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Zirconium alloys in nuclear power engineering

  • Structural Materials For Elements Of Nuclear-Reactor Active Zones
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Metal Science and Heat Treatment Aims and scope

Abstract

Results of studies of zirconium alloys É110 and É635 that have served in parts of VVÉR-1000 reactors are presented. The influence of the composition on the properties of alloys É110 and É635 is studied and improved modifications are suggested. The effect of the total content of admixtures in alloy É110 on corrosion and embrittlement of pipes under conditions simulating LOCA is investigated.

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REFERENCES

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  1. A. V. Nikulina
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Translated from Metallovedenie i Termicheskaya Obrabotka Metallov, No. 11, pp. 8–12, November, 2004.

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Nikulina, A.V. Zirconium alloys in nuclear power engineering. Met Sci Heat Treat 46, 458–462 (2004). https://doi.org/10.1007/s11041-005-0002-x

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  • DOI: https://doi.org/10.1007/s11041-005-0002-x

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