar 

  26. H. Komita, S. Morooka, et al., Study on the Heat Transfer to the Supercritical Pressure Fluid for Supercritical Water Cooled Power Reactor Development,” Proc. NURETH-10, Seoul, Korea, October 5–9, 2003, 1–11 (2003)

    Google Scholar 

  27. H. Mori, S. Yoshida, et al., “Heat Transfer Study Under Supercritical Pressure Conditions for Single Rod Test Section,” Proc. ICAPP’05, Seoul, Korea, May 15–19, 2005, Paper No. 5303 (2005)

    Google Scholar 

  28. H. Mori, M. Ohno, et al., “Research and Development of a Super Fast Reactor (7) Heat Transfer to a Supercritical Pressure Fluid Flowing in a Sub-bundle Channel,” Proc. 16th PBNC, Aomori, Japan, October 13–18, 2008, P16P1297 (2008)

    Google Scholar 

  29. K. Ezato, M. Akiba, et al., “Research and Development of a Super Fast Reactor (8) Heat Transfer Experiments Around a Simulated Fuel Rod with Supercritical Pressure Water,” Proc. 16th PBNC, Aomori, Japan, October 13–18, 2008, P16P1240 (2008)

    Google Scholar 

  30. K. Ezato, Y. Seki, et al., “Heat Transfer in a Seven-Rod Test Bundle with Supercritical Pressure Water (1) Experiments,” Proc ICAPP’09, Tokyo, Japan, May 10–14, 2009, Paper No. 9464 (2009)

    Google Scholar 

  31. T. Misawa, T. Nakatsuka, et al., “Numerical Analysis of Heat Transfer Experiment of Supercritical Pressure Water in Seven-Rod Test Bundle,” Proc. NURETH-13, Kanazawa, Japan, September 27–October 2, 2009 (2009)

    Google Scholar 

  32. T. Misawa, H. Yoshida, et al., “Numerical Analysis of Heat Transfer Test of Supercritical Water in a Tube Using the Three-Dimensional Two-Fluid Model Code,” Proc. ICONE16, Orlando, FL, May 11–15, 2008, ICONE16-48690 (2008)

    Google Scholar 

  33. T. Misawa, T. Nakatsuka, et al., “Research and Development of a Super Fast Reactor (9) Numerical Analysis of Heat Transfer Experiment of Supercritical Pressure Water and Freon in a Rod Bundle,” Proc. 16th PBNC, Aomori, Japan, October 13–18, 2008, P16P1065 (2008)

    Google Scholar 

  34. H. Yoshida, T. Nakatsuka and T. Suzuki, “Numerical Simulation of Heat Transfer Test of Forced Convection Supercritical Water in a Circular Pipe,” Proc. NTHAS6, Okinawa, Japan, November 24–27, 2008, N6P1082 (2008)

    Google Scholar 

  35. T. Nakatsuka, T. Misawa, et al., “Numerical Simulation of Heat Transfer Experiment of Supercritical Water by Two-Fluid Model Code ACE-3D,” Proc. 4th Int. Symp. on SCWR, Heidelberg, Germany, March 8–11, 2009, Paper No. 31 (2009)

    Google Scholar 

  36. T. Nakatsuka, T. Misawa, et al., “Numerical Simulation on Thermal-Hydraulic Characteristics in Fuel Assemblies of Supercritical Water Cooled Reactors Using Two-Fluid Model Analysis Code ACE-3D,” Proc. Global 2009, Paris, France, September 6–11, Paper No. 9486 (2009)

    Google Scholar 

  37. H. Mori, M. Ohno and Y. Hamamoto, “Experimental Study for Research and Development of a Super Fast Reactor (1) Critical Heat Flux in the Near-Critical Pressure Region,” Proc. ICAPP’09, Tokyo, Japan, May 10–14, 2009, Paper No. 9368 (2009)

    Google Scholar 

  38. H. Mori, Y. Hamamoto and Y. Ohno, “Experimental Study for Research and Development of a Super Fast Reactor (2) Oscillatory Condensation of High Temperature Vapor Directly Discharged into Sub-cooled Liquid Pool,” Proc. ICAPP’09, Tokyo, Japan, May 10–14, 2009, Paper No. 9369 (2009)

    Google Scholar 

  39. S. Kasahara, J. Kuniya, et al., “General Corrosion of Iron, Nickel and Titanium Alloys as Candidate Materials for the Fuel Claddings of the Supercritical-Water Cooled Power Reactor,” Proc. GENES4/ANP2003, Kyoto, Japan, September 15–19, 2003, Paper No. 1132 (2003)

    Google Scholar 

  40. J. Kaneda, S. Kasahara, et al., “Corrosion Film Properties of the Candidate Materials for the Fuel Claddings of the Supercritical-Water Reactor,” Proc. ICAPP’05, Seoul, Korea, May 15–19, 2005, Paper No. 5594 (2005)

    Google Scholar 

  41. J. Kaneda, S. Kasahara, et al., “General Corrosion Properties of Titanium Based Alloys for the Fuel Claddings in the Supercritical Water-Cooled Reactors,” Proc. 12th Int. Conf. on Environmental Degradation of Materials in Nuclear Systems-Water Reactors, Salt Lake City, UT, August 14–18, 2005 (2005)

    Google Scholar 

  42. Y. Tuchiya, F. Kano, et al., “SCC and Irradiation Properties of Metals Under Supercritical-Water Cooled Power Reactor Conditions,” Proc. GENES4/ANP2003, Kyoto, Japan, September 15–19, 2003, Paper No. 1096 (2003)

    Google Scholar 

  43. Y. Tsuchiya, F. Kano, et al., “SCC Properties of Metals Under Supercritical-Water Cooled Power Reactor Conditions,” Proc. Corrosion 2004, New Orleans, LA, March 28–April 1, 2004, Paper No. 4485 (2004)

    Google Scholar 

  44. H. Matusi, Y. Sato, et al., “Material Development for Supercritical Water-Cooled Reactors,” Proc. ICAPP’07, Nice, France, May 13–18, 2007, Paper No. 7447 (2007)

    Google Scholar 

  45. J. Kaneda, S. Kasahara, et al., “Material Properties of Stainless Steels Modified with Addition of Zirconium for Supercritical Water-Cooled Reactor,” Proc. ICAPP’07, Nice, France, May 13–18, 2007, Paper No. 7500 (2007)

    Google Scholar 

  46. M. Katsuragawa, H. Kashihara and M. Akebi, “Status of Liquid Metal Fast Breeder Reactor Fuel Development in Japan,” Journal of Nuclear Materials, Vol. 204, 14–22 (1993)

    Article  Google Scholar 

  47. Y. Nakazono, T. Iwai and H. Abe, “Corrosion Properties of PNC1520 Austenitic Stainless Steel in Supercritical Water as a Fuel Cladding Candidate Material for Supercritical Water Reactor,” Proc. 4th Int. Symp. on SCWR, Heidelberg, Germany, March 8–11, 2009, Paper No. 59 (2009)

    Google Scholar 

  48. Y. Nakazono, T. Iwai and H. Abe, “Corrosion Properties of Modified PNC1520 Austenitic Stainless Steel in Supercritical Water as a Fuel Cladding Candidate Material for Supercritical Water Reactor,” Proc. ICAPP’09, Tokyo, Japan, May 10–14, 2009, Paper No. 9456 (2009)

    Google Scholar 

  49. http://www.nuclear.jp/~hit/index_e.html

  50. K. Sasaki, T. Kubo, et al., “Research and Development of a Super Fast Reactor (10) Fabrication and Characterization of Durable Thermal Shielding Material,” Proc. 16th PBNC, Aomori, Japan, October 13–18, 2008, P16P1427 (2008)

    Google Scholar 

  51. G. Wu, Y. Katsumura, et al., “Pulse Radiolysis of High Temperature and Supercritical Water: Experimental Setup and \( e_{aq}^{-} \)-Observation,” Radiation Physics and Chemistry, Vol. 60, 395–398 (2001)

    Article  Google Scholar 

  52. G. Wu, Y. Katsumura et al., “Temperature Dependence of \( (SCN)_2^{ \bullet - } \) in Water at 25–400°C: Absorption Spectrum, Equilibrium Constant, and Decay,” Journal of Physical Chemistry A, Vol. 105, 4933–4939 (2001)

    Article  Google Scholar 

  53. G. Wu, Y. Katsumura, et al., “Temperature Dependence of Carbonate Radical in NaHCO3 and Na2CO3 Solutions: Is the Radical a Single Anion?,” Journal of Physical Chemistry A, Vol. 106, 2430–2437 (2002)

    Article  Google Scholar 

  54. M. Mostafavi, M. Lin, et al., “Pulse Radiolysis Study of Absorption Spectra of Ag0 and \( {\hbox{Ag}}_2^{+} \) in Water from Room Temperature up to 380°C,” Journal of Physical Chemistry A, Vol. 106, 3123–3127 (2002)

    Article  Google Scholar 

  55. G. Wu, Y. Katsumura, et al., “Temperature Dependence of Ketyl Radical in Aqueous Benzophenone Solutions up to 400°C: A Pulse Radiolysis Study,” Physical Chemistry Chemical Physics, Vol. 4, 3980–3988 (2002)

    Article  Google Scholar 

  56. M. Lin, Y. Katsumura, et al., “Pulse Radiolysis Study on the Estimation of Radiolytic Yields of Water Decomposition Products in High-Temperature and Supercritical Water: Use of Methyl Viologen as a Scavenger,” Journal of Physical Chemistry A, Vol. 109, 8287–8295 (2004)

    Article  Google Scholar 

  57. Y. Katsumura, K. Kiuchi, et al., “Fundamental R&D Program on Water Chemistry of Supercritical Pressure Water Under Radiation Field,” Proc. 2nd Int. Symp. on SCWR (SCR-2003), Tokyo, Japan, September 18–19, 2003, 1–6 (2003)

    Google Scholar 

  58. Y. Katsumura, K. Kiuchi, et al., “Research Program on Water Chemistry of Supercritical Pressure Water Under Radiation Field,” Proc. 14th Int. Conf. on the Properties of Water and Steam, Kyoto, Japan, August 29–September 3, 2004, 545–550 (2004)

    Google Scholar 

  59. T. Miyazaki, Y. Katsumura, et al., “Gamma-Radiolysis of Benzophenone Aqueous Solution at Elevated Temperatures up to Supercritical Condition,” Radiation Physics and Chemistry, Vol. 75, 218–228 (2006)

    Article  Google Scholar 

  60. N. Saito, Y. Tsuchiya, et al., “Chemical Thermodynamics Consideration on Corrosion Products in Supercritical-Water-Cooled Reactor Coolant,” Nuclear Technology, Vol. 155, 105–113 (2006)

    Google Scholar 

  61. T. Miyazaki, Y. Katsumura, et al., “Radiolysis of Phenol in Aqueous Solution at Elevated Temperatures,” Radiation Physics and Chemistry, Vol. 75, 408–415 (2006)

    Article  Google Scholar 

  62. Z. Han, Y. Katsumura, et al., “Effect of Temperature on the Absorption Spectra of the Solvated Electron in 1-Propanol and 2-Propanol: Pulse Radiolysis and Laser Photolysis Studies at Temperatures up to Supercritical Condition,” Radiation Physics and Chemistry, Vol. 77, 409–415 (2008)

    Article  Google Scholar 

  63. Z. Han and Y. Muroya, “Research and Development of a Super Fast Reactor (11) An Approach to Evaluate the Elution Characteristic of Stainless Materials in Subcritical and Supercritical Water,” Proc. 16th PBNC, Aomori, Japan, October 13–18, 2008, P16P1315 (2008)

    Google Scholar 

  64. Z. Han and Y. Muroya, “Development of a New Method to Study Elution Properties of Stainless Materials in Subcritical and Supercritical Water,” Proc. 4th Int. Symp. on SCWR, Heidelberg, Germany, March 8–11, 2009, Paper No. 75 (2009)

    Google Scholar 

  65. G. Heusener, U. Muller, T. Schulenberg and D. Square, “A European Development Program for a High Performance Light Water Reactor (HPLWR),” Proc. 1 st Int. Symp. on Supercritical Water-Cooled Reactors, Tokyo, Japan, November 6–9, 2000, Paper No. 102 (2000)

    Google Scholar 

  66. D. Squarer, D. Bittermann, et al., “Overview of the HPLWR Project and Future Direction,” Proc. ICAPP’03, Cordoba, Spain, May 4–7, 2003, Paper No. 3137 (2003)

    Google Scholar 

  67. D. Squarer, T. Schulenberg, et al., “High Performance Light Water Reactor,” Nuclear Engineering and Design, Vol. 221, 167–180 (2003)

    Article  Google Scholar 

  68. J. Starflinger, N. Aksan, et al., “Roadmap for Supercritical Water-Cooled Reactor R&D in Europe,” Proc. Global 2003, New Orleans, LA, November 16–20, 2003, 1137–1142 (2003)

    Google Scholar 

  69. J. Starflinger, T. Schulenberg, et al., “European Research Activities within the Project: High Performance Light Water Reactor Phase 2,” Proc. ICAPP’07, Nice, France, May 13–18, 2007, Paper No. 7416 (2007)

    Google Scholar 

  70. T. Schulenberg and J. Starflinger, “European Research Project on the High Performance Light Water Reactor,” Proc. 4th Int. Symp. on SCWR, Heidelberg, Germany, March 8–11, 2009, Paper No. 54 (2009)

    Google Scholar 

  71. J. Starflinger, T. Schulenberg, et al., “Results of the Mid-Term Assessment of the High Performance Light Water Reactor 2 Project,” Proc. ICAPP’09, Tokyo, Japan, May 10–14, 2009, Paper No. 9268 (2009)

    Google Scholar 

  72. T. Schulenberg, C. Maraczy, J. Heinecke and W. Bernnat, “Design and Analysis of a Thermal Core for a HPLWR – a State of the Art Review,” Proc. NURETH-13, Kanazawa, Japan, September 27–October 2, 2009, Paper N13P1039 (2009)

    Google Scholar 

  73. D. Brady, D. Duttey, et al., “Generation IV Reactor Development in Canada,” Proc. 3rd Int. Symp. on SCWR, Shanghai, China, March 12–15, 2007, SCR2007-P057 (2007)

    Google Scholar 

  74. D. Boyle, D. Brady, et al., “Canada’s Generation IV National Program – Overview,” Proc. 4th Int. Symp. on SCWR, Heidelberg, Germany, March 8–11, 2009, Paper No. 74 (2009)

    Google Scholar 

  75. C. K. Chow and H. F. Khartabil, “Conceptual Fuel Channel Designs for CANDU-SCWR,” Nuclear Engineering and Technology, Vol. 40(2), 139–146 (2008)

    Article  Google Scholar 

  76. H. F. Khartabil, “Review and Status of the Gen-IV CANDU-SCWR Passive Moderator Core Cooling System,” Proc. ICONE-16, Orlando, FL, May 11–15, 2008, ICONE16-48741 (2008)

    Google Scholar 

  77. D. Guzonas, et al., “Corrosion of Candidate Materials for Use in a Supercritical Water CANDU Reactor,” Proc. 13th Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, Whistler, BC (2007)

    Google Scholar 

  78. D. C. Groeneveld, S. Tavoularis, et al., “Analytical and Experimental Program of Supercritical Heat Transfer Research at the University of Ottawa,” Nuclear Engineering and Technology, Vol. 40(2), 107–116 (2008)

    Article  Google Scholar 

  79. V. Chatoorgoon, V. Shah, et al., “Linear Predictions of Supercritical Flow Stability in Parallel Channels,” Proc. 3rd Int. Symp. on SCWR, Shanghai, China, March 12–15, 2007, SCR2007-P097 (2007)

    Google Scholar 

  80. Y. Y. Bae, K. M. Bae, et al., “R&D on a Supercritical Pressure Water Cooled Reactor in Korea,” Proc. ICAPP’06, Reno, NV, June 4–8, 2006, Paper No. 6022 (2006)

    Google Scholar 

  81. Y. Y. Bae, K. M. Bae, et al., “SCWR Research in Korea,” Proc. 3rd Int. Symp. on SCWR, Shanghai, China, March 12–15, 2007, SCR2007-P006 (2007)

    Google Scholar 

  82. Y. Y. Bae, G. Jang, et al., “Research Activities on a Supercritical Pressure Water Reactor in Korea,” Nuclear Engineering and Technology, Vol. 39(4), 273–286 (2007)

    Article  Google Scholar 

  83. Y. Y. Bae, H. Y. Kim, et al., “Update on the SCWR Research in Korea,” Proc. 4th Int. Symp. on SCWR, Heidelberg, Germany, March 8–11, 2009, Paper No. 52 (2009)

    Google Scholar 

  84. S. Y. Hong, K. Lee, et al., “Interim Results of SCWR Development Feasibility Study in Korea,” Proc. 4th Int. Symp. on SCWR, Heidelberg, Germany, March 8–11, 2009, Paper No. 50 (2009)

    Google Scholar 

  85. H. K. Joo, J. W. Yoo and J. M. Noh, “A Conceptual Design for a Rectangular Fuel Assembly for the Thermal SCWR System,” Proc. Global 2003, New Orleans, LA, November 16–20, 2003, 1149–1154 (2003)

    Google Scholar 

  86. K. M. Bae, H. K. Joo and Y. Y. Bae, “Conceptual Design of a 1,400 MWe Supercritical Water Cooled Reactor Core with a Cruciform Type U/Zr Solid Moderator,” Proc. ICAPP’07, Nice, France, May 13–18, 2007, Paper No. 7502 (2007)

    Google Scholar 

  87. Y. B. Kim, S. M. Bae, et al., “Sensitivity Study of SCWR Core Design Concepts in Korea,” Proc. 16th PBNC, Aomori, Japan, October 13–18, 2008, P16P1132 (2008)

    Google Scholar 

  88. H. Y. Kim, H. Kim, et al., “Heat Transfer Test in a Vertical Tube Using CO2 at Supercritical Pressures,” Journal of Nuclear Science and Technology, Vol. 44(3), 1–9 (2007)

    MATH  Google Scholar 

  89. H. Y. Kim, H. Kim, et al., “Experimental Investigations on Heat Transfer to CO2 Flowing Upward in a Narrow Annulus at Supercritical Pressures,” Nuclear Engineering and Technology, Vol. 40(2), 155–162 (2008)

    Article  Google Scholar 

  90. H. Kim, H. Y. Kim, et al., “Heat Transfer to Supercritical Pressure Carbon Dioxide Flowing Upward Through Tubes and a Narrow Annulus Passage,” Progress in Nuclear Energy, Vol. 50, 518–525 (2008)

    Article  Google Scholar 

  91. H. Kim, Y. Y. Bae, et al., “Experimental Investigations on Heat Transfer Characteristics in Upward Flow of Supercritical Carbon Dioxide,” Nuclear Technology, Vol. 164, 119–129 (2008)

    Google Scholar 

  92. Y. Y. Bae and H. Y. Kim, “Convective Heat Transfer to CO2 at a Supercritical Pressure Flowing Vertically Upward in Tubes and an Annular Channel,” Experimental Thermal and Fluid Science, Vol. 33(2), 329–339 (2009)

    Article  Google Scholar 

  93. Y. Y. Bae, H. Y. Kim and T. Yoo, “Heat Transfer Experiments in a Wire-Inserted Tube at Supercritical Conditions,” Proc. 4th Int. Symp. on SCWR, Heidelberg, Germany, March 8–11, 2009, Paper No. 27 (2009)

    Google Scholar 

  94. X. Cheng, “R&D Activities on SCWR in China,” Proc. 4th Int. Symp. on SCWR, Heidelberg, Germany, March 8–11, 2009, Paper No. 53 (2009)

    Google Scholar 

  95. X. Cheng, X. J. Liu, et al., “A Mixed Core for Supercritical Water-Cooled Reactors, Nuclear Engineering and Technology, Vol. 40(1), 1–10 (2008)

    Article  Google Scholar 

  96. X. J. Liu and X. Cheng, “Coupled Thermal-Hydraulics and Neutron-Physics Analysis of SCWR with Mixed Spectrum Core,” Proc. 4th Int. Symp. on SCWR, Heidelberg, Germany, March 8–11, 2009, Paper No. 44 (2009)

    Google Scholar 

  97. J. Buongiorno, “The Supercritical Water Cooled Reactor: Ongoing Research and Development in the US,” Proc. ICAPP’04, Pittsburgh, PA, June 13–17, 2004, Paper No. 4229 (2004)

    Google Scholar 

  98. S. M. Modro, “The Supercritical Water Cooled Reactor Research and Development in the US,” Proc. ICAPP’05, Seoul, Korea, May 15–19, 2005, Paper No. 5694 (2005)

    Google Scholar 

  99. J. Buongiorno and P. Macdonald, “Supercritical Water Reactor (SCWR), Progress Report for the FY03 Generation-IV R&D Activities for the Development of the SCWR in the US,” INEEL/EXT03-03-01210, Idaho National Engineering and Environmental Laboratory (2003)

    Google Scholar 

  100. J. Licht, M. Anderson and M. Corradini, “Heat Transfer to Water at Supercritical Pressures,” Proc. ICAPP’07, Nice, France, May 13–18, 2007, Paper No. 7223 (2007)

    Google Scholar 

  101. J. Licht, M. Anderson and M. Corradini, “Heat Transfer to Water at Supercritical Pressures in Circular and Square Annular Flow Geometry,” International Journal of Heat and Fluid Flow, Vol. 29, 156–166 (2008)

    Article  Google Scholar 

  102. J. Licht, M. Anderson and M. Corradini, “Deterioration of Heat Transfer in Upward Flowing Supercritical Pressure Water,” Proc. ICAPP’09, Tokyo, Japan, May 10–14, 2009, Paper No. 9391 (2009)

    Google Scholar 

  103. G. Mignot, M. Anderson and M. Corradini, “Critical Flow Experiment and Analysis for Supercritical Fluid,” Nuclear Engineering and Technology, Vol. 40(2), 133–138 (2008)

    Article  Google Scholar 

  104. G. Mignot and M. Anderson, “Experimental Study of Supercritical CO2 depressurization,” Proc. International Workshop on Thermal-Hydraulics of Innovative Reactor and Transmutation Systems –THIRS, Karlsruhe, Germany, April 14–16, 2008, SC1 (2008)

    Google Scholar 

  105. G. Mignot, M. Anderson and M. Corradini, “Measurement of Supercritical CO2 Critical Flow: Effects of L/D and Surface Roughness,” Nuclear Engineering and Design, Vol. 239, 949–955 (2009)

    Article  Google Scholar 

  106. K. Sridharan, A. Zillmer, et al., “Corrosion Behavior of Candidate Alloys for Supercritical Water Reactors,” Proc. ICAPP’04, Pittsburgh, PA, USA, June 13–17, 2004, Paper No. 4136 (2004)

    Google Scholar 

  107. T. Allen, L. Tan, et al., “Corrosion and Radiation Response of Advanced Ferritic–Martensitic Steels for Generation IV Application,” Proc. Global 2005, Tsukuba, Japan, October 9–13, 2005, Paper No. IL001 (2005)

    Google Scholar 

  108. T. Allen, L. Tan, et al., “Corrosion of Ferritic–Martensitic Alloys in Supercritical Water for GenIV Application,” Proc. Global 2005, Tsukuba, Japan, October 9–13, 2005, Paper No. 419 (2005)

    Google Scholar 

  109. T. Allen, G. Was, et al., “Radiation Resistance of Advanced Ferritic–Martensitic Steel HCM12A,” Journal of ASTM international, Vol. 2(8), Paper ID JAI12382 (2005)

    Google Scholar 

  110. Y. Chen, K. Sridharan and T. Allen, “Corrosion Behavior of Ferritic/Martensitic Steel T91 in Supercritical Water,” Corrosion Science, Vol. 48(9), 2843–2854 (2006)

    Article  Google Scholar 

  111. L. Tan, Y. Yang and T. Allen. “Oxidation Behavior of Alloy HCM12A Exposed in Supercritical Water,” Corrosion Science, 48, 4234–4242 (2006)

    Article  Google Scholar 

  112. L. Tan, Y. Yang and Y. Allen, “Porosity Prediction in Supercritical Water Exposed Ferritic/Martensitic Steel HCM12A,” Corrosion Science, 48, 3123–3138 (2006)

    Article  Google Scholar 

  113. L. Tan, K. Sridharan and T. Allen, “The Effect of Grain Boundary Engineering on the Oxidation Behavior of INCOLOY Alloy 800H in Supercritical Water,” Journal of Nuclear Materials, Vol. 348, 263–271 (2006)

    Article  Google Scholar 

  114. X. Ren, K. Sridharan and T. Allen, “Corrosion of Ferritic–Martensitic Steel HT9 in Supercritical Water,” Journal of Nuclear Materials, Vol. 358, 227–234 (2006)

    Article  Google Scholar 

  115. Y. Chen, K. Sridharan, et al., “Microstructural Examination of Oxide Layers Formed on an Oxide Dispersion Strengthened Ferritic Steel Exposed to Supercritical Water,” Journal of Nuclear Materials, Vol. 359, 50–28 (2006)

    Article  Google Scholar 

  116. Y. Chen, K. Sridharan, et al., “Oxidation of 9Cr Oxide Dispersion Strengthened Steel Exposed in Supercritical Water,” Journal of Nuclear Materials, Vol. 371, 118–128 (2007)

    Article  Google Scholar 

  117. X. Ren, K. Sridharan and T. Allen, “Corrosion Behavior of Alloys 625 and 718 in Supercritical Water,” Corrosion, Vol. 63(7), 603–612 (2007)

    Article  Google Scholar 

  118. L. Tan, X. Ren, et al., “Effect of Shot-peening on the Oxidation of Alloy 800H exposed to Supercritical Water and Cyclic Oxidation,” Corrosion Science, 50, 2040–2046 (2008)

    Article  Google Scholar 

  119. L. Tan, X. Ren, et al., “Corrosion Behavior of Ni-base Alloys for Advanced High Temperature Water-Cooled Nuclear Plants,” Corrosion Science, 50, 3056–3062 (2008)

    Article  Google Scholar 

  120. T. Allen, K. Sridharan, et al., “Materials Development and Selection for Corrosion Resistance: A Critical Issue in Supercritical Water Reactors,” Proc. 16th PBNC, Aomori, Japan, October 13–18, 2008, P16P1032 (2008)

    Google Scholar 

  121. E. Edwards, D. Bartels, et al., “Radiation Chemical Yields of Water in Neutron and Gamma Radiation,” Transactions of ANS, 92, 125–126 (2005)

    Google Scholar 

  122. P. Humrickhouse, P. Wilson, et al., “Gamma Shield Design for the Supercritical Water Neutron Radiolysis Experiment,” Transactions of ANS, 92, 161–162 (2005)

    Google Scholar 

  123. E. Edwards, P. Wilson, et al., “University of Wisconsin Supercritical Water Loop Radiation Energy Deposition Calibration,” Transactions of ANS, 94, 533–534 (2006)

    Google Scholar 

  124. E. Edwards, P. Wilson, et al., “Radiation Chemistry Results from the Supercritical Water Loop at UW-Madison,” Transactions of ANS, 95, 939–940 (2006)

    Google Scholar 

  125. P. Wilson and P. Hu, “Accounting for Moderator Heating in Supercritical Water Reactor Analysis,” Transactions of ANS, 92, 520–521 (2005)

    Google Scholar 

  126. P. Wilson and P. Hu, “Reactor Analysis for Counter-flowing Moderator and Coolant in a Supercritical Water Reactor,” Proc. ICONE-14, July 17–20, 2006, Miami, FL, ICONE14-89392 (2006)

    Google Scholar 

  127. P. Hu and P. Wilson, “Core Flow Distribution from Coupled Supercritical Water Reactor Analysis,” Proc. 3rd Int. Symp. on SCWR, Shanghai, China, March 12–15, 2007, Paper No. SCWR2007-P058 (2007)

    Google Scholar 

  128. P. Hu and P. Wilson, “Supercritical Water Reactor Steady State, Burnup and Transient Analysis with Extended PARCS/RELAP5,” Proc. 4th Int. Symp. on SCWR, Heidelberg, Germany, March 8–11, 2009, Paper No. 13 (2009)

    Google Scholar 

  129. J. McKinley, S. Teysseyre, et al., “Corrosion and Stress Corrosion Cracking of Austenitic Alloys in Supercritical Water,” Proc. GENES4/ANP2003, Kyoto, Japan, September 15–19, 2003, Paper No. 1027 (2003)

    Google Scholar 

  130. G. Was, S. Teysseyre and J. McKinley, “Corrosion and Stress Corrosion Cracking of Iron- and Nickel-base Austenitic Alloys in Supercritical Water,” Proc. NACE’s Annual Conference, Corrosion 2004, New-Orleans, LA, USA, March 28–April 1, 2004, Paper No. 04492 (2004)

    Google Scholar 

  131. P. Ampornrat, C. Bahn and G. Was, “Corrosion and Stress Corrosion Cracking of Ferritic–Martensitic Alloys in Supercritical Water,” Proc. 12th Int. Conf. on Environmental Degradation of Materials in Nuclear Systems-Water Reactors, Salt Lake City, UT, August 14–18, 2005 (2005)

    Google Scholar 

  132. G. Was and S. Teysseyre, “Challenges and Recent Progress in Corrosion and Stress Corrosion Cracking of alloys for Supercritical Water Reactor Core Components,” Proc. 12th Int. Conf. on Environmental Degradation of Materials in Nuclear Systems-Water Reactors, Salt Lake City, UT, August 14–18, 2005 (2005)

    Google Scholar 

  133. G. Gupta and G. Was, “Effect of Proton Irradiation and GBE on SCC of F-M Alloys in SCW,” Proc. 12th Int. Conf. on Environmental Degradation of Materials in Nuclear Systems-Water Reactors, Salt Lake City, UT, August 14–18, 2005 (2005)

    Google Scholar 

  134. G. Was, S. Teysseyre, et al., “Corrosion of Austenitic Alloys in Supercritical Water,” Proc. NACE’s Annual Conference, Corrosion 2005, Houston TX, April 3–7, 2005, Paper No. 05397 (2005)

    Google Scholar 

  135. G. Gupta and G. Was, “The Role of Grain Boundary Engineering on the High Temperature Creep of Ferritic–Martensitic Alloy T91,” Journal of ASTM international, Vol. 2(3), Paper ID JAI12355 (2005)

    Google Scholar 

  136. G. Was, S. Teysseyre and Z. Jiao, “Corrosion of Austenitic Alloys in Supercritical Water,” Corrosion, Vol. 62(11), 989–1005 (2006)

    Article  Google Scholar 

  137. S. Teysseyre and G. Was, “Stress Corrosion Cracking of Austenitic Alloys in Supercritical Water,” Corrosion, Vol. 62(12), 1100–1116 (2006)

    Article  Google Scholar 

  138. G. Gupta, G. Was, et al., “Role of Grain Boundary Engineering in Mitigating Stress Corrosion Cracking of HT-9 in Supercritical Water,” Journal of Nuclear Materials, Vol. 361, 160–173 (2007)

    Article  Google Scholar 

  139. P. Ampornrat and G. Was, “Oxidation of Ferritic–Martensitic Alloys T91, HCM12A and HT-9 in Supercritical Water,” Journal of Nuclear Materials, Vol. 371, 1–17 (2007)

    Article  Google Scholar 

  140. S. Teysseyre, Q. Peng, et al., “Facility for Stress Corrosion Cracking of Irradiated Specimens in Supercritical Water,” Journal of Nuclear Materials, Vol. 371, 98–106 (2007)

    Article  Google Scholar 

  141. S. Teysseyre, Z. Jiao, et al., “Effect of Irradiation on Stress Corrosion Cracking In Supercritical Water,” Journal of Nuclear Materials, Vol. 371, 107–117 (2007)

    Article  Google Scholar 

  142. G. Was, P. Ampornrat, et al., “Corrosion and Stress Corrosion Cracking in Supercritical Water,” Journal of Nuclear Materials, Vol. 371, 176–201 (2007)

    Article  Google Scholar 

  143. J. Zhao, P. Saha and M. Kazimi, “Stability of Supercritical Water-Cooled Reactor During Steady-State and Sliding Pressure Start-up,” Proc. NURETH-11, Avignon, France, October 2–6, 2005, Paper No. 106 (2005)

    Google Scholar 

  144. J. Zhao, P. Saha and M. Kazimi, “Coupled Neutronic and Thermal-Hydraulic Out-of-Phase Stability of Supercritical Water Cooled Reactors,” Proc. ICAPP’06, Reno, NV, June 4–8, 2006, Paper No. 6424 (2006)

    Google Scholar 

  145. J. Zhao, P. Saha and M. Kazimi, “Hot Channel Stability of Supercritical Water-Cooled Reactors (Part I): Steady State and Sliding Pressure Startup,” Nuclear Technology, Vol. 158, 158–173 (2007)

    Google Scholar 

  146. J. Zhao, P. Saha and M. Kazimi, “Hot Channel Stability of Supercritical Water-Cooled Reactors (Part II): Effect of Water Rods Heating and Comparison with BWR Stability,” Nuclear Technology, Vol. 158, 174–190 (2007)

    Google Scholar 

  147. http://www.gen-4.org/PDFs/GenIVRoadmap.pdf

  148. S. León and N. Aksan, “IAEA Coordinated Research Programme on Heat Transfer Behavior and Thermo-Hydraulics Code Testing for Super Critical Water Cooled Reactors,” Proc. ICAPP’09, Tokyo, Japan, May 10–14, 2009, Paper No. 9482 (2009)

    Google Scholar 

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Authors and Affiliations

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Correspondence to Yoshiaki Oka .

Glossary

3YSZ

3 mol% yttria-stabilized zirconia

8YSZ

8 mol% yttria-stabilized zirconia

ANL

argonne national laboratory

BOP

balance of plant

BWR

boiling water reactor

CANDU

CANada Deuterium Uranium

CFD

computational fluid dynamics

CHF

critical heat flux

CRIEPI

Central Research Institute of Electric Power Industry

CRP

Coordinated Research Program

CSTWG

Chinese SCWR Technical Working Group

EUR

European Utility Requirement

FQ

fuel qualification

FPP

fusion power plant

FZK

Forschungszentrum Karlsruhe

GIF

Generation-IV International Forum

HIT

High fluence irradiation facility

HPLWR

High performance light water reactor

IAEA

International Atomic Energy Agency

IEM

information exchange meeting

I-NERI

International Nuclear Energy Initiative

INL

Idaho National Laboratory

JAEA

Japan Atomic Energy Agency

JMTR

Japan Material Test Reactor

JSPS

Japan Society for the Promotion of Science

KAERI

Korea Atomic Energy Research Institute

KEPRI

Korea Electric Power Research Institute

LDV

laser Doppler velocimetry

LOCA

loss of coolant accident

LWR

light water reactor

M&C

materials and chemistry

MEXT

Ministry of Education, Culture, Sports, Science and Technology

MHI

Mitsubishi Heavy Industry Ltd.

NERI

Nuclear Energy Research Initiative

NFD

Nuclear Fuel Development

NRCan

Natural Resources Canada

ODS

Oxide dispersion strengthening

PA

project agreement

PIE

post irradiation examination

PMB

project management board

PWR

pressure water reactor

R&D

research and development

RCM

Research Coordination Meeting

SA

system agreement

SCC

stress corrosion cracking

SCWR

supercritical water cooled reactor

SI&A

system integration and assessment

SJTU

Shanghai Jiao Tong University

SRP

system research plan

SRV

safety relief valve

SSC

system steering committee

SWAMUP

supercritical water multi-purpose test loop

TEPCO

Tokyo Electric Power Company

TH&S

thermal hydraulics and safety

TWG-LWR

Technical Working Groups on Advanced Technologies for LWR

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Oka, Y., Koshizuka, S., Ishiwatari, Y., Yamaji, A. (2010). Research and Development. In: Super Light Water Reactors and Super Fast Reactors. Springer, Boston, MA. https://doi.org/10.1007/978-1-4419-6035-1_8

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