Advances in Energy Research

  • 제1권1호
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  • Pages.13-33
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  • 2013
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  • 2287-6316(pISSN)
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  • 2287-6324(eISSN)
테크노프레스 (Techno-Press)
권호 표지
DOI QR코드

DOI QR Code

Hydrogen production using high temperature reactors: an overview

  • Deokattey, Sangeeta (Scientific Information Resource Division, Bhabha Atomic Research Centre) ;
  • Bhanumurthy, K. (Scientific Information Resource Division, Bhabha Atomic Research Centre) ;
  • Vijayan, P.K. (Reactor Engineering Division, Bhabha Atomic Research Centre) ;
  • Dulera, I.V. (Reactor Engineering Division, Bhabha Atomic Research Centre)
  • 투고 : 2012.10.27
  • 심사 : 2013.03.12
  • 발행 : 2013.03.25
⟨ 이전 논문 다음 논문 ⟩

초록

The present work is an attempt to provide an overview, about the status of R&D and current trends in Hydrogen Production using High Temperature Reactors. Bibliographic references from the INIS database, the Science Direct database and the NTIS database were downloaded and analyzed. Ten year data on the subject, published between 2001 and 2010, was selected for the study. Appropriate qued ry formulations on these databases, resulted in the retrieval of 621 unique bibliographic records. Using the content analysis method, all the records were analyzed. Part One of the analysis details Scientometric R&D indicators, Part Two is a subject-based analysis, grouped under: A. International Initiatives and Programmes for Hydrogen Production; B. European R&D initiatives for Hydrogen production; C. National Initiatives and Programmes for Nuclear Hydrogen Production; D. Reactor Technologies for Nuclear Hydrogen production; E. Fuel Developments; F. Hydrogen Production Processes using HTRs and G. Materials Consideration for Nuclear Hydrogen Production. The results of this analysis are summarized in the study.

키워드

참고문헌

  1. Abdesselam, A., Noirault, S. and Grambow, B. (2006), "Immobilization of inert TRISO-coated fuel in glass for geological disposal", J. Nucl. Mater., 358(1),1-9. https://doi.org/10.1016/j.jnucmat.2006.04.015
  2. Bing, L.B., Liang, T. and Tang, C. (2006), "A review of TRISO-coated particle nuclear fuel performance models", Rare Met., 25(6) Supplement 1, 337-342.
  3. Buckthorpe, D., Breuil, E. and Besson, D. (2007), "RAPHAEL: materials and components highlights from the HTR FP5 and FP6 programmes", Proceedings of the INIS-FR--08-1008, ICAPP 2007 - International Congress on Advances in Nuclear Power Plants. The Nuclear Renaissance at Work, Nice Acropolis (France), 13-18 May.
  4. Cabet, C. and Rouillard, F. (2009), "Corrosion of high temperature metallic materials in VHTR", J. Nucl. Mater., 392(2), 235-242. https://doi.org/10.1016/j.jnucmat.2009.03.029
  5. Cerri, G. et al. (2010), "Sulfur-Iodine plant for large scale hydrogen production by nuclear power", Int. J. Hydrogen Energy, 35 (9), 4002-14. https://doi.org/10.1016/j.ijhydene.2010.01.066
  6. Chang, J. et al. (2009), Development of the log-in process and the operation process for the VHTR-SI process dynamic simulation code, spring meeting of the Korean Nuclear Society, Jeju (Republic of Korea) 18-23 May.
  7. Chang, J.H. et al. (2007), "A study of a nuclear hydrogen production demonstration plant", Nucl. Eng. Technol., 39(2), 111-122. https://doi.org/10.5516/NET.2007.39.2.111
  8. Chang, J.H., Kang, H.S. and Gil, C.S. (2006), Preliminary conceptual design and development of core technology of very high temperature gas-cooled reactor hydrogen production, Korea Atomic Energy Research Institute, Taejon (Republic of Korea), Report Number KAERI/RR--2666/2005.
  9. Chi, S.H. and Kim, G.C. (2006), Mrozowski cracks and oxidation behavior Of IG-110 And IG-430 nuclear graphites, spring meeting of the KNS Gapyoung (Republic of Korea) 25-26 May, Korean Nuclear Society, Taejon (Republic of Korea), Proc. of the KNS spring meeting Taejon (Republic of Korea) KNS.
  10. COE-INES (2006), "A general survey of the potential and the main issues associated with the sulfur-iodine thermochemical cycle for hydrogen production using nuclear heat", Prog. Nucl. Energy, 50(2-6), 402-410. Innovative Nuclear Energy Systems for Sustainable Development of the World, Proc. of the Second COE-INES International Symposium, INES-2, November 26-30. Yokohama, Japan.
  11. Copsey, B. et al. (2004), "The framatome ANP indirect-cycle very high temperature reactor", Proceedings of the 2004 international congress on advances in nuclear power plants - ICAPP'04 La Grange Park (United States), American Nuclear Society, ANS 2004, 310-320.
  12. Kim, D.J., Sah, I.J. and Jang, C.H. (2010), "Effects of high temperature aging in an impure helium environment on low temperature embrittlement of Alloy 617 and Haynes 230", J. Nucl. Mater., 405(1), 9-16. https://doi.org/10.1016/j.jnucmat.2010.07.026
  13. Elder, R. and Ray, A. (2009), "Nuclear heat for hydrogen production: coupling a very high/high temperature reactor to a hydrogen production plant", Prog. Nucl. Energy, 51, 500-25. https://doi.org/10.1016/j.pnucene.2008.11.001
  14. Fabrice, G., Abdesselam, A. and Grambow, B. (2010), "HTR fuel waste management: TRISO separation and acid-graphite intercalation compounds preparation", J. Nucl. Mater., 407(2), 71-77. https://doi.org/10.1016/j.jnucmat.2010.09.026
  15. Fachinger, J. et al. (2006), "Behaviour of spent HTR fuel elements in aquatic phases of repository host rock formations", Nucl. Eng. Des., 236 (5-6),543-554. https://doi.org/10.1016/j.nucengdes.2005.11.023
  16. Fazio, C. et al. (2009), "European cross-cutting research on structural materials for Generation IV and transmutation systems", J. Nucl. Mater., 392(2), 316-323. https://doi.org/10.1016/j.jnucmat.2009.03.020
  17. Flores, F.A., Nelson, E.P.F. and Francois, L.J.L. (2005), "Probabilistic analysis of safety of a production plant of hydrogen using nuclear energy", Instituto Nacional de Investigaciones Nucleares, Ocoyoacac, Estado de Mexico (Mexico). 16. Annual Congress of the SNM; 23. Annual Meeting of the SMSR Oaxaca (Mexico) 10-13 July.
  18. Fukada, S. and Nobutaka, H. (2010), Heat pump cycle by hydrogen-absorbing alloys to assist high-temperature gas-cooled reactor in producing hydrogen, DOI :10.1787/9789264087156-46-en, OECD Library, 407-415.
  19. Greneche, D. and Szymczak, W.J. (2006), "The AREVA HTR fuel cycle: an analysis of technical issues and potential industrial solutions", Nucl. Eng. Des., 236(5-6), 635-642. https://doi.org/10.1016/j.nucengdes.2005.10.022
  20. Hittner, D. et al. (2007), "HTR-TN achievements and prospects for future developments"- HTR2008-58249", International Congress on Advances in Nuclear Power Plants, ICAPP 2007, The Nuclear Renaissance at Work, Nice Acropolis (France), 13-18 May.
  21. Hodotsuka, M., Yang, X. and Okuda, H. (2007), "Study on vapor-liquid equilibrium of hydriodic acid for thermochemical hydrogen production IS process", ICONE-15, International Congress on Nuclear Engineering Nagoya, Aichi (Japan), 22-26 April.
  22. Hong, J.K. et al. (2004), "Corrosion test of materials for I-S process in boiling sulfuric acid", autumn meeting of the KNS Yongpyong (Republic of Korea) 28-29 Oct., Korean Nuclear Society, Taejon (Republic of Korea), Proc. of the KNS autumn meeting.
  23. Hong, S.D. et al. (2005), "Conceptual design of a small scale high temperature and high pressure gas poop", Korea Atomic Energy Research Institute, Taejon (Republic of Korea), autumn meeting of the KNS Busan (Republic of Korea) 27-28 Oct., Korean Nuclear Society, Taejon (Republic of Korea) Proceedings of the KNS autumn meeting Taejon (Republic of Korea) KNS.
  24. Ichimiya, K. et al. (2006), "Thermal performance of a circular tube filled with a high porous material", Nippon-Kikai-Gakkai-Ronbunshu, 72(723), 2747-2752.
  25. INIS Database (2001-2010), Vienna, International Atomic Energy Agency, 2011, http://www.iaea.org/INIS.
  26. Ishikura S. et al. (2008), "Thermomechanical simulation of SiC-Block-Made sulfuric acid decomposer", Nippon-Genshiryoku-Gakkai-Wabun-Ronbunshi, 7(2), 134-141. https://doi.org/10.3327/taesj.J07.015
  27. Ishiyama, S. (2003), "Electricity and hydrogen multi production process with new solid electrolyte for HTGR (1). Tri-generation process into thermal-electricity-chemical energy", Nippon-Genshiryoku-Gakkai-Wabun-Ronbunshi, 2(1), 14-23. https://doi.org/10.3327/taesj2002.2.14
  28. Ishiyama, S. (2003), "Study on HIx cycling techniques for thermo chemical hydrogen production process. R and D on refractory and corrosion resistant pressure sensor for hydrogen iodide cycling test loop", Nippon-Kikai-Gakkai-Ronbunshu, 69(686), 1510-1516.
  29. Ishiyama, S. (2004), "R and D on sulfuric acid ceramic evaporator for nuclear. Heat chemical IS hydrogen Production Plant", HYDROGEN 2004, world hydrogen energy conference Yokohama, Kanagawa Japan) 27 Jun - 2 July, Proceedings of the 15th world hydrogen energy conference.
  30. Jang, J. et al. (2007), "Development of a visualization program for a distillation column for VHTR-assisted hydrogen production systems", spring meeting of the KNS Jeju (Republic of Korea) 10-11 May.
  31. Jeong, H.S. et al. (2002), "Enthalpy analysis of hydrogen production processes", 2002 joint spring meeting of the KNS-KARP Gwangju (Republic of Korea) 23-24 May, Korean Nuclear Society, Korean Association for Radiation Protection, Seoul (Republic of Korea), Proc. of the KNS-KARP Joint spring meeting Taejon (Republic of Korea) KNS.
  32. Jo, C.K. and Noh, J.M. (2007), "Preliminary core design analysis of a 200mwth pebble bed-type VHTR", spring meeting of the KNS Jeju (Republic of Korea) 10-11 May, Korean Nuclear Society, Daejeon (Republic of Korea), Proc. of the KNS spring meeting Daejeon (Republic of Korea) KNS.
  33. Jun, S.Y. et al. (2010), "Numerical prediction of the fission product plate-out for a VHTR application", Ann. Nucl. Energy, 37(4), 471- 481. https://doi.org/10.1016/j.anucene.2010.01.009
  34. Kanagawa, A. (2007), "Development of $SO_3$ decomposer for thermochemical hydrogen production by IS process. Basic of Sic plate-type $SO_3$ decomposer and catalyst test results", Japan Atomic Energy Agency Technical Report, JAEA-Technology-2007-043, Ibaraki, Japan.
  35. Kang, H.S. et al. (2008), "Sensitivity calculations on spark ignition model for a CFD analysis of the JAEA explosion test in the open space", Korea Atomic Energy Research Institute, 2008 Spring Meeting of the KNS Kyeongju (Republic of Korea) 29-30 May.
  36. Kasahara, S., Kubo, S. and Ogawa, M. (2005), "R and D of the thermochemical hydrogen production using nuclear heat from high temperature gas-cooled reactor", Dennetsu, 44(188), 25-30.
  37. Kasahara, S. et al. (2007), Study of purification methods for produced hydrogen by the HTTR-IS system, Japan Atomic Energy Agency, Ibaraki, 40 p. JAEA-Technology-2007-040.
  38. Kasahara, S. et al. (2003), "Thermal efficiency of the IS process for thermochemical hydrogen production using the HTGR", GENES4/ANP2003: International conference on global environment and advanced nuclear power plants, Kyoto, Japan, 15-19 September, Session 12, Technology of Hydrogen Production, Paper 1038.
  39. Kawasaki, K. et al. (2005), "Achievement of coolant temperature of 950 degree C in HTTR", (Japan Atomic Energy Research Institute, Department of HTTR Project, Oarai-machi (Japan), International conference on nuclear engineering Beijing (China), 16-20 May, Abstracts, Atomic Energy Press, Beijing, China, 197p.
  40. Kazuhiko, K. and Xing,Y. (2004), "Deployment of GTHTR300 cogeneration for hydrogen and electric generation", Department of Advanced Nuclear Heat Technology, Japan Atomic Energy Research Institute, ICAPP'04: 2004 international congress on advances in nuclear power plants Pittsburgh, PA (United States) 13-17 June.
  41. Khamis, I. (2011), "Non-electric applications of nuclear reactors", IAEA, Department of Nuclear Energy, Vienna, Austria.
  42. Kim, C.H. (2004), "Preliminary study on coupling high temperature gas cooled reactor with hydrogen production systems", autumn meeting of the KNS Yongpyong (Republic of Korea) 28-29, Oct., Korean Nuclear Society, Taejon (Republic of Korea), Proc. of the KNS autumn meeting Taejon (Republic of Korea), 171-172.
  43. Kim, C.S. et al. (2007), "Effect of catalyst on thermal design of a lab-acale $SO_3$ decomposer for nuclear hydrogen production", spring meeting of the KNS Jeju (Republic of Korea) 10-11 May, Proc. of the KNS spring meeting, Daejeon (Republic of Korea) KNS.
  44. Kim, D.H et al. (2005), "Benchmark calculations for graphite-moderated reactors using different evaluated nuclear data", spring meeting of the KNS Jeju (Republic of Korea) 26-27 May, Korean Nuclear Society, Taejon (Republic of Korea), Proc. of the KNS spring meeting Taejon (Republic of Korea) KNS.
  45. Kim, E.S., Oh, C.H. and Patterson, M. (2010), "Study on the tritium behaviors in the VHTR system. Part 1. Development of tritium analysis code for VHTR and verification", Nucl. Eng. Des., 240(7), 1758-1767. https://doi.org/10.1016/j.nucengdes.2010.02.023
  46. Kim, H.C. et al. (2005), "Monte Carlo benchmark calculations for HTR-10 initial core", autumn meeting of the KNS Busan (Republic of Korea) 27-28 Oct., Korean Nuclear Society, Taejon (Republic of Korea), Proc. of the KNS autumn meeting Taejon (Republic of Korea) KNS.
  47. Kim, H.C. et al. (2007), "Monte Carlo benchmark calculations for 400mwth PBMR core", spring meeting of the KNS Jeju (Republic of Korea) 10-11 May, Korean Nuclear Society, Daejeon (Republic of Korea), Proc. of the KNS spring meeting Daejeon (Republic of Korea) KNS.
  48. Kim, J.B. et al. (2006), "Current status of the elevated temperature structure design codes for VHTR", autumn meeting of the KNS Kyongju (Republic of Korea) 2-3 Nov., Korean Nuclear Society, Taejon (Republic of Korea), Proc. of the KNS autumn meeting Taejon (Republic of Korea) KNS.
  49. Kim, J.H. et al. (2008), "Simulation of a secondary system for the small-scale test loop", spring meeting of the Korean Nuclear Society, Kyeongju (Republic of Korea) 29-30 May.
  50. Kim, J.H. et al. (2009), "Hydrogen iodide decomposer sizing for a nuclear hydrogen production by SI process", autumn meeting of the KNS. Kyungju (Republic of Korea). 29-30 Oct.
  51. Kim, M.H., Lee, W.J. and Chang, J.H. (2006), "A CFD assessment of a compact high temperature heat exchanger", Korea Atomic Energy Research Institute, Taejon (Republic of Korea), spring meeting of the KNS Gapyoung (Republic of Korea) 25-26, May, Korean Nuclear Society, Taejon (Republic of Korea), Proc. of the KNS spring meeting Taejon (Republic of Korea) KNS.
  52. Kim, Y.W. et al. (2006), "A plate-fin type $SO_3$ decomposer for a nuclear hydrogen production system", (Korea Atomic Energy Research Institute, Taejon (Republic of Korea) CA: autumn meeting of the KNS Kyongju (Republic of Korea) 2-3 Nov., Proc. of the KNS autumn meeting Taejon (Republic of Korea) KNS.
  53. Kim, Y.W. et al. (2007), "Stress fields for a coated surface of an SO Sub 3 decomposing heat exchanger in a nuclear hydrogen production system", spring meeting of the KNS Jeju (Republic of Korea) 10-11 May.
  54. Kosmidou, T. and Haehner, P. (2009), "Advanced construction materials for thermo-chemical hydrogen production from VHTR process heat", Joint EC-IAEA topical meeting on development of new structural materials for advanced fission and fusion reactor systems, Barcelona (Spain), 5-9 Oct., Report Number: INIS-XA--09N1699.
  55. Kubo, S. et al. (2004), "A pilot test plan of the thermochemical water-splitting iodine-sulfur process", Nucl. Eng. Des., 233(1-3), 355-362. https://doi.org/10.1016/j.nucengdes.2004.08.018
  56. Le Duigou, A. et al. (2006), "HYTHEC: aims and first assessments of an EC funded project on massive scale hydrogen production via thermochemical cycles", INIS-FR--6858, World Hydrogen Energy Conference, Lyon (France), 13-16 June.
  57. Lee, K.J. (2005), "A study on the analysis of source term evaluation method and tritium behavior mechanism", Korea Atomic Energy Research Institute, Daejeon (Republic of Korea), 175 p. KAERI/CM--891/2005.
  58. Lee, K.Y. et al. (2007), "Technical integration of nuclear hydrogen production technology", Korea Atomic Energy Research Institute, Daejeon (Republic of Korea), 284 p. KAERI/RR--2821/2006.
  59. Lee, H.C. et al. (2009), "Decay heat analysis of a VHTR core by Monte Carlo core depletion calculation", The Nuclear Fuel Cycle: Sustainable Options and Industrial Perspectives Paris (France) 6-11 Sep., Societe Francaise d'Energie Nucleaire, Proceedings of the GLOBAL 2009 congress.
  60. Lee, W.J., Noh, J.M. and Kim, K.S. (2006), "Development of very high temperature reactor design technology", Korea Atomic Energy Research Institute, Daejeon (Republic of Korea), May, KAERI/RR--2753/2006.
  61. Lee, W.J. (2009), "Progress of nuclear hydrogen program in Korea", Nuclear Hydrogen Workshop 'Nuclear Hydrogen for Green Horizon' Jeju (Republic of Korea) 20 May, Korea Nuclear Society, Daejeon (Republic of Korea); Korea Atomic Energy Research Institute. Proc. of the 3rd Nuclear Hydrogen Workshop 'Nuclear Hydrogen for Green Horizon' Daejeon (Republic of Korea) KNS.
  62. Lim, H.S., Lee, S.W. and Lee, W.J. (2007), "Safety characteristics of the circular and annular pebble-cores for a 200mwth prototype VHTR for a hydrogen production", spring meeting of the KNS Jeju (Republic of Korea), 10-11 May.
  63. Maeda, Y. et al. (2005), "Development of dynamic analysis code for HTTR hydrogen production system", Japan Atomic Energy Research Inst., Ibaraki, 158 p. JAERI-Data/Code--2005-001.
  64. Martin, B. et al. (2007), "Development of design and simulation model and safety study of large-scale hydrogen production using nuclear power", NTIS Technical Report, DE2008-921148, 296p.
  65. Matts, R. et al. (2007), "Thermal hydraulic optimization of a VHTR block-type core", ICONE-15, international conference on nuclear engineering, Nagoya, Aichi (Japan) 22-26 Apr 2007, Japan Society of Mechanical Engineers, Tokyo (Japan), Proc. of the ICONE-15 (Rev.).
  66. Min, H.K., Nam, I.T. and Hong, S.L. (2010), "Thermal-fluid assessment of the design options for reactor vessel cooling in a prismatic core VHTR", Ann. Nucl. Energy, 37(12), 1774 -1782. https://doi.org/10.1016/j.anucene.2010.08.007
  67. Morris, R.N. et al. (2008), Next generation nuclear plant phenomena identification and ranking tables (Pirts), 3, Fission-Product Transport And Dose PIRTS, US Nuclear Regulatory Commission, Washington, NUREG/CR-6944-V3.
  68. Murakami, T. et al. (2006), "Analysis on characteristic of hydrogen gas dispersion and evaluation method of blast overpressure in VHTR hydrogen production system", Nippon-Genshiryoku-Gakkai-Wabun- Ronbunshi, 5(4), 316-324. https://doi.org/10.3327/taesj2002.5.316
  69. Murakami, T., Nishihara, T. and Kunitomi, K. (2008), "Safety assessment of VHTR hydrogen production system against fire, explosion and acute toxicity", Nippon-Genshiryoku-Gakkai-Wabun-Ronbunshi, 7(3), 231-241. https://doi.org/10.3327/taesj.J07.039
  70. Nam, IlT, (2008), "Thermo-fluid investigation on a double-side-cooled annular fuel for the prismatic very high temperature gas-cooled reactor", Nucl. Eng. Des., 238 (10), 2821- 2827. https://doi.org/10.1016/j.nucengdes.2008.05.008
  71. Nariaki, S., Hirofumi, O. and Tetsuaki, T. (2006), "Hydrogen permeation through heat transfer pipes made of Hastelloy XR during the initial $950^{\circ}C$ operation of the HTTR", J. Nucl. Mater., 353 (1-2), 42-51. https://doi.org/10.1016/j.jnucmat.2006.03.008
  72. National Technical Reports Library (NTRL): National Technical Information Service (NTIS) Database (2001-2010), Virginia, US Dept. of Commerce, 2011.
  73. Nishihara, T. (2005), "Analytical study on hydrogen dispersion in the HTGR hydrogen production system", Japan Atomic Energy Research Inst., GLOBAL 2005: International conference on nuclear energy systems for future generation and global sustainability Tsukuba, Ibaraki (Japan) 9-13, Oct.
  74. Nishihara, T. (2004), "Development of high temperature isolation valve for the HTTR hydrogen production system", Nippon-Genshiryoku-Gakkai-Wabun-Ronbunshi, 3(4), 381-387. https://doi.org/10.3327/taesj2002.3.381
  75. Nishihara, T. and Takeda, T. (2005), "Study on introduction scenario of the high temperature gas-cooled reactor hydrogen cogeneration system", (GTHTR300C), Part 1, Japan Atomic Energy Research Inst., Ibaraki, 26 p. (JAERI-Tech--2005-049).
  76. Nishihara, T. et al. (2003), "Study on system layout and component design in the HTTR hydrogen production system", Japan Atomic Energy Research Inst., Ibaraki, 54 p. (JAERI-Tech--2002-101).
  77. No, H.C. et al. (2009), "Horizon expansion of thermal-hydraulic activities into HTGR safety analysis including gas-turbine cycle and hydrogen plant", Nucl. Eng. Technol., 41(7), 875-884. https://doi.org/10.5516/NET.2009.41.7.875
  78. Noguchi, H. et al. (2007), "Shakedown of sulfuric acid flow test loop for thermo-chemical hydrogen production technology by IS process", Japan Atomic Energy Agency Technical Report, JAEA-Technology--2007-054, Ibaraki, Japan.
  79. Noguchi, H. et al. (2010), "Operation test of sulfuric acid flow test loops", Nippon Genshiryoku Gakkai Wabun Ronbunshi, 9(3), 288-295. https://doi.org/10.3327/taesj.J09.038
  80. OECD (2000), "Nuclear production of hydrogen", First Information Exchange Meeting, Paris, France, 2-3 Oct., OECD Publishing, Paris.
  81. OECD (2003), "Nuclear production of hydrogen", Second Information Exchange Meeting, Argonne, Illinois, USA, 2-3 Oct., OECD Publishing, Paris.
  82. OECD Nuclear Energy Agency, (2010), "Conceptual design of the HTTR-IS nuclear hydrogen production system: detection of the heat transfer tube rupture in intermediate heat exchanger", OECD Nucl. Energy, 4 (9), 336-344.
  83. OECD Nuclear Science Committee (2005), "OECD/NEA/+NSC PBMR coupled neutronics/thermal hydraulics transient benchmark: the PBMR-400 core design", First Workshop Summary Record, NEA/NSC/DOC/2005 (13).
  84. Ogawa, M. and Shiozawa, S. (2002), "Present status of research and development on high temperature gascooled reactor system", Enerugi,-Shigen, 23(6), 412-416.
  85. Oh, C.H. (2007), "HyPEP FY-07 Report: Initial calculations of component sizes, quasi-static, and dynamics analyses", NTIS Technical Report, DE2008-915538, 89p.
  86. Oh, C.H. and Kim, E.S. (2009), "Method and system for the production of hydrogen at reduced VHTR outlet temperatures", Idaho National Laboratory, NURETH-13: 13. International Topical Meeting on Nuclear Reactor Thermal Hydraulics Kanazawa (Japan) 27 Sep. - 2 Oct., Report Number INL/CON--09-16111.
  87. Oh, C.H. et al. (2007), "High temperature gas-cooled reactor coupled with high tmperature steam electrolysis", American Institute of Chemical Engineers, Spring National Meeting Houston, TX (United States) 22-27 Apr.
  88. Oh, C.H. et al. (2007), "Steam generator component model in a combined cycle of power conversion unit for very high temperature gas-cooled reactor", NTIS Technical Report, Virginia, DE2008-912895, 8p.
  89. Ohashi, H. et al. (2004), "Simulation test on normal start-up and shutdown of HTTR hydrogen production system using mock-up model test facility", NUTHOS-6; international topical meeting on nuclear reactor thermal hydraulics, operations and safety, Nara (Japan) 4-8 Oct., Atomic Energy Society of Japan, Tokyo (Japan), Proc., 13 p.
  90. Ohashi, H. et al. (2007), "Numerical study on tritium behavior by using isotope exchange reactions in thermochemical water-splitting iodine-sulfur process", J. Nucl. Sci. Technol., 44(11), 1407-1420. https://doi.org/10.1080/18811248.2007.9711388
  91. Ohashi, H. et al. (2009), "Hydrogen iodide processing section in a thermochemical water-splitting iodine-sulfur process using a multistage hydrogen iodide decomposer", Nippon-Genshiryoku-Gakkai- Wabun-Ronbunshi, 8(1), 68-82. https://doi.org/10.3327/taesj.J08.010
  92. Pappano, P.J. et al. (2008), "A novel approach to fabricating fuel compacts for the next generation nuclear plant (NGNP)", J. Nucl. Mater., 381 (1-2), 25-38. https://doi.org/10.1016/j.jnucmat.2008.07.032
  93. Park, J.H. et al. (2006), "Improvement of homogeneity of the Zrc film by controlling the vaporizer temperature", autumn meeting of the KNS Kyongju (Republic of Korea) 2-3 Nov., Korean Nuclear Society, Taejon (Republic of Korea) Proc. of the KNS autumn meeting Taejon (Republic of Korea), KNS.
  94. Park, Won-Seok, Chang, Jong-Hwa and Park, Chang-Ku (2004), "Status of experimental data for the VHTR core design", Korea Atomic Energy Research Institute, Taejon (Republic of Korea), 68 p. KAERI/AR--702/2004.
  95. Ravenswaay, J.P. et al. (2009), "Status and planning of South Africa's nuclear hydrogen production program", Nuclear Hydrogen Workshop 'Nuclear Hydrogen for Green Horizon', Jeju (Republic of Korea) 20 May, Proc. of the 3rd Nuclear Hydrogen Workshop 'Nuclear Hydrogen for Green Horizon' Daejeon (Republic of Korea) KNS.
  96. Richards, M. (2006), "Modular helium reactor for hydrogen production", NTIS Technical report. NTIS, Virginia, DE2007-911857.
  97. Sakaba, N. et al. (2008), "Examination on small-sized cogeneration HTGR for developing countries", Japan Atomic Energy Agency, Tokai, Ibaraki (Japan), 66 p. JAEA-Technology--2008-019.
  98. Sakaba, N. et al. (2008), "Hydrogen production by high-temperature gas-cooled reactor. Conceptual design of advanced process heat exchangers of the HTTR-IS hydrogen production system", Nippon-Genshiryoku-Gakkai-Wabun-Ronbunshi, 7(3), 242-256. https://doi.org/10.3327/taesj.J07.037
  99. Science Direct Database (2001-2010).
  100. Seo, D.U. et al. (2009), "Modeling of a high temperature sulfuric acid loop using aspen plus", autumn meeting of the KNS, Kyungju (Republic of Korea), 29-30 Oct.
  101. Seo, D.U. et al. (2009), "Modeling of a high temperature sulfuric acid loop using aspen plus", autumn meeting of the Korean Nuclear Society, Kyungju (Republic of Korea), 29-30 Oct.
  102. Sherman, S.R. (2007), "Nuclear reactor/hydrogen process interface including the HyPEP model", NTIS Technical Report, Virginia, DE2007-912461, 9p.
  103. Shin, Y.J., Jeong, H.S. and Jang, J.H. (2003), "Evaluation of the methane-methanol-methanal cycle for nuclear hydrogen production", autumn meeting of the KNS Yongpyong (Republic of Korea) 30-31, Oct. Korean Nuclear Society, Taejon (Republic of Korea), Proc. of the KNS autumn meeting Taejon (Republic of Korea) KNS.
  104. Shusaku, S. et al. (2001), "Present status of JAERI'S R and D on hydrogen production systems in HTGR", First information exchange meeting nuclear production of hydrogen, Paris (France) 2-3 Oct. 2000. Organisation for Economic Co-Operation and Development, Nuclear Energy Agency, Paris, 57-69.
  105. Somolova, M. et al. (2008), "Preliminary analyses on hydrogen diffusion through small break of thermo-chemical IS process hydrogen plant", Japan Atomic Energy Agency Technical Report. JAEA-TECHNOLOGY--2008-003, Ibaraki, Japan.
  106. Song, K.N. et al. (2007), "Conceptual design on the main components for NHDD program", (Korea Atomic Energy Research Institute, Daejon (Republic of Korea)), CA: ICONE-15: international conference on nuclear engineering, Nagoya, Aichi (Japan) 22-26 Apr.
  107. Steinbruck, M. et al. (2008), "Status of studies on high-temperature oxidation and quench behaviour of zircaloy-4 and E110 cladding alloys", ERMSAR-2008, Paper 2, The 3rd European Review Meeting on Severe Accident Research, Nesseber, Bulgaria, 23-25 Sep. Contract: SARNET FI6O-CT-2004-509065.
  108. Tae, H.W. and Un, C.L. (2009), "Passive system reliability in the nuclear power plants (NPPs) using statistical modeling", Nucl. Eng. Des., 239(12), 3014- 3020. https://doi.org/10.1016/j.nucengdes.2009.08.002
  109. Taiju, S. (2008), "Non-destructive evaluation methods for degradation of IG-110 and IG-430 graphite", J. Nucl. Mater., 381(1-2),165-170. https://doi.org/10.1016/j.jnucmat.2008.07.014
  110. Takeda, T. and Ichimiya, K. (2007), "Applicability of heat transfer enhancement method using porous material to nuclear hydrogen production system", Japan Atomic Energy Agency, ICONE-15: 15. International Conference on Nuclear Engineering, Nagoya, Aichi (Japan), 22-26 Apr.
  111. Takeda, T. and Iwatsuki, J. (2001), "Study on mutual permeation of hydrogen isotope through metal. Mutual permeation of hydrogen and deuterium through Inconel 600", Japan Atomic Energy Research Inst., Ibaraki, 24 p. (JAERI-Research--2000-057).
  112. Takeda, T., Iwatsuki, J. and Nishihara, T. (2002), "Study on hydrogen isotope permeation in the HTTR hydrogen production system. 2. Effectiveness of reducing the amount of permeated deuterium by oxidized film", Japan Atomic Energy Research Inst., Ibaraki, 51 p. (JAERI-Tech--2002-090).
  113. Terada, A. and Hino, R. (2007), "Development of hydraulic analysis code for optimizing thermo-chemical IS process reactors", ICONE-15, international conference on nuclear engineering Nagoya, Aichi (Japan), 22-26 Apr.
  114. UKAEA and OECD/NEA (2004), "IRPhE-DRAGON-DPR, OECD high temperature reactor dragon project", Primary Documents, Available at: http://www.nea.fr/abs/html/nea-726.html.
  115. Vandel, D. (2007), "Next generation nuclear plant system requirements manual", Idaho National Laboratory, Idaho Falls, Department of Energy, Washington, DC. Technical Report No. INLEXT0712999.
  116. Verfondern, K. and von Lensa, W. (2006), "Michelangelo network recommendations on nuclear hydrogen production", Int. J. Nucl. Hydr. Prod. Appl., 1(1), 68-78.
  117. Vilim, R.B. (2007), "Initial assessment of the operability of the VHTR-HTSE nuclear hydrogen plant", NTIS Technical report, NTIS, Virginia, DE2008-919345.
  118. VIlim, R. (2009), "NGNP/HTE full-power operation at reduced high-temperature heat exchanger temperatures", NTIS Technical Report, Virginia, DE2009-951249, 33p.
  119. Wang, Z.L. et al. (2010), "Comparison of sulfur-iodine and copper-chlorine thermochemical hydrogen production cycles", Int. J. Hydrogen Energy, 35(10), 4820-4830. https://doi.org/10.1016/j.ijhydene.2009.09.006
  120. Wu, Z., Lin, D. and Zhong, D. (2002), "The design features of the HTR-10", Nucl. Eng. Des., 218 (1-3), 25-32. https://doi.org/10.1016/S0029-5493(02)00182-6
  121. Yin, H., Jiang, S. and Zhang, Y. (2006), "Numerical analysis of steam reformer of steam methane reforming hydrogen production system connected with high temperature gas cooled reactor", Nucl. Power Eng., 27(3),102-107.
  122. Yin, H., Jiang, S. and Zhang, Y. (2006), "Initial study on steam reformer of high-temperature gas-cooled reactor powered steam methane reforming hydrogen production system", At. Energy Sci. Technol., 40(4), 406-410.
  123. Yin, H. et al. (2007), "Modeling of the helium-heated steam reformer for HTR-10", J. Nucl. Sci. Technol., 44(7), 977-984. https://doi.org/10.1080/18811248.2007.9711337
  124. Yoon, C. et al. (2009), "CFD analysis of a very high temperature helium heater in the VHTR simulated experimental loop", autumn meeting of the KNS, Kyungju (Republic of Korea), 29-30, Oct.
  125. Zhang, Z. et al. (2006), "Design aspects of the Chinese modular high-temperature gas-cooled reactor TR-PM", Nucl. Eng. Des., 236(5-6) , 485-490. https://doi.org/10.1016/j.nucengdes.2005.11.024

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