Skip to main content
Fachgebiete
Automobil + Motoren Bauwesen + Immobilien Business IT + Informatik Elektrotechnik + Elektronik Energie + Nachhaltigkeit Finance + Banking Management + Führung Marketing + Vertrieb Maschinenbau + Werkstoffe Versicherung + Risiko
DE
EN
Themenseiten
Organisationspsychologie Projektmanagement Marketing Smart Manufacturing
Bücher
Zeitschriften
Weitere Formate
Podcasts Webinare Technik Webinare Wirtschaft Kongresse Veranstaltungskalender Awards
Jetzt Einzelzugang starten
Zugang für Unternehmen
Referenzkunden
MTZ-Fachkongress

Antriebe und Energiesysteme von morgen


Austausch von Automobil- und Energiewirtschaft

Am 14./15. Mai geht es in Chemnitz um die Mobilitätswende durch Elektro- und Wasserstofffahrzeuge.
Erweiterte Suche
Anmelden
nach oben
Steel in Translation
Erschienen in: Steel in Translation 4/2019

01.04.2019

Creep Resistance of Ferrite–Martensite Steel for Nuclear Reactors

verfasst von: M. Yu. Belomyttsev, V. G. Molyarov

Erschienen in: Steel in Translation | Ausgabe 4/2019

Einloggen

Aktivieren Sie unsere intelligente Suche, um passende Fachinhalte oder Patente zu finden.

search-config
loading …

Abstract

High-temperature ferrite–martensite steels with 12% Cr are characterized by high strength and creep resistance at 600–750°C. In the high-safety BREST reactor, 16Kh12MVSFBR (EP-823) steel is used to manufacture fuel-rod casings. Literature data regarding its mechanical characteristics in tensile tests at 20–750°C are available, as well as limited information regarding the long-term strength, but nothing has been reported regarding its creep rate. In the present work, the creep of EP-823 steel is investigated for 3-kg samples from three melts. Cylindrical samples (~5–6 mm) undergo compressive tests in air at 600–760°C, under a stress of 70–310 MPa. In the compressive tests, the duration is no more than 11 h. The structure after quenching and tempering consists of tempered martensite and some (6–12 vol %) δ ferrite, with grains no larger than 20 μm. The experimental data and the approximation for the creep are in better agreement when plotted in logarithmic coordinates (log σ–log έ) than in semilogarithmic coordinates (σ–log έ). Analysis of the results in terms of the Hollomon equation PS =(T/1000)[CS – log(έ)] and the Larson–Miller equation PE = (T/1000)[CE – log(σ)] yields formulas for the creep rate at specified stress (100–220 MPa) in the form log(έ) = –19.355 + 9.17(T/1000)log (σ); and for the creep limits with specified tolerances on the creep rate (0.1–1%/h) in the form log(σ) = 4.304 – 0.109(T/1000)(20 – log(έ)). Similar results are obtained in calculating the creep limits and creep rates by the pair models and the Hollomon (Larson–Miller) models, but the Hollomon models are preferable because they take account of all three variables. The results of control tests in identical tensile conditions are presented. It is shown that, in determining the strength characteristics, there is a linear relation between the results of the compressive and tensile tests: σ0.2co = 1.3 σ0.2te. Analysis of the creep indicates that the creep rate for steel of the same type (09Kh12V3BR) and the same melt, with different loading (tension or compression) are similar, whereas the creep rate for steel of the same type (EP-823 steel) and different melts may differ by an order of magnitude even in the same loading conditions (compression).
Vorheriger Artikel Improving Cylindrical Inconel 718 Ingots Produced at PAO Ruspolimet
Nächster Artikel Kinematics of Metallurgical Cutters with Parallel Blades

Sie haben noch keine Lizenz? Dann Informieren Sie sich jetzt über unsere Produkte:

Springer Professional "Wirtschaft+Technik"

Online-Abonnement

Mit Springer Professional "Wirtschaft+Technik" erhalten Sie Zugriff auf:

  • über 102.000 Bücher
  • über 537 Zeitschriften

aus folgenden Fachgebieten:

  • Automobil + Motoren
  • Bauwesen + Immobilien
  • Business IT + Informatik
  • Elektrotechnik + Elektronik
  • Energie + Nachhaltigkeit
  • Finance + Banking
  • Management + Führung
  • Marketing + Vertrieb
  • Maschinenbau + Werkstoffe
  • Versicherung + Risiko

Jetzt Wissensvorsprung sichern!

Jetzt informieren

Springer Professional "Technik"

Online-Abonnement

Mit Springer Professional "Technik" erhalten Sie Zugriff auf:

  • über 67.000 Bücher
  • über 390 Zeitschriften

aus folgenden Fachgebieten:

  • Automobil + Motoren
  • Bauwesen + Immobilien
  • Business IT + Informatik
  • Elektrotechnik + Elektronik
  • Energie + Nachhaltigkeit
  • Maschinenbau + Werkstoffe




 

Jetzt Wissensvorsprung sichern!

Jetzt informieren
Literatur
1.
Beskorovainyi, N.M., Kalin, B.A., Platonov, P.A., and Chernov, I.I., Konstruktsionnye materialy yadernykh reaktorov (Constructional Materials of Nuclear Reactors), Moscow: Energoatomizdat, 1995.
2.
Solonin, M.I., Reshetnikov, F.G., Ioltukhovskii, A.G., and Nikulina, A.V., New constructional materials for active zones of nuclear power installations, Fiz. Khim. Obrab. Mater., 2001, no. 4, pp. 17–27.
3.
Fiziko-energeticheskii institut: letopis’ v sud’bakh (Institute of Physics and Power Engineering: Chronicles in People’s Destiny), Zrodnikov, A.V., Ed., Obninsk: Fiz.-Energ. Inst. im. A.I. Leypunskogo, 2006.
4.
Klueh, R. and Harries, D., High-Chromium Ferritic and Martensitic Steels for Nuclear Applications, American Society for Testing and Materials Monograph Series vol. 3, West Conshohocken, PA: ASTM Int., 2001.CrossRef
5.
Yan, W., Wang, W., Shan, Y., Yang, K., and Sha, W., 9–12Cr Heat-Resistant Steels, New York: Springer-Verlag, 2015.CrossRef
6.
Gerasimov, V.V. and Monakhov, A.S., Materialy yadernoi tekhniki. Uchebnik dlya vuzov (Materials of Nuclear Equipment: Manual for Higher Education Institutions), Moscow: Energoatomizdat, 1982.
7.
Beskorovainyi, N.M., Belomyttsev, Yu.S., Abramovich, M.D., Ivanov, V.K., and Shulepov, V.I., Konstruktsionnye materialy yadernykh reaktorov. Chast’ 2. Struktura, svoistva, naznacheniya (Constructional Materials for Nuclear Reactors, Part 2: Structure, Properties, and Application), Moscow: Atomizdat, 1977.
8.
Ibragimov, Sh.Sh., Kirsanov, V.V., and Pyatiletov, Yu.S., Radiatsionnye povrezhdeniya metallov i splavov (Irradiation Damage of Metals and Alloys), Moscow: Energoatomizdat, 1985.
9.
Klueh, R.L., Elevated temperature ferritic and martensitic steels and their application to future nuclear reactors, Int. Mater. Rev., 2004, vol. 50, pp. 287–310.CrossRef
10.
Kalin, B.A., Platonov, P.A., Tuzov, Yu.V., Chernov, I.I., and Shtrombakh, Ya.I., Fizicheskoe materialovedenie. Uchebnik dlya vuzov. Tom 6. Konstruktsionnye materialy yadernoi tekhniki (Physical Material Science: Manual for Higher Education Institutions, Vol. 6: Constructional Materials for Nuclear Power Industry), Kalin, B.A., Ed., Moscow: Nats. Issled. Yad. Univ.,–Mosk. Inzh.-Fiz. Inst., 2012.
11.
Frost, B.R.T., Nuclear Fuel Elements: Design, Fabrication and Performance, New York: Pergamon, 1982.
12.
Lanskaya, K.A., Vysokokhromistye zharoprochnye stali (High-Chromium Heat Resistant Steels), Moscow: Metallurgiya, 1976.
13.
Khimushin, F.F., Nerzhaveyushchie stali (Stainless Steels), Moscow: Metallurgiya, 1967.
14.
Votinov, S.N., Golovin, I.S., and Kolotushkin, V.P., Development of perspective materials for fuel rods cover of nuclear reactors on fast neutrons, in Atomnye elektrostantsii Rossii. 60 let atomnoi promyshlennosti (Atomic Power Stations of Russia: 60 Years of the Nuclear Industry), Moscow, 2005, pp. 313–335.
15.
Mal’tsev, V.V., Ogorodov, A.M., Roslyakov, V.F., Sergeev, G.A., and Sheinkman, A.G., Operating experience of fuel rods and fuel assembly wrappers (FAW) of reactor BN-600, Trudy Mezhdunarodnoi konferentsii po radiatsionnomu materialovedeniyu, Alushta, 22–25 maya 1990 g. (Proc. Int. Conf. on Radiating Material Science, Alushta, May 22–25, 1990), Kharkov: Khark. Fiz.-Tekh. Inst., 1990, vol. 4, pp. 105–112.
16.
Tselishchev, A.V., Ageev, V.S., Budanov, Yu.P., and Mitrofanova, N.M., Development of structural steel for fuel elements and fuel assemblies of sodium-cooled fast reactors, At. Energy, 2010, vol. 108, no. 4, pp. 274–280.CrossRef
17.
Solonin, M.I., Ioltukhovskii, A.G., Bibilashvili, Yu.K., Leont’eva-Smirnova, M.V., Medvedeva, E.A., Mitrofanova, N.M., Budanov, Yu.P., Chernov, V.M., and Tselishchev, A.V., Problems of creation and development of stainless steels for details of active zones of nuclear reactors on fast neutrons and of thermonuclear reactor of synthesis, Fiz. Khim. Obrab. Mater., 2001, no. 5, pp. 5–13.
18.
Dvoriashin, A.M., Porollo, S.I., Konobeev, Yu.V., and Garner, F.A., Influence of high dose neutron irradiation on microstructure of EP-450 ferritic–martensitic steel irradiated in three Russian fast reactors, J. Nucl. Mater., 2004, vols. 329–333, pp. 319–323.CrossRef
19.
Odette, G.R., Alinger, M.J., and Wirth, B.D., Recent developments in irradiation-resistant steels, Annu. Rev. Mater. Res., 2008, vol. 38, pp. 471–503.CrossRef
20.
Kupriiyanova, Y.E., Bryk, V.V., Borodin, O.V., Kalchenko, A.S., Voyevodin, V.N., Tolstolutskaya, G.D., and Garner, F.A., Use of double and triple-ion irradiation to study the influence of high levels of helium and hydrogen on void swelling of 8–12% Cr ferritic-martensitic steels, J. Nucl. Mater., 2016, vol. 468, pp. 264–273.CrossRef
21.
Rusanov, A.E., Troyanov, V.M., Belomyttsev, Yu.S., and Shulepin, S.V., Development and research of covering steels for fuel rods of nuclear power stations with heavy heat carrier, Materialy konferentsii “Tyazhelye zhidkometallicheskie teplonositeli v yadernykh tekhnologiyakh” (Proc. Conf. “Heavy Liquid-Metal Heat Carriers for Nuclear Technologies”), Obninsk: Fiz.-Energ. Inst. im. A.I. Leypunskogo, 1999, vol. 2, pp. 673–685.
22.
Roy, A.K. and Hossain, M.K., Cracking of martensitic alloy EP-823 under controlled potential, J. Mater. Eng. Perform., 2006, vol. 15, no. 3, pp. 336–344.CrossRef
23.
Maloy, S.A., Romero, T., and James, M.R., Tensile testing of EP-823 and HT-9 after irradiation in STIP II, J. Nucl. Mater., 2006, vol. 356, nos. 1–3, pp. 56–61.CrossRef
24.
Voyevodin, V.N., Karpov, S.A., Kopanets, I.E., Ruzhytskyi, V.V., Tolstolutskaya, G.D., and Garner, F.A., Influence of displacement damage on deuterium and helium retention in austenitic and ferritic-martensitic alloys considered for ADS service, J. Nucl. Mater., 2016, vol. 468, pp. 274–280.CrossRef
25.
Ioltukhovskii, A.G., Leont’eva-Smirnova, M.V., Chernov, V.M., Tsvelev, V.V., Solonin, M.I., Golovanov, V.N., and Shamardin, V.K., Development of new-generation high-temperature 12% chromium steel 16Kh12V2FTaR with rapid decline of the induced activity for the atomic power engineering of Russia, Met. Sci. Heat Treat., 2002, vol. 44, nos. 11–12, pp. 482–486.CrossRef
26.
Ioltukhovskiy, A.G., Blokhin, A.I., Budylkin, N.I., Chernov, V.M., Leont’eva-Smirnova, M.V., Mironova, E.G., Medvedeva, E.A., Solonin, M.I., Porollo, S.I., and Zavyalsky, L.P., Material science and manufacturing of heat-resistant reduced-activation ferritic-martensitic steels for fusion, J. Nucl. Mater., 2000, vols. 283–287, pp. 652–656.CrossRef
27.
Ioltukhovskiy, A.G., Leonteva-Smirnova, M.V., Solonin, M.I., Chernov, V.M., Golovanov, V.N., Shamardin, V.K., Bulanova, T.M., Povstyanko, A.V., and Fedoseev, A.E., Heat resistant reduced activation 12% Cr steel of 16Cr12W2VTaB type-advanced structural material for fusion and fast breeder power reactors, J. Nucl. Mater., 2002, vols. 307–311, pp. 532–535.CrossRef
28.
Ioltukhovskii, A.G., Leont’eva-Smirnova, M.V., Chernov, V.M., Tsvelev, V.V., Solonin, M.I., Golovanov, V.N., and Shamardin, V.K., Development of heat resisting 12% chromic steel 16Cr12W2VTaB of new generation with fast recession of the induced activity for needs of atomic engineering of Russia, Vopr. At. Nauki Tekh., Ser.: Fiz. Radiats. Povrezhdenii Radiats. Materialoved., 2003, no. 6. pp. 60–64.
29.
Nikitina, A.A., Ageev, V.S., Chukanov, A.P., Tsvelev, V.V., Porezanov, N.P., and Kruglov, O.A., R&D of ferritic-martensitic steel EP450 ODS for fuel pin claddings of prospective fast reactors, J. Nucl. Mater., 2012, vol. 428, pp. 117–124.CrossRef
30.
Klueh, R.L., Ehrlich, K., and Abe, F., Ferritic/martensitic steels: promises and problems, J. Nucl. Mater., 1992, vol. 191, pp. 116–124.
31.
Roy, A.K., Kukatla, S.R., Yarlagadda, B., Potluri, V.N., Lewis, M., and O’Toole, B., Tensile properties of martensitic stainless steels at elevated temperatures, J. Mater. Eng. Perform., 2005, vol. 14, no. 2, pp. 212–218.CrossRef
32.
Porollo, S.I., Dvoriashin, A.M., Konobeev, Yu.V., and Garner, F.A., Microstructure and mechanical properties of ferritic/martensitic steel EP-823 after neutron irradiation to high doses in BOR-60, J. Nucl. Mater., 2004, vols. 329–333, pp. 314–318.CrossRef
33.
Maloy, S.A., Romero, T., James, M.R., and Dai, Y., Tensile testing of EP-823 and HT-9 after irradiation in STIP II, J. Nucl. Mater., 2006, vol. 356, pp. 56–61.CrossRef
34.
Dragunov, Yu.G., Zubchenko, A.S., Kashirskii, Yu.V., Degtyarev, A.F., Zharov, V.V., Koloskov, M.M., Orlov, A.S., and Skorobogatykh, V.N., Marochnik stalei i splavov (Handbook of Grades of Steels and Alloys), Dragunov, Yu.G. and Zubchenko, A.S., Eds., Moscow: Mashinostroenie, 2015.
35.
Leont’eva-Smirnova, M.V., Agafonov, A.N., Ermolaev, G.N., Ioltukhovskii, A.G., Mozhalov, E.M., Reviznikov, L.I., Tsvelev, V.V., Chernov, V.M., Bulanova, T.M., Golovanov, V.N., Ostrovskii Z.O., Shamardin V.K., Blokhin A.I., Ivanov M.B., Kozlov E.V., et al., Microstructure and mechanical properties of reduced-activated ferritic-martensitic steel EK-181 (RUSFER-EK-181), Perspekt. Mater., 2006, no. 6, pp. 40–52.
36.
Solonin, M.I., Ioltukhovskii, A.G., Leont’eva-Smirnova, M.V., Bibilashvili, Yu.K., Golovanov, V.N., Kondrat’ev, V.P., Chernov, V.M., and Shamardin, V.K., RF Patent 2211878, 2003.
37.
Ye, Z., Wang, P., Li, D., Zhang, Y., and Li, Y., Effect of carbon and niobium on the microstructure and impact toughness of a high silicon 12% Cr ferritic/martensitic heat resistant steel, Mater. Sci. Eng., A, 2014, vol. 616, pp. 12–19.CrossRef
38.
Zelenskii, G.K., Ioltukhovskii, A.G., Leont’eva-Smirnova, M.V., Naumenko, I.A., and Tolkachenko, S.A., Corrosion resistance of fuel element steel cladding in a lead coolant, Met. Sci. Heat Treat., 2007, vol. 49, nos. 11–12, pp. 533–538.CrossRef
39.
Ye, Z., Wang, P., Li, D., and Li, Y., M23C6 precipitates induced inhomogeneous distribution of silicon in the oxide formed on high-silicon ferritic/martensitic steel, Scr. Mater., 2015, vol. 97, pp. 45–48.CrossRef
40.
Bobkov, V.P., Blokhin, A.I., Rumyantsev, V.N., Solov’ev, V.A., and Tarasikov, V.P., Spravochnik po svoistvam materialov dlya perspektivnykh reaktornykh tekhnologii. Tom 5. Svoistva reaktornykh stalei i splavov (Handbook on Properties of Materials for Prospective Nuclear Power Technologies, Vol. 5: Properties of Nuclear Reactor Steels and Alloys), Poplavskii, V.M., Ed., Moscow: IzdAT, 2014.
41.
Vatulin, A.V., Constructional and fuel materials of active zones of nuclear reactors (condition and direction of development), in Toplivnyi tsikl yadernoi energetiki Rossii. Nauchnye problemy i perspektivy (The Fuel Cycle of Nuclear Power in Russia: Scientific Problems and Prospects), Moscow: Vysokotekhnol. Nauchno-Issled. Inst. Neorg. Mater., 2006, pp. 113–130.
42.
Ioltukhovskii, A.G., Lanskaya, K.A,. Belomyttsev, Yu.S., and Saratovskii, L.N., Investigation of heat treatment conditions of 12%-chromic steel EP-823 with reference to operating conditions of fuel assembly wrappers (FAW) of reactor BN-600, Vopr. At. Nauki Tekh., Ser.: At. Materialoved., 1985, no. 2 (19), pp. 65–70.
43.
Bibilashvili, Yu.K., Ioltukhovskii, A.G., Kazennov, Yu.I., Budanov, Yu.P., and Chernov, V.M., Service characteristics of 12% chromic steels with reference to operating conditions of elements of active zones of nuclear reactors with lead and lead-bismuth heat carrier, Materialy konferentsii “Tyazhelye zhidkometallicheskie teplonositeli v yadernykh tekhnologiyakh” (Proc. Conf. “Heavy Liquid-Metal Heat Carriers for Nuclear Technologies”), Obninsk: Fiz.-Energ. Inst. im. A.I. Leypunskogo, 1999, vol. 2, pp. 782–791.
44.
Ioltukhovskii, A.G., Leont’eva-Smirnova, M.V., Ageev, V.S., Golovanov, V.N., Kondrat’ev, V.P., Shamardin, V.K., and Chernov, V.M., Influence of initial structural condition on propensity of 12% of chromic steel to embrittlement under irradiation, Tret’ya mezhotraslevaya konferentsiya po reaktornomu materialovedeniyu, Dmitrovgrad, 27–30 oktyabrya 1992 g. (The Third Interbranch Russian Conf. on Reactor Material Science, Dimitrovgrad, October 27–30, 1994), Dmitrovgrad: Nauchno-Issled. Inst. At. Reakt., 1994, vol. 2, pp. 56–68.
45.
Khabarov, V.S. and Porollo, S.I., Influence of initial heat treatment on mechanical properties of irradiated ferritic-martensitic steels EI-842, EP-450 and EP-823, Materialy Pyatoi mezhotraslevoi konferentsii po reaktornomu materialovedeniyu, Dmitrovgrad, 8–12 sentyabrya, 1997 g. (Proc. 5th Interbranch Conf. on Reactor Material Science, Dimitrovgrad, September 8–12, 1997), Dmitrovgrad: Nauchno-Issled. Inst. At. Reakt., 1998, vol. 2, part 2, pp. 123–135.
46.
Rozenberg, V.M., Osnovy zharoprochnosti metallicheskikh materialov (Fundamentals of Heat Resistance of Metal Materials), Moscow: Metallurgiya, 1973.
47.
Shtremel’, M.A., Prochnost’ splavov. Chast’ 2: Deformatsiya (Strength of Alloys, Part 2: Deformation), Moscow: Mosk. Inst. Stali Splavov, 1999.
48.
Shlyakman, B.M., Yampol’skii, O.N., and Ratushev, D.V., A method for determining constant C in the Hollomon parameter, Met. Sci. Heat Treat., 2011, vol. 52, nos. 9–10, pp. 451–453.CrossRef
49.
Obraztsov, S.M., Shimkevich, A.L., Obraztsov, S.M., and Shimkevich, A.L., Bootstrap-identification of exponential dependence, Zavod. Lab., 2000, vol. 66, no. 1, pp. 62–64.
50.
Belomyttsev, M.Yu. and Mordashov, S.V., Short-term creep of St3 steel, Steel Transl., 2015, vol. 45, no. 11, pp. 815–818.CrossRef
Metadaten
Titel
Creep Resistance of Ferrite–Martensite Steel for Nuclear Reactors
verfasst von
M. Yu. Belomyttsev
V. G. Molyarov
Publikationsdatum
01.04.2019
Verlag
Pleiades Publishing
Erschienen in
Steel in Translation / Ausgabe 4/2019
Print ISSN: 0967-0912
Elektronische ISSN: 1935-0988
DOI
https://doi.org/10.3103/S0967091219040028

Weitere Artikel der Ausgabe 4/2019

Steel in Translation 4/2019 Zur Ausgabe

OriginalPaper

Improved Electrical Control of Ladle–Furnace Units by Means of Arc-Current Harmonics

OriginalPaper

Kinematics of Metallurgical Cutters with Parallel Blades

OriginalPaper

Stabilizing the Stress State of Wire in Drawing under Countertension with Variable Frictional Coefficient

OriginalPaper

Improving Cylindrical Inconel 718 Ingots Produced at PAO Ruspolimet

OriginalPaper

Influence of Vanadium on Carbide Deposition in the Working Layer of ICDP Iron Rollers

OriginalPaper

Production of Heavy Plates of Pipe Steel with Increased Strength and Cold Resistance on the 5000 Rolling Mill at PJSC MMK

Premium Partner

    Marktübersichten

    Die im Laufe eines Jahres in der „adhäsion“ veröffentlichten Marktübersichten helfen Anwendern verschiedenster Branchen, sich einen gezielten Überblick über Lieferantenangebote zu verschaffen. 

    Zur Marktübersicht
    Bildnachweise