Corrosion Behavior of Selected Structural Materials in a Simulated Steam-Cycle High-Temperature Gas-Cooled Reactor Helium Environment-Reference-Cited by-同舟云学术

Corrosion Behavior of Selected Structural Materials in a Simulated Steam-Cycle High-Temperature Gas-Cooled Reactor Helium Environment

Published:1979-05 Issue:3 Volume:43 Page:349-365
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Mazandarany F. N.¹,Lai G. Y.¹

Affiliation:

1. General Atomic Company P.O. Box 81608, San Diego, California 92138

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/NT79-A19223

Reference14 articles.

1. F. N. MAZANDARANY, “Effects of Elevated Temperature Exposure to a Simulated HTGR Primary Coolant Environment on Several Unstressed Austenitic Alloys,” GA-A13462, General Atomic Company (Aug. 1975).

2. G. Y. LAI, General Atomic Company, unpublished data (1976).

3. M. R. EVERETT, “The Kinetics of Carbon Deposition Reactions in High Temperature Gas Cooled Reactors,” Dragon Project Report 50 (Jan. 1967).

4. R. D. BURNETTE et al. “Evaluation of Carbon Deposition Phenomena in HTGR Systems,” GA-8624, Gulf General Atomic (Oct. 5, 1968).

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