Irradiation Effects on Reactor Structural Materials

The report, covering research for the period 1 May - 31 July 1973, includes: (1) fatigue properties of irradiated EBR-2 control rod thimble (304 stainless steel); (2) fracture toughness characterization of irradiated stainless steels; (3) notch ductility of higher strength steels. Types A543 plate a...

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Bibliographische Detailangaben
1. Verfasser:	Steele,L E
Format:	Report
Sprache:	eng
Schlagworte:	ANNEALING CONTROL RODS DAMAGE ELECTRON MICROSCOPY FATIGUE(MECHANICS) Fission Reactor Materials FRACTURE(MECHANICS) ION BOMBARDMENT IRON ALLOYS LIFE(DURABILITY) Metallurgy and Metallography NEUTRON REACTIONS Radioactiv, Radioactive Wastes & Fission Prod REACTOR MATERIALS SM-1 REACTOR STAINLESS STEEL STEEL STEEL 304 STEEL 316 STEEL A-508 STEEL A-543
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Beschreibung
Zusammenfassung:	The report, covering research for the period 1 May - 31 July 1973, includes: (1) fatigue properties of irradiated EBR-2 control rod thimble (304 stainless steel); (2) fracture toughness characterization of irradiated stainless steels; (3) notch ductility of higher strength steels. Types A543 plate and A508 forging; (4) damage produced in iron and iron alloys by neutron irradiation and ion bombardment; (5) mircrostructure of helium-implanted annealed and cold worked 316 stainless steel, and (6) determination of neutron flux level in the SM-1 reactor. (Modified author abstract) See also report dated 15 May 73, AD-763 658.