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Forsyth, D.R.; Schwirian, R.E.
Proceedings of the 7th International Meeting on Nuclear Reactor Thermal-Hydraulics NURETH-7. Volume 1, Sessions 1-51995
Proceedings of the 7th International Meeting on Nuclear Reactor Thermal-Hydraulics NURETH-7. Volume 1, Sessions 1-51995
AbstractAbstract
[en] ALLOY 600 has been used typically for penetrations through the closure head in pressurized water reactors because of its thermal compatibility with carbon steel, superior resistance to chloride attack and higher strength than the austenitic stainless steels. Recent plant operating experience with this alloy has indicated that this material may be susceptible to degradation. One of the major parameters relating to degradation of the head penetrations are the operational temperatures and stress levels in the penetration
Primary Subject
Source
Block, R.C.; Feiner, F. (American Nuclear Society, La Grange Park, IL (United States)) (comps.); Nuclear Regulatory Commission, Washington, DC (United States). Div. of Systems Technology; American Nuclear Society, La Grange Park, IL (United States); American Inst. of Chemical Engineers, New York, NY (United States); American Society of Mechanical Engineers, New York, NY (United States); Canadian Nuclear Society, Toronto, ON (Canada); Japan Society of Multiphase Flow, Osaka (Japan); 862 p; Sep 1995; p. 696-710; 7. international meeting on nuclear reactor thermal hydraulics; Saratoga, NY (United States); 10-15 Sep 1995; Also available from OSTI as TI95017077; NTIS; GPO
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
ALLOY-NI76CR15FE8, ALLOYS, ALUMINIUM ADDITIONS, CHROMIUM ALLOYS, COMPUTER CODES, CONTAINERS, CORROSION RESISTANT ALLOYS, ENRICHED URANIUM REACTORS, HEAT RESISTANT MATERIALS, HEAT RESISTING ALLOYS, INCONEL ALLOYS, IRON ALLOYS, MATERIALS, NICKEL ALLOYS, NICKEL BASE ALLOYS, NIMONIC, POWER REACTORS, REACTORS, SAFETY, THERMAL REACTORS, TITANIUM ADDITIONS, TRANSITION ELEMENT ALLOYS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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