Reactor Core Materials Interactions at Very High Temperatures-Reference-Cited by-同舟云学术

Reactor Core Materials Interactions at Very High Temperatures

Published:1989-09-02 Issue:1 Volume:87 Page:327-333
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Hofmann Peter¹,Hagen Siegfried J. L.¹,Schanz Gerhard¹,Skokan Alfred¹

Affiliation:

1. Kernforschungszentrum Karlsruhe, Postfach 3640 7500 Karlsruhe 1, Federal Republic of Germany

Publisher

Informa UK Limited

Subject

Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

https://www.tandfonline.com/doi/pdf/10.13182/NT-TMI2-146

Reference30 articles.

1. H. M. CHUNG and G. R. THOMAS, “The Retarding Effect of Hydrogen on Zircaloy Oxidation,” NSAC-29, Nuclear Safety Analysis Center (1981).

2. J. T. PRATER and E. L. COURTRIGHT, “High-Temperature Oxidation of Zircaloy-4 in Steam and Steam-Hydrogen Environments,” NUREG/CR-4476, PNL-5558, U.S. Nuclear Regulatory Commission (1986).

3. Untersuchungen in system Zirkonium-Sauerstoff teil 2 untersuchungen zur kinetik der reaktion zwischen Zirkonium und sauerstoff, sowie über die konstitution des systems Zirkonium-Sauerstoff

4. Oxidation kinetics and related phenomena of zircaloy-4 fuel cladding exposed to high temperature steam and hydrogen-steam mixtures under PWR accident conditions

5. Oxidation of Zircaloy-4 under Limited Steam Supply from 1,000 to 1,400°C

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