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Title: Reactor vessel cladding separate effects studies

Abstract

The existence of a layer of tough weld overlay cladding on the interior of a light-water reactor pressure vessel could mitigate damage caused during certain overcooling transients. The potential benefit of the cladding is that it could keep a short surface flaw, which would otherwise become long, from growing either by impeding crack initiation or by arresting a running crack. Two aspects critical to cladding behavior will be reported: irradiation effects on cladding toughness and the response of mechanically loaded, flawed structures in the presence of cladding. 15 refs., 24 figs., 6 tabs.

Authors:
Publication Date:
Research Org.:
Oak Ridge National Lab., TN (USA)
OSTI Identifier:
6404079
Report Number(s):
CONF-8510173-6
ON: TI86002199
DOE Contract Number:  
AC05-84OR21400
Resource Type:
Conference
Resource Relation:
Conference: 13. water reactor safety research information meeting, Gaithersburg, MD, USA, 22 Oct 1985
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 36 MATERIALS SCIENCE; BWR TYPE REACTORS; PRESSURE VESSELS; REACTOR MATERIALS; CLADDING; CRACK PROPAGATION; PWR TYPE REACTORS; PHYSICAL RADIATION EFFECTS; TENSILE PROPERTIES; STAINLESS STEEL-308; STAINLESS STEEL-309; STEEL-ASTM-A533-B; DUCTILE-BRITTLE TRANSITIONS; SUBMERGED ARC WELDING; THERMAL STRESSES; TRANSIENTS; ALLOYS; ARC WELDING; CARBON STEELS; CHROMIUM ALLOYS; CHROMIUM STEELS; CHROMIUM-NICKEL STEELS; CONTAINERS; CORROSION RESISTANT ALLOYS; DEPOSITION; FABRICATION; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; IRON ALLOYS; IRON BASE ALLOYS; JOINING; MATERIALS; MECHANICAL PROPERTIES; NICKEL ALLOYS; RADIATION EFFECTS; REACTORS; STAINLESS STEELS; STEELS; STRESSES; SURFACE COATING; WATER COOLED REACTORS; WATER MODERATED REACTORS; WELDING; 210100* - Power Reactors, Nonbreeding, Light-Water Moderated, Boiling Water Cooled; 210200 - Power Reactors, Nonbreeding, Light-Water Moderated, Nonboiling Water Cooled; 360106 - Metals & Alloys- Radiation Effects

Citation Formats

Corwin, W R. Reactor vessel cladding separate effects studies. United States: N. p., 1985. Web.
Corwin, W R. Reactor vessel cladding separate effects studies. United States.
Corwin, W R. 1985. "Reactor vessel cladding separate effects studies". United States. https://www.osti.gov/servlets/purl/6404079.
@article{osti_6404079,
title = {Reactor vessel cladding separate effects studies},
author = {Corwin, W R},
abstractNote = {The existence of a layer of tough weld overlay cladding on the interior of a light-water reactor pressure vessel could mitigate damage caused during certain overcooling transients. The potential benefit of the cladding is that it could keep a short surface flaw, which would otherwise become long, from growing either by impeding crack initiation or by arresting a running crack. Two aspects critical to cladding behavior will be reported: irradiation effects on cladding toughness and the response of mechanically loaded, flawed structures in the presence of cladding. 15 refs., 24 figs., 6 tabs.},
doi = {},
url = {https://www.osti.gov/biblio/6404079}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Tue Jan 01 00:00:00 EST 1985},
month = {Tue Jan 01 00:00:00 EST 1985}
}

Conference:
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