Skip to main content
Erschienen in: International Journal of Mechanics and Materials in Design 4/2018

11.11.2017

Multicriteria materials selection for extreme operating conditions based on a multiobjective analysis of irradiation embrittlement and hot cracking prediction models

verfasst von: A. Rodríguez-Prieto, A. M. Camacho, M. A. Sebastián

Erschienen in: International Journal of Mechanics and Materials in Design | Ausgabe 4/2018

Einloggen

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

search-config
loading …

Abstract

A methodology for evaluating different combinations of materials specifications for extreme environment applications is presented. This new approach addresses the materials selection problem using a multicriteria stringency level methodology that defines several thresholds obtained by analyzing different prediction models of irradiation embrittlement and hot cracking. To solve the conflicts among thresholds as provided by the different prediction models, a multiobjective approach is carried out. Materials for reactor pressure vessels have been considered as case study. It has been concluded that the best option to manufacture a pressure vessel for a pressurized water modern reactor is the selection of German manufacturing standards. Finally, a sensitivity analysis of the proposed methodology has been performed to evaluate the divergences between the single stringency level methodology and the new proposal including multicriteria decision making aspects.

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!

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!

Literatur
Zurück zum Zitat Amayev, A.D., Kryukov, A.M., Sokov, M.A.: Recovery of the transition temperature of irradiated WWER-440 Vessel Metal by Annealing. In: Steele, L.E. (ed.) Radiation Embrittlement of Nuclear Pressure Vessel Steels: An International Review, vol. 4, pp. 369–379. ASTM STP 1170 (1993) Amayev, A.D., Kryukov, A.M., Sokov, M.A.: Recovery of the transition temperature of irradiated WWER-440 Vessel Metal by Annealing. In: Steele, L.E. (ed.) Radiation Embrittlement of Nuclear Pressure Vessel Steels: An International Review, vol. 4, pp. 369–379. ASTM STP 1170 (1993)
Zurück zum Zitat American Society for Metals—ASM: Source book on stainless steels. Engineering Bockshelfs, Russell Township, USA (2012) American Society for Metals—ASM: Source book on stainless steels. Engineering Bockshelfs, Russell Township, USA (2012)
Zurück zum Zitat Arantes, F.M.L., Trevisan, R.E.: Experimental and theoretical evaluation of solidification cracking in weld metal. J. Achiev. Mater. Manuf. Eng. 20(1–2), 407–410 (2007) Arantes, F.M.L., Trevisan, R.E.: Experimental and theoretical evaluation of solidification cracking in weld metal. J. Achiev. Mater. Manuf. Eng. 20(1–2), 407–410 (2007)
Zurück zum Zitat ASME B&PV: Boiler and Pressure Vessels Code. American Society of Mechanical Engineers, New York (2015) ASME B&PV: Boiler and Pressure Vessels Code. American Society of Mechanical Engineers, New York (2015)
Zurück zum Zitat ASME B&PV II D App. 1 Mandatory, 2015: Basis for Establishing Stress Values. American Society of Mechanical Engineers, New York (2015) ASME B&PV II D App. 1 Mandatory, 2015: Basis for Establishing Stress Values. American Society of Mechanical Engineers, New York (2015)
Zurück zum Zitat ASTM E900: Standard Guide for Predicting Radiation-Induced Transition Temperature Shift in Reactor Vessel Materials. American Society for Testing and Materials, Philadephia (2002) ASTM E900: Standard Guide for Predicting Radiation-Induced Transition Temperature Shift in Reactor Vessel Materials. American Society for Testing and Materials, Philadephia (2002)
Zurück zum Zitat Ballesteros, A., Acosta, B.: Embrittlement Trend Curve for Vessel Steels with Low Copper Content. International Atomic Energy Agency, Vienna (1997) Ballesteros, A., Acosta, B.: Embrittlement Trend Curve for Vessel Steels with Low Copper Content. International Atomic Energy Agency, Vienna (1997)
Zurück zum Zitat Blagoeva, D.T., Debarberis, L., Jong, M., ten Pierick, P.: Stability of ferritic steel to higher doses: survey of reactor pressure vessel steel data and comparison with candidate materials for future nuclear systems. Int. J. Press. Vessel. Pip. 122, 1–5 (2014)CrossRef Blagoeva, D.T., Debarberis, L., Jong, M., ten Pierick, P.: Stability of ferritic steel to higher doses: survey of reactor pressure vessel steel data and comparison with candidate materials for future nuclear systems. Int. J. Press. Vessel. Pip. 122, 1–5 (2014)CrossRef
Zurück zum Zitat Bringas, J.E. (ed.): Handbook of Comparative World Steel Standards. American Society for Testing and Materials, Philadelphia (2000) Bringas, J.E. (ed.): Handbook of Comparative World Steel Standards. American Society for Testing and Materials, Philadelphia (2000)
Zurück zum Zitat Brooks, A., Thompson, W.: Microstructural development and solidification cracking susceptibility of austenitic stainless steel welds. Int. Mater. Rev. 36, 16–44 (1991)CrossRef Brooks, A., Thompson, W.: Microstructural development and solidification cracking susceptibility of austenitic stainless steel welds. Int. Mater. Rev. 36, 16–44 (1991)CrossRef
Zurück zum Zitat Chauhan, A., Vaish, R., Bowen, C.: Piezoelectric material selection for ultrasonic transducer and actuator applications. Proc. IMechE Part L J. Mater. Des. Appl. 229(1), 3–12 (2015)CrossRef Chauhan, A., Vaish, R., Bowen, C.: Piezoelectric material selection for ultrasonic transducer and actuator applications. Proc. IMechE Part L J. Mater. Des. Appl. 229(1), 3–12 (2015)CrossRef
Zurück zum Zitat Chung, H.M., Perry, D.L., Shack, W.J.: Sulphur in Austenitic Stainless Steel and Irradiation Assisted Stress Corrosion Cracking. NACE International, Houston (2003) Chung, H.M., Perry, D.L., Shack, W.J.: Sulphur in Austenitic Stainless Steel and Irradiation Assisted Stress Corrosion Cracking. NACE International, Houston (2003)
Zurück zum Zitat Eason, E.D., Wright, J.E., Odette, G.R.: Improved Embrittlement Correlations for Reactor Pressure Vessel Steels. NUREG/CR-6551. U.S. Nuclear Regulatory Commission, Washington (1998) Eason, E.D., Wright, J.E., Odette, G.R.: Improved Embrittlement Correlations for Reactor Pressure Vessel Steels. NUREG/CR-6551. U.S. Nuclear Regulatory Commission, Washington (1998)
Zurück zum Zitat Fujii, K., Fukuya, K., Kasada, R., Kimura, A., Ohkubo, T.: Effects of stress on radiation hardening and microstructural evolution in A533B steel. J. Nucl. Mater. 407(3), 151–156 (2010)CrossRef Fujii, K., Fukuya, K., Kasada, R., Kimura, A., Ohkubo, T.: Effects of stress on radiation hardening and microstructural evolution in A533B steel. J. Nucl. Mater. 407(3), 151–156 (2010)CrossRef
Zurück zum Zitat Gillemot, F.: Overview of reactor pressure vessel cladding. Int. J. Nucl. Knowl. Manag. 4(4), 265–278 (2010)CrossRef Gillemot, F.: Overview of reactor pressure vessel cladding. Int. J. Nucl. Knowl. Manag. 4(4), 265–278 (2010)CrossRef
Zurück zum Zitat Hyde, T., Sun, W.: Some issues on creep damage modelling of welds with heterogeneous structures. Int. J. Mech. Mater. Des. 5, 327–335 (2009)CrossRef Hyde, T., Sun, W.: Some issues on creep damage modelling of welds with heterogeneous structures. Int. J. Mech. Mater. Des. 5, 327–335 (2009)CrossRef
Zurück zum Zitat IAEA: Earthquake Preparedness and Response for Nuclear Power Plants. International Atomic Energy Agency Publications, Vienna (2011) IAEA: Earthquake Preparedness and Response for Nuclear Power Plants. International Atomic Energy Agency Publications, Vienna (2011)
Zurück zum Zitat Jenkins, M.L., Kirk, M.A., Pythian, W.J.: Experimental studies of cascade phenomena in metals. J. Nucl. Mater. 205, 16–30 (1993)CrossRef Jenkins, M.L., Kirk, M.A., Pythian, W.J.: Experimental studies of cascade phenomena in metals. J. Nucl. Mater. 205, 16–30 (1993)CrossRef
Zurück zum Zitat Jiang, C., Huang, X.P., Wei, X.P., Liu, N.Y.: A time-variant reliability analysis method for structural systems based on stochastic process discretization. Int. J. Mech. Mater. Des. 13, 173–193 (2017)CrossRef Jiang, C., Huang, X.P., Wei, X.P., Liu, N.Y.: A time-variant reliability analysis method for structural systems based on stochastic process discretization. Int. J. Mech. Mater. Des. 13, 173–193 (2017)CrossRef
Zurück zum Zitat Kemp, R., Cottrell, G.A., Bhadeshia, H.K.D.H., Odette, G.R., Yamamoto, T., Kishimoto, H.: Neural-network analysis of irradiation hardening in low-activation steels. J. Nucl. Mater. 348(3), 311–328 (2006)CrossRef Kemp, R., Cottrell, G.A., Bhadeshia, H.K.D.H., Odette, G.R., Yamamoto, T., Kishimoto, H.: Neural-network analysis of irradiation hardening in low-activation steels. J. Nucl. Mater. 348(3), 311–328 (2006)CrossRef
Zurück zum Zitat Kim, M.C., Park, S.G., Lee, K.H., Lee, B.S.: Comparison of fracture properties in SA508 Gr. 3 and Gr. 4N high strength low alloy steels for advanced pressure vessel materials. Int. J. Press. Vessel. Pip. 131, 60–66 (2015)CrossRef Kim, M.C., Park, S.G., Lee, K.H., Lee, B.S.: Comparison of fracture properties in SA508 Gr. 3 and Gr. 4N high strength low alloy steels for advanced pressure vessel materials. Int. J. Press. Vessel. Pip. 131, 60–66 (2015)CrossRef
Zurück zum Zitat Kirk, M.: Development of the alternate pressurized thermal shock rule (10 CFR 50.61a) in the United States. Nucl. Eng. Technol. 45(3), 277–294 (2013)CrossRef Kirk, M.: Development of the alternate pressurized thermal shock rule (10 CFR 50.61a) in the United States. Nucl. Eng. Technol. 45(3), 277–294 (2013)CrossRef
Zurück zum Zitat Kobayashi, S., Yamamoto, T., Klingensmith, D., Odette, G.R., Kikuchi, H., Kamada, Y.: Magnetic evaluation of irradiation hardening in A533B reactor pressure vessel steels: magnetic hysteresis measurements and the model analysis. J. Nucl. Mater. 422(1–3), 158–162 (2012)CrossRef Kobayashi, S., Yamamoto, T., Klingensmith, D., Odette, G.R., Kikuchi, H., Kamada, Y.: Magnetic evaluation of irradiation hardening in A533B reactor pressure vessel steels: magnetic hysteresis measurements and the model analysis. J. Nucl. Mater. 422(1–3), 158–162 (2012)CrossRef
Zurück zum Zitat Kotecki, D., Sievert, T.A.: WRC-1992 Constitution diagram for stainless steel weld metal: a modification of the WRC-1988 diagram. Weld. J. 71, 171–178 (1992) Kotecki, D., Sievert, T.A.: WRC-1992 Constitution diagram for stainless steel weld metal: a modification of the WRC-1988 diagram. Weld. J. 71, 171–178 (1992)
Zurück zum Zitat KTA Safety Standard 3201.1: Components of the Reactor Coolant Pressure Boundary of Light Water Reactors. Part 1: Materials and Product Forms. Nuclear Safety Standards Commission (KTA), Salzgitter (1998) KTA Safety Standard 3201.1: Components of the Reactor Coolant Pressure Boundary of Light Water Reactors. Part 1: Materials and Product Forms. Nuclear Safety Standards Commission (KTA), Salzgitter (1998)
Zurück zum Zitat KTA Safety Standard 3201.3: Components of the Reactor Coolant Pressure Boundary of Light Water Reactors—Part 3: Manufacture. Nuclear Safety Standards Commission (KTA), Salzgitter (2007) KTA Safety Standard 3201.3: Components of the Reactor Coolant Pressure Boundary of Light Water Reactors—Part 3: Manufacture. Nuclear Safety Standards Commission (KTA), Salzgitter (2007)
Zurück zum Zitat KTA Safety Standard 3203: Surveillance of the Irradiation Behaviour of Reactor Pressure Vessel Materials of LWR Facilities. Nuclear Safety Standards Commission (KTA), Salzgitter (2001) KTA Safety Standard 3203: Surveillance of the Irradiation Behaviour of Reactor Pressure Vessel Materials of LWR Facilities. Nuclear Safety Standards Commission (KTA), Salzgitter (2001)
Zurück zum Zitat KTA Safety Standard 3201.2: Components of the reactor coolant pressure boundary of light water reactors—Part 3: design and analysis. Nuclear Safety Standards Commission (KTA), Salzgitter (2011) KTA Safety Standard 3201.2: Components of the reactor coolant pressure boundary of light water reactors—Part 3: design and analysis. Nuclear Safety Standards Commission (KTA), Salzgitter (2011)
Zurück zum Zitat Kwon, J., Kwon, S.C., Hong, J.-H.: Prediction of radiation hardening in reactor pressure vessel steel based on a theoretical model. Ann. Nucl. Energy 30(15), 1549–1559 (2003)CrossRef Kwon, J., Kwon, S.C., Hong, J.-H.: Prediction of radiation hardening in reactor pressure vessel steel based on a theoretical model. Ann. Nucl. Energy 30(15), 1549–1559 (2003)CrossRef
Zurück zum Zitat Leite, M., Silva, A., Henriques, E., Madeira, J.F.A.: Materials selection for a set of multiple parts considering manufacturing costs and weight reduction with structural isoperformance using direct multisearch optimization. Struct. Multidiscip. Optim. 52, 635–644 (2015)MathSciNetCrossRef Leite, M., Silva, A., Henriques, E., Madeira, J.F.A.: Materials selection for a set of multiple parts considering manufacturing costs and weight reduction with structural isoperformance using direct multisearch optimization. Struct. Multidiscip. Optim. 52, 635–644 (2015)MathSciNetCrossRef
Zurück zum Zitat Miannay, D., Dussarté, D., Soulat, P.: The nil-ductility temperature shift arising from irradiation as predicted through the French test reactors experiments. Effects of radiation on materials. ASTM STP 1046, 284–304 (1990) Miannay, D., Dussarté, D., Soulat, P.: The nil-ductility temperature shift arising from irradiation as predicted through the French test reactors experiments. Effects of radiation on materials. ASTM STP 1046, 284–304 (1990)
Zurück zum Zitat Milani, A.S., Shanian, A.: Gear material selection with uncertain and incomplete data. Material performance indices and decision aid model. Int. J. Mech. Mater. Des. 3, 209–222 (2006)CrossRef Milani, A.S., Shanian, A.: Gear material selection with uncertain and incomplete data. Material performance indices and decision aid model. Int. J. Mech. Mater. Des. 3, 209–222 (2006)CrossRef
Zurück zum Zitat Moorhead, A.J., Sikka, V.K., Reed, R.W.: Effect of small additions of niobium on the welding behaviour of an austenitic stainless steel, properties of austenitic stainless steels and their weld metals (influence of slaight chemistry variations). ASTM Spec. Tech. Publ. 679, 103–111 (1979) Moorhead, A.J., Sikka, V.K., Reed, R.W.: Effect of small additions of niobium on the welding behaviour of an austenitic stainless steel, properties of austenitic stainless steels and their weld metals (influence of slaight chemistry variations). ASTM Spec. Tech. Publ. 679, 103–111 (1979)
Zurück zum Zitat Moss, D., Basic, M.: Pressure vessel design manual. Butterworth-Heinemann, Oxford (2013) Moss, D., Basic, M.: Pressure vessel design manual. Butterworth-Heinemann, Oxford (2013)
Zurück zum Zitat Odette, G.R., Lucas, G.E.: Irradiation embrittlement of reactor pressure vessel steels:mechanism, models, and data correlations. Radiation embrittlement of nuclear pressure vessels steels: an international review. ASTM STP 909, 206–241 (1986) Odette, G.R., Lucas, G.E.: Irradiation embrittlement of reactor pressure vessel steels:mechanism, models, and data correlations. Radiation embrittlement of nuclear pressure vessels steels: an international review. ASTM STP 909, 206–241 (1986)
Zurück zum Zitat RCC-MR: Design and Construction Rules for Mechanical Components of Nuclear Installations Applicable for High Temperature Structures and ITER Vacuum Vessel. AFCEN publications, Paris (2007) RCC-MR: Design and Construction Rules for Mechanical Components of Nuclear Installations Applicable for High Temperature Structures and ITER Vacuum Vessel. AFCEN publications, Paris (2007)
Zurück zum Zitat Regulatory Guide R.G 1.99 Rev.1: Effects of Residual Elements on Predicted Radiation Damage to Reactor Vessels Materials. Nuclear Regulatory Commission (NRC), Washington (1977) Regulatory Guide R.G 1.99 Rev.1: Effects of Residual Elements on Predicted Radiation Damage to Reactor Vessels Materials. Nuclear Regulatory Commission (NRC), Washington (1977)
Zurück zum Zitat Regulatory Guide R.G 1.99 Rev.2: Radiation Embrittlement of Reactor Vessel Materials. Nuclear Regulatory Commission, Washington (1988) Regulatory Guide R.G 1.99 Rev.2: Radiation Embrittlement of Reactor Vessel Materials. Nuclear Regulatory Commission, Washington (1988)
Zurück zum Zitat Riou, B., Escaravage, C., Hittner, D., Pierron, D.: Issues in reactor pressure vessel materials. In: Proceedings of the 2nd International Topical Meeting on High Temperature Reactor Technology, pp. 10–22. Beijing (China), 22–24 Sept (2004) Riou, B., Escaravage, C., Hittner, D., Pierron, D.: Issues in reactor pressure vessel materials. In: Proceedings of the 2nd International Topical Meeting on High Temperature Reactor Technology, pp. 10–22. Beijing (China), 22–24 Sept (2004)
Zurück zum Zitat Rodríguez, A., Camacho, A.M., Sebastián, M.A.: Prediction of the mechanical behaviour of cladding materials for nuclear reactor pressure-vessels based on the analysis of technological requirements. Proc. Eng. 100, 1301–1308 (2015)CrossRef Rodríguez, A., Camacho, A.M., Sebastián, M.A.: Prediction of the mechanical behaviour of cladding materials for nuclear reactor pressure-vessels based on the analysis of technological requirements. Proc. Eng. 100, 1301–1308 (2015)CrossRef
Zurück zum Zitat Rodríguez-Prieto, A., Camacho, A.M., Sebastián, M.A.: Materials selection criteria for nuclear power applications: a decision algorithm. JOM 68(2), 496–506 (2016)CrossRef Rodríguez-Prieto, A., Camacho, A.M., Sebastián, M.A.: Materials selection criteria for nuclear power applications: a decision algorithm. JOM 68(2), 496–506 (2016)CrossRef
Zurück zum Zitat Rodríguez-Prieto, A., Camacho, A.M., Sebastián, M.A.: Selection of candidate materials for reactor pressure vessels: application of irradiation embrittlement prediction models and a stringency level methodology. Proc. IMechE Part L J. Mater. Des. Appl. (2017a). https://doi.org/10.1177/1464420717727769 CrossRef Rodríguez-Prieto, A., Camacho, A.M., Sebastián, M.A.: Selection of candidate materials for reactor pressure vessels: application of irradiation embrittlement prediction models and a stringency level methodology. Proc. IMechE Part L J. Mater. Des. Appl. (2017a). https://​doi.​org/​10.​1177/​1464420717727769​ CrossRef
Zurück zum Zitat Rodríguez-Prieto, A., Camacho, A.M., Sebastián, M.A.: Evaluation method for pressure vessel manufacturing codes: the influence of ASME unit conversion. Int. J. Mater. Prod. Technol. 54(4), 259–274 (2017b)CrossRef Rodríguez-Prieto, A., Camacho, A.M., Sebastián, M.A.: Evaluation method for pressure vessel manufacturing codes: the influence of ASME unit conversion. Int. J. Mater. Prod. Technol. 54(4), 259–274 (2017b)CrossRef
Zurück zum Zitat Soneda, N., Dohi, K., Nishida, K., Nomoto, A., Iwasaki, M., Tsuno, S., Akiyama, T., Watanabe, S., Ohta, T.: Flux effect on neutron irradiation embrittlement of Reactor Pressure Vessel steels irradiated to high fluences. In: Proceedings of the International Symposium on Contribution of Materials Investigations to Improve the Safety and Performance of LWRs, pp. 1–9. Avignon (France), 26–30 Sept (2011) Soneda, N., Dohi, K., Nishida, K., Nomoto, A., Iwasaki, M., Tsuno, S., Akiyama, T., Watanabe, S., Ohta, T.: Flux effect on neutron irradiation embrittlement of Reactor Pressure Vessel steels irradiated to high fluences. In: Proceedings of the International Symposium on Contribution of Materials Investigations to Improve the Safety and Performance of LWRs, pp. 1–9. Avignon (France), 26–30 Sept (2011)
Zurück zum Zitat Timofeev, B.: Assessment of the first generation RPV state after designed lifetime. Int. J. Press. Vessel. Pip. 81(8), 703–712 (2004)CrossRef Timofeev, B.: Assessment of the first generation RPV state after designed lifetime. Int. J. Press. Vessel. Pip. 81(8), 703–712 (2004)CrossRef
Zurück zum Zitat Valiente, M.A.: Predictive and measurement methods for delta ferrite determination in stainless steels. Weld. J. 91(4), 113–121 (2012) Valiente, M.A.: Predictive and measurement methods for delta ferrite determination in stainless steels. Weld. J. 91(4), 113–121 (2012)
Zurück zum Zitat Vijayaraghavan, V., Garg, A., Wong, C.H., Tai, K., Singru, P.M.: An integrated computational approach for determining the elastic properties of boron nitride nanotubes. Int. J. Mech. Mater. Des. 11, 1–14 (2015)CrossRef Vijayaraghavan, V., Garg, A., Wong, C.H., Tai, K., Singru, P.M.: An integrated computational approach for determining the elastic properties of boron nitride nanotubes. Int. J. Mech. Mater. Des. 11, 1–14 (2015)CrossRef
Zurück zum Zitat Welding Handbook: Materials and Applications Part 2, vol. 4, Nine edn. American welding society (AWS) publications, Miami (2014) Welding Handbook: Materials and Applications Part 2, vol. 4, Nine edn. American welding society (AWS) publications, Miami (2014)
Zurück zum Zitat Wu, S.J., Cao, L.W.: Effect of intergranular failure on the critical fracture stress and the fracture toughness of degraded reactor pressure vessel steel. Int. J. Press. Vessel. Pip. 101, 23–29 (2013)CrossRef Wu, S.J., Cao, L.W.: Effect of intergranular failure on the critical fracture stress and the fracture toughness of degraded reactor pressure vessel steel. Int. J. Press. Vessel. Pip. 101, 23–29 (2013)CrossRef
Metadaten
Titel
Multicriteria materials selection for extreme operating conditions based on a multiobjective analysis of irradiation embrittlement and hot cracking prediction models
verfasst von
A. Rodríguez-Prieto
A. M. Camacho
M. A. Sebastián
Publikationsdatum
11.11.2017
Verlag
Springer Netherlands
Erschienen in
International Journal of Mechanics and Materials in Design / Ausgabe 4/2018
Print ISSN: 1569-1713
Elektronische ISSN: 1573-8841
DOI
https://doi.org/10.1007/s10999-017-9393-2

Weitere Artikel der Ausgabe 4/2018

International Journal of Mechanics and Materials in Design 4/2018 Zur Ausgabe

    Marktübersichten

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