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Title: Stress corrosion in liquid metal fast breeder reactor systems, LMFBR

Abstract

Work has been carried out to determine the degree of reduced SCC susceptibility obtained by the use of remelted rather than air melted 2 1/4 Cr-1 Mo steel. Both Vacuum Arc Remelt (VAR) and Electro Slag Remelt (ESR) material have been evaluated. This work has consisted of the testing of 2 1/4 Cr-1 Mo specimens in 10% and 20% sodium hydroxide at 232/sup 0/C, usng an autoclave system with a tensile loading capability. The work has continued into an evaluation of stress corrosion resistance as a function of post weld heat treatment (PWHT) and as a function of the extent of weld repair by remelting. The second area where attention has been focused is the Sodium Water Reaction Products System (SWRPRS). In the eventuality of a steam generator water leak and the resultant sodium-water reaction, this system is designed to accept the mixture of water-sodium and concomitant reaction products. Specimen holders have been installed in the SWRP system at the Energy Technology Engineering Center (ETEC). This system is connected to the Large Leak Test Vessel (LLTV) which will be used to provide data on the effects of large water leaks in LMFBR steam generator systems. Prototypical materials representing those alloysmore » used for the sodium-water reaction products system are being exposed under large leak conditions. Critical regions of the system piping have been ultrasonically inspected to provide baseline data.« less

Authors:
; ; ;
Publication Date:
Research Org.:
General Electric Co., San Jose, CA (USA). Advanced Reactor Systems Dept.
OSTI Identifier:
5032543
Report Number(s):
GEFR-SP-222; CONF-801036-5
DOE Contract Number:  
AT03-76SF70030
Resource Type:
Conference
Resource Relation:
Conference: Special topical meeting - materials performance in nuclear steam generators, St Petersburg Beach, FL, USA, 6 Oct 1980
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; CHROMIUM-MOLYBDENUM STEELS; STRESS CORROSION; LMFBR TYPE REACTORS; MOLTEN METAL-WATER REACTIONS; AQUEOUS SOLUTIONS; CORROSION RESISTANCE; HEAT TREATMENTS; HIGH TEMPERATURE; LEAKS; SODIUM; SODIUM HYDROXIDES; STEAM GENERATORS; WELDED JOINTS; ALKALI METAL COMPOUNDS; ALKALI METALS; ALLOYS; BOILERS; BREEDER REACTORS; CHEMICAL REACTIONS; CHROMIUM ALLOYS; CHROMIUM STEELS; CORROSION; DISPERSIONS; ELEMENTS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; HYDROGEN COMPOUNDS; HYDROXIDES; IRON ALLOYS; IRON BASE ALLOYS; JOINTS; LIQUID METAL COOLED REACTORS; METALS; MIXTURES; OXYGEN COMPOUNDS; REACTORS; SODIUM COMPOUNDS; SOLUTIONS; STEELS; VAPOR GENERATORS; 220900* - Nuclear Reactor Technology- Reactor Safety; 210500 - Power Reactors, Breeding

Citation Formats

Ring, P J, Spalaris, C N, Odegaard, T K, and Offer, H P. Stress corrosion in liquid metal fast breeder reactor systems, LMFBR. United States: N. p., 1980. Web.
Ring, P J, Spalaris, C N, Odegaard, T K, & Offer, H P. Stress corrosion in liquid metal fast breeder reactor systems, LMFBR. United States.
Ring, P J, Spalaris, C N, Odegaard, T K, and Offer, H P. 1980. "Stress corrosion in liquid metal fast breeder reactor systems, LMFBR". United States.
@article{osti_5032543,
title = {Stress corrosion in liquid metal fast breeder reactor systems, LMFBR},
author = {Ring, P J and Spalaris, C N and Odegaard, T K and Offer, H P},
abstractNote = {Work has been carried out to determine the degree of reduced SCC susceptibility obtained by the use of remelted rather than air melted 2 1/4 Cr-1 Mo steel. Both Vacuum Arc Remelt (VAR) and Electro Slag Remelt (ESR) material have been evaluated. This work has consisted of the testing of 2 1/4 Cr-1 Mo specimens in 10% and 20% sodium hydroxide at 232/sup 0/C, usng an autoclave system with a tensile loading capability. The work has continued into an evaluation of stress corrosion resistance as a function of post weld heat treatment (PWHT) and as a function of the extent of weld repair by remelting. The second area where attention has been focused is the Sodium Water Reaction Products System (SWRPRS). In the eventuality of a steam generator water leak and the resultant sodium-water reaction, this system is designed to accept the mixture of water-sodium and concomitant reaction products. Specimen holders have been installed in the SWRP system at the Energy Technology Engineering Center (ETEC). This system is connected to the Large Leak Test Vessel (LLTV) which will be used to provide data on the effects of large water leaks in LMFBR steam generator systems. Prototypical materials representing those alloys used for the sodium-water reaction products system are being exposed under large leak conditions. Critical regions of the system piping have been ultrasonically inspected to provide baseline data.},
doi = {},
url = {https://www.osti.gov/biblio/5032543}, journal = {},
number = ,
volume = ,
place = {United States},
year = {1980},
month = {8}
}

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