Dispersion-Strengthened Ferritic Steels as Fast-Reactor Structural Materials-Reference-Cited by-同舟云学术

Dispersion-Strengthened Ferritic Steels as Fast-Reactor Structural Materials

Published:1974-11 Issue:2 Volume:24 Page:216-224
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Huet J.-J.¹,Leroy V.¹

Affiliation:

1. Centre d'Etude de I'Energie Nucléaire CEN/SCK, 1144, Avenue E. Plasky, B-1040, Bruxelles, Belgique

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/NT74-A31476

Reference9 articles.

1. W. R. MARTIN et al. “Irradiation Effects at High Temperature for Fe-Cr-Al-Y Alloys,” ORNL-3970, Oak Ridge National Laboratory (1966).

2. J. Z. BRIGGS and T. D. PARKER, “The Super 12% Cr Steels,” Climax Molybdenum Company (1965).

3. J. P. BREYER et al. “Ferritic Stainless Alloys Containing Titanium and Molybdenum as Major Alloying Additions,” Metallurgical Reports CRM No. 36, Centre de Recherches Métallurgiques, Liège, Belgium (Sep. 1973).

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