Materials for the Very High Temperature Reactor (VHTR): A versatile nuclear power station for combined cycle electricity and heat production

Chimia

Volumn 59, Issue 12, 2005, Pages 977-982

  Hoffelner, Wolfgang ^a  

^a PAUL SCHERRER INSTITUTE   (Switzerland)

Author keywords

Gas cooled reactor; Generation IV; Helium gas turbine; High temperature materials; High temperature reactor; Hydrogen

Indexed keywords

EID: 30344439073     PISSN: 00094293     EISSN: None     Source Type: Journal    
DOI: 10.2533/000942905777675435     Document Type: Article

References (27)

1. A Technology Roadmap for Generation IV Nuclear Energy Systems, http://gif.inel.gov/roadmap/pdfs/gen_iv_roadmap.pdf, US DOE, December 2004.
2. F. Southworth, 'Very High Temperature gas Cooled Reactor Systems', http://gif.inel.gov/roadmap/pdfs/very_high_temp_gas_cooled_reactor_sys.pdf, 2002 Winter ANS Meeting, Washington DC, 2002.
3. S. Shiozawa, 'Present Status and Plan of Research and Development on HTTR and Hydrogen Production at JAERI', 3rd IPHE SC meeting, Paris, 27 January 2005, http://www.iphe.net/IPHE%20Paris/Thursday%20Presentations/IPHE%20(by%20Dr. %20Shiozawa).ppt.
4. J.-C. Gauthier, G. Brinkmann, B. Copsey, M. Lecomte, 'ANTARES the HTR/VHTR Project at Framatome ANP', http://www.iaea.org/inis/aws/htgr/fulltext/ htr2004 _a10.pdf, 2nd International Topical Meeting on High Temperature Reactor Technology, Paper A10, Beijing September 22-24, 2004.
5. T. Tanaka, O. Baba, S. Shiozawa, M. Okubo, K. Kunitomi, 'Construction of the HTTR and its Testing Program for Advanced HTGR Development', Technical committee meeting on design and development of gas cooled reactors with closed cycle gas turbines, Beijing (China), 30 Oct.-2 Nov. 1995, International Atomic Energy Agency, Vienna (Austria) IAEA-TECDOC - 899, pp: 15-23, see also http://www.iaea.org/inis/aws/htgr/fulltext/28008785.pdf.
6. Y. Sub, D. Zhong, Y. Xu, Z. Wu, 'The HTR-10 Test reactor and Potential use of HTGR for Non-electric Application in China', Advisory group meeting on non-electric applications of nuclear energy, Jakarta (Indonesia), 21-23 Nov. 1995, International Atomic Energy Agency, Vienna (Austria) IAEA-TECDOC - 923, pp: 211-222.
7. D. Matzner, 'PBMR Project Status and the Way Ahead', 2nd International Topical Meeting on HIGH TEMPERATURE REACTOR TECHNOLOGY, Beijing, China, September 22-24, 2004, Paper A04.
8. P.E. MacDonald, J.W. Sterbentz, P.D. Bayless, H.D. Gougar, R.L. Moore, A.M. Ougouag, W.K. Terry, NGNP Point Design, ICAPP 04, Pittsburgh, May 2004.
9. A.J. Neylan, F.A. Silday, B.P. Kohler, D. Lomba, R. Rose, 'Status of GT-MHR with Emphasis on the Power Conversion System', Technical committee meeting on design and development of gas cooled reactors with closed cycle gas turbines. Beijing (China), 30 Oct.-2 Nov. 1995, International Atomic Energy Agency, Vienna (Austria), IAEA-TECDOC - 899, pp: 55-66.
10. J. Chang, 'Status of Nuclear Hydrogen Production Project with a VHTR in South Korea', ICAPP-04 Pittsburgh, Conf. Proc., ICAPP, 2004, SK.
11. D.E. Buckthorpe, 'HTR materials & technologies (HTR Metallic Materials)', High Temperature Reactor School Cadarache (F), Nov. 4-8, 2002 HTR/ECS.
12. R. Viswanathan, W.T. Bakker, 'Materials for Ultrasupercritical Fossil Power Plants', TR-114750, EPRI, Palo Alto, CA, February, 2000.
13. S. Jitsukawa, M. Tamura, B. van der Schaaf, R.L. Klueh, A. Alamo, C. Petersen, M. Schirra, P. Spaetig, G.R. Odette, A.A. Tavassoli, K. Shiba, A. Kohyama, A. Kimura, 'Development of an extensive database of mechanical and physical properties for reduced-activation martensitic steel F82H', J. Nucl. Mat. 2002, 307-311, 179-186.
14. Y.A. Shtrombakh, B.A. Gurovich, P.A. Platonov, 'Radiation Damage of Graphite and Carbon-Graphite', J. Nucl. Mat. 1995, 225, 273-302.
15. W. Von Lensa, 'The Role of International Collaboration within the European High-Temperature Reactor-Technology Network (HTR-TN)', http://www.inet.tsinghua.edu.cn/english/HTR_meetings_S/file_doc/ownpp/5, Juelich, 2001.
16. M. Nazmy, M. Staubli, G. Onofrio, V. Lupine, 'Surface defect tolerance of cast TiAl alloy in fatigue', Scripta Materialia 2001, 45, 787-792.
17. 2 matrix composites', Materials Letters 2004, 58, 308-311.
18. 2 matrix composites with other silicon-base composite systems', Materials Science and Engineering 1999, A261, 53-63.
19. A.T. Motta, 'Amorphization of intermetallic compounds under irradiation - a review', J. Nucl. Mat. 1997, 244, 227-250.
20. A. Hishinuma, 'Radiation Damage of TiAl intermetallic alloys', J. Nucl. Mat. 1996, 239, 267-272.
21. M.Ishihara, T.Shibata, C.Wan, S.Baba, Y. Motohashi, T. Hoshiya, 'Effects of Superplastic Deformation on Thermal and Mechanical Properties of 3Y-TZP Ceramics', The Second Information Exchange Meeting on Basic Studies in the Field of High Temperature Engineering, Headquarters of Organisation for Economic Co-operation and Development Paris, France 10-12, October, 2001, p.17, http://www.nea.fr/html/science/htemp/iem2/abstracts/httr2-abstracts-for-dist-r0. pdf.
22. 'Status of Metallic Materials Development for Application in Advanced High-temperature Gas-cooled Reactors', Nuclear Technology, Vol. 66, No 1, July 1984;
23. Nuclear Technology, Vol 66, No. 2, August 1984;
24. Nuclear Technology, Vol. 66, No 3, September 1984.
25. S. Ahmaniemi, P. Vuoristo, T. Mäntylä, 'Thick Thermal Barrier Coatings - State-of-the-Art', Euroceram Newsletter, 2003, http://www.euroceram. com/en/news/news_7_4.cfm.
26. P. Billot, CEA Saclay, private communication, March 2004.
27. World Nuclear Association Annual Symposium, 3-5 September, 2003, London, Conf. Proc., World Nuclear Association, 2003, p. 1-15; see also http://www.world-nuclear.org/sym/2003/pdf/labar.pdf.