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Conference Article: 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)

Abstract

The HTR-materials program in Germany has been directed towards the qualification of high temperature alloys for heat exchanging components of advanced nuclear process heat plants. From the available conventional alloys, the nickel-base alloy NiCr22Co12Mo (Alloy 617) has been selected for the highest working temperatures. With respect to the design of intermediate heat exchanger and methane reformer tubes long term properties for different semifinished products and weldments of this material have been determined. The experimental work included creep and creep rupture tests, fatigue and creep/fatigue tests and short term mechanical tests after thermal ageing. With regard to the development of fracture mechanics criteria for leak before break argumentations, additional creep and fatigue crack growth experiments have been carried out. Typical examples of the data obtained will be presented. The implementation of the data in the derivation of design curves and the formulation of design rules will be shown.

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key words: Gas Cooled Reactor, Nuclear Technology
Reference:
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, pp:91-99