Tensile and Impact Properties of Candidate Alloys for High-Temperature Gas-Cooled Reactor Applications-Reference-Cited by-同舟云学术

Tensile and Impact Properties of Candidate Alloys for High-Temperature Gas-Cooled Reactor Applications

Published:1984-08 Issue:2 Volume:66 Page:357-362
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Bruch Udo¹,Schuhmacher Dieter¹,Ennis Philip J.²,Heesen Eberhard te³

Affiliation:

1. Rheinische Braunkohlenwerke AG, 5000 Cologne 41 Federal Republic of Germany

2. Institut für Reaktorwerkstoffe Kernforschungsanlage Jülich GmbH, P.O. Box 19 13D-5170 Jülich, Federal Republic of Germany

3. GHT/INTERATOM GmbH D-5060 Bensberg, 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/NT84-A33438

Reference5 articles.

1. “Prüfung metallischer Werkstoffe-Zugversuche,” DIN 50145, German Institute for Standards (DIN) (May 1975).

2. Microstructure and phase stability of INCONEL alloy 617

3. S. J. MATTHEWS, “Thermal Stability of Solid Solution Strengthened High Performance Alloys,” Publication 8979, Cabot Corporation (1976).

4. Precipitation Behavior of Ni–Cr–22 Fe–18 Mo (Hastelloy-X) and Ni-Cr-22 Co-12 Mo (Inconel-617) After Isothermal Aging

5. P. J. ENNIS, D. F. LUPTON, H. NICKEL and H. SCHUSTER, “Influence of Carburization on the Room Temperature Tensile Properties of High Temperature Alloys,” Jül-1786, Kernforschungsanlage Jülich (May 1982).

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