HTGR Knowledge Base
IWGGCR--18: High temperature metallic materials for gas-cooled reactors
High temperature metallic materials for gas-cooled reactors. Proceedings of a specialists meeting held in Cracow, 20-23 June 1988
International Atomic Energy Agency, Vienna (Austria). International Working Group on Gas-Cooled Reactors, IWGGCR--18
Abstract
The Specialists' Meeting was organized in conjunction with an earlier meeting on this topic held in Vienna, Austria, 1981, which provided for a comprehensive review of the status of materials development and testing at that time and for a description of test facilities. This meeting provided an opportunity (1) to review and discuss the progress made since 1981 in the development, testing and qualification of high temperature metallic materials, (2) to critically assess results achieved, and (3) to give directions for future research and development programmes. In particular, the meeting provided a form for a close interaction between component designers and materials specialists. The meeting was attended by 48 participants from France, People's Republic of China, Federal Republic of Germany, Japan, Poland, Switzerland, United Kingdom, USSR and USA presenting 22 papers. The technical part of the meeting was subdivided into four technical sessions: Components Design and Testing - Implications for Materials (4 papers). Microstructure and Environmental Compatibility (4 papers). Mechanical Properties (9 papers). New Alloys and Developments (6 papers). At the end of the meeting a round table discussion was organized in order to summarize the meeting and to make recommendations for future activities. This volume contains all papers presented at the meeting.
view the full text of this conference report (format: PDF, size= 11358kB, 214 pages)
see also:
- Cover Pages (3 pages, format: PDF, size= 67kB )
- Index of Contents (2 pages, format: PDF, size= 81kB )
- Introduction and Summary of Sessions (7 pages, format: PDF, size= 325kB )
- List of Participants (1 page, format: PDF, size= 71kB )
Articles
Service conditions and relevant properties of HTGR metallic materials
Bodmann, E.; Diehl, H.; Blume-Firla, I.; Demus, H. (Hochtemperatur-Reaktorbau
GmbH, Mannheim (Germany, F.R.))
A proposal to develop a high temperature structural design guideline for HTGR components
Hada, K. (Japan Atomic Energy Research Inst., Naka, Ibaraki (Japan). HTTR
Designing Lab.)
Design requirements for high temperature metallic component materials in the US modular
HTGR
Shenoy, A.S.; Betts, W.S. (General Atomics, San Diego, CA (USA))
Structural integrity evaluation of a helically-coiled He/He intermediate heat exchanger
Okubo, M.; Hada, K.; Baba, O. (Japan Atomic Energy Research Inst., Naka,
Ibaraki (Japan). HTTR Designing Lab.)
Structural instabilities of high temperature alloys and their use in advanced high temperature gas
cooled reactors
Schuster, H.; Ennis, P.J.; Nickel, H. (Kernforschungsanlage Juelich GmbH
(Germany, F.R.). Inst. fuer Reaktorwerkstoffe); Czyrska-Filemonowicz, A.
(Akademia Gorniczo-Hutnicza, Cracow (Poland). Inst. Metalurgii)
Correlation between microstructure and the creep behaviour at high temperature of Alloy 800 H
Spiradek, K. (Institute of Nuclear Physics, Cracow (Poland)); Degischer, H.P.
(Aluminium Ranshofen GmbH, Ranshofen (Austria)); Lahodny, H.
(Max-Planck-Institut fuer Metallforschung, Stuttgart (Germany, F.R.))
Thermal stability and environmental compatibility of Inconel 617
Kimball, O.F. (Oak Ridge National Lab., Oak Ridge, TN (USA). Metals and
Ceramics Div.)
Corrosion behaviour of high temperature alloys in the cooling gas of high temperature reactors
Quadakkers, W.J.; Schuster, H. (Kernforschungsanlage Juelich GmbH (Germany,
F.R.). Inst. fuer Reaktorwerkstoffe)
Current status of studies on high temperature metallic materials for HTGR applications in JAERI
Tsuji, H.; Nakajima, H.; Kondo, T. (Japan Atomic Energy Research Inst., Naka,
Ibaraki (Japan). Dept. of Fuels and Materials Research)
High temperature low-cycle fatigue strength of Hastelloy-XR
Nagato, K.; Murakami, T.; Hashimoto, T. (Kawasaki Heavy Industries Ltd,
Tokyo (Japan). Nuclear Systems Div.)
Evaluation of mechanical properties of the alloy NiCr22Co12Mo (Alloy 617) for heat
exchanging components of HTGRs
Breitling, H.; Dietz, W. (Internationale Atomreaktorbau GmbH (INTERATOM),
Bergisch Gladbach (Germany, F.R.)); Penkalla, H.J. (Kernforschungsanlage
Juelich GmbH (Germany, F.R.). Inst. fuer Reaktorwerkstoffe)
Multiaxial creep of tubes of Alloy 800 and Alloy 617 at high temperature
Penkalla, H.J.; Schubert, F.; Nickel, H. (Kernforschungsanlage Juelich GmbH
(Germany, F.R.). Inst. fuer Reaktorwerkstoffe)
Fatigue properties of nickel-base high temperature alloys for HTGRs
Tsuji, H.; Nakajima, H. (Japan Atomic Energy Research Inst., Naka, Ibaraki
(Japan). Dept. of Fuels and Materials Research)
Post-service examination of a 10 MW helium-helium heat exchanger and comparison with long
term behaviour in laboratory tests
Cook, R.H.; Graham, L.W. (R.M. Detection Ltd, Poole, Dorset (UK). High
Temperature Materials Programme (HTMP)); Exner, R. (Balcke-Duerr AG,
Ratingen (Germany, F.R.))
Creep and fatigue crack growth in tubes of HTR components
Roedig, M.; Pfaffelhuber, M.; Schubert, F.; Nickel, H. (Kernforschungsanlage
Juelich GmbH (Germany, F.R.). Inst. fuer Reaktorwerkstoffe); Bodmann, E.
(Hochtemperatur-Reaktorbau GmbH, Mannheim (Germany, F.R.))
Fracture mechanical characteristic values (J-integral) with transference to components (tubes) by
an analytical method
Ullrich, G.; Alder, H.P. (Paul Scherrer Inst. (PSI), Wuerenlingen (Switzerland));
Huthmann, H.; Grueter, L. (Internationale Atomreaktorbau GmbH
(INTERATOM), Bergisch Gladbach (Germany, F.R.))
Fracture toughness of Alloy 800 H at room temperature
Krompholz, K.; Ullrich, G.; Alder, H.P. (Paul Scherrer Inst. (PSI), Wuerenlingen
(Switzerland)); Gnirss, G. (Asea Brown Boveri AG, Mannheim (Germany, F.R.));
Huthmann, H. (Internationale Atomreaktorbau GmbH (INTERATOM), Bergisch
Gladbach (Germany, F.R.)); Roedig, M.; Schubert, F. (Kernforschungsanlage
Juelich GmbH (Germany, F.R.). Inst. fuer Reaktorwerkstoffe)
The new alloy Thermon 4972 (NiCr22W12Fe) for high temperature components of gas-cooled
reactors
Huchtemann, B. (Thyssen Edelstahlwerke AG, Krefeld (Germany, F.R.))
Comparison of mechanical and corrosion behaviour of Alloy 800 H and the new alloy AC 66
Pelz, W. (Bergbau-Forschung GmbH, Essen (Germany, F.R.)); Schendler, W.;
Weber, H. (Mannesmann-Roehrenwerke AG, Duisburg (Germany, F.R.))
Experimental and theoretical work for the analysis of creep ratcheting and creep buckling of
HTR components
Breitbach, G.; Schubert, F.; Nickel, H. (Kernforschungsanlage Juelich GmbH
(Germany, F.R.). Inst. fuer Reaktorwerkstoffe); Seehafer, H.J. (Internationale
Atomreaktorbau GmbH (INTERATOM), Bergisch Gladbach (Germany, F.R.))
Development and validation of an improved creep-fatigue interaction rule for
lifetime determination of high temperature components
Lehmann, H.J.; Becker, M.; Luedeke, M. (Rheinisch-Westfaelischer Technischer
Ueberwachungs-Verein e.V., Essen (Germany, F.R.))
Wear stresses in ceramic layers at elevated temperatures under helium atmosphere
Fricker, U. (Sulzer Bros. Ltd., Winterthur (Switzerland)); Ullrich, G.; Alder, H.P.
(Paul Scherrer Inst. (PSI), Wuerenlingen (Switzerland))
Promising materials for HTGR high temperature heat exchangers
Kuznetsov, E.V.; Tokareva, T.B.; Ryabchenkov, A.V.; Novichkova, O.V.;
Starostin, Yu.D. (Tsentral'nyj Nauchno-Issledovatel'skij Inst. Tekhnologii
Mashinostroeniya, Moscow (USSR))
