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Title: High-temperature solution annealing as an IASCC mitigation technique

Abstract

Pre-irradiation solution annealing treatments for limited times in the temperature range from 2200{degrees}F (1204{degrees}C) to 2400{degrees}F (1316{degrees}C) were shown to be effective in eliminating irradiation assisted stress corrosion cracking (IASCC) in Type 304 stainless steel (SS), which had been irradiated to fluences between 2.58 and 3.08 {times} 10{sup 21} n/cm{sup 2} (E > 1 MeV). Varying resistance to IASCC as a function of heat treatment parameters was demonstrated in constant extension rate tensile (CERT) tests performed in boiling water reactor (BWR) simulated water. Measures of IASCC susceptibility used in the CERT tests (% IGSCC, % elongation, and maximum stress) could not be correlated with data obtained from HNO{sub 3}/Cr{sup +6} corrosion tests, or from Auger and analytical electron microscopy (AEM) analyses of grain boundary composition. Corrosion test data, however, could be correlated with the Auger and AEM results. The absence of a correlation between IASCC susceptibility and the grain boundary contents of Si, P, and S suggests that other impurities that are known to segregate and undergo nuclear transmutations, such as N and B, may play an important role in the IASCC mechanism. Tensile test data showed that the high temperature solution annealed (HTSA) material had undergone less radiation strengtheningmore » than mill annealed (MA) material. Elongations of approximately 10% were measured in the HTSA material compared to 2% in the MA material. 13 refs., 24 figs., 10 tabs.« less

Authors:
 [1];  [2];  [3];  [4]
  1. General Electric Co., San Jose, CA (USA)
  2. UKAEA Harwell Lab. (UK)
  3. Oak Ridge National Lab., TN (USA)
  4. General Electric Co., Pleasanton, CA (USA). Vallecitos Nuclear Center
Publication Date:
Research Org.:
Oak Ridge National Lab., TN (USA)
Sponsoring Org.:
USDOE; USDOE, Washington, DC (USA)
OSTI Identifier:
5736866
Report Number(s):
CONF-910808-1
ON: DE91012220
DOE Contract Number:  
AC05-84OR21400
Resource Type:
Conference
Resource Relation:
Conference: 5. international symposium on environmental degradation on materials in nuclear power systems - water reactors, Monterey, CA (USA), 25-29 Aug 1991
Country of Publication:
United States
Language:
English
Subject:
36 MATERIALS SCIENCE; STAINLESS STEEL-304; ANNEALING; STRESS CORROSION; AUGER ELECTRON SPECTROSCOPY; BORON; CHROMIUM IONS; CRACK PROPAGATION; ELECTRON MICROSCOPY; ELONGATION; EXPERIMENTAL DATA; GRAIN BOUNDARIES; HEAT TREATMENTS; IRRADIATION; IRRADIATION PROCEDURES; MITIGATION; NITRIC ACID; NITROGEN; RADIATION EFFECTS; SEGREGATION; TENSILE PROPERTIES; TRANSMUTATION; VERY HIGH TEMPERATURE; ALLOYS; AUSTENITIC STEELS; CHARGED PARTICLES; CHEMICAL REACTIONS; CHROMIUM ALLOYS; CHROMIUM-NICKEL STEELS; CORROSION; CORROSION RESISTANT ALLOYS; CRYSTAL STRUCTURE; DATA; ELECTRON SPECTROSCOPY; ELEMENTS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; HYDROGEN COMPOUNDS; INFORMATION; INORGANIC ACIDS; IONS; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS; MECHANICAL PROPERTIES; MICROSCOPY; MICROSTRUCTURE; NICKEL ALLOYS; NONMETALS; NUMERICAL DATA; SEMIMETALS; SPECTROSCOPY; STAINLESS STEELS; STEEL-CR19NI10; STEELS; 360103* - Metals & Alloys- Mechanical Properties; 360106 - Metals & Alloys- Radiation Effects; 360101 - Metals & Alloys- Preparation & Fabrication

Citation Formats

Jacobs, A J, Shepherd, C M, Bell, G E.C., and Wozadlo, G P. High-temperature solution annealing as an IASCC mitigation technique. United States: N. p., 1991. Web.
Jacobs, A J, Shepherd, C M, Bell, G E.C., & Wozadlo, G P. High-temperature solution annealing as an IASCC mitigation technique. United States.
Jacobs, A J, Shepherd, C M, Bell, G E.C., and Wozadlo, G P. Tue . "High-temperature solution annealing as an IASCC mitigation technique". United States.
@article{osti_5736866,
title = {High-temperature solution annealing as an IASCC mitigation technique},
author = {Jacobs, A J and Shepherd, C M and Bell, G E.C. and Wozadlo, G P},
abstractNote = {Pre-irradiation solution annealing treatments for limited times in the temperature range from 2200{degrees}F (1204{degrees}C) to 2400{degrees}F (1316{degrees}C) were shown to be effective in eliminating irradiation assisted stress corrosion cracking (IASCC) in Type 304 stainless steel (SS), which had been irradiated to fluences between 2.58 and 3.08 {times} 10{sup 21} n/cm{sup 2} (E > 1 MeV). Varying resistance to IASCC as a function of heat treatment parameters was demonstrated in constant extension rate tensile (CERT) tests performed in boiling water reactor (BWR) simulated water. Measures of IASCC susceptibility used in the CERT tests (% IGSCC, % elongation, and maximum stress) could not be correlated with data obtained from HNO{sub 3}/Cr{sup +6} corrosion tests, or from Auger and analytical electron microscopy (AEM) analyses of grain boundary composition. Corrosion test data, however, could be correlated with the Auger and AEM results. The absence of a correlation between IASCC susceptibility and the grain boundary contents of Si, P, and S suggests that other impurities that are known to segregate and undergo nuclear transmutations, such as N and B, may play an important role in the IASCC mechanism. Tensile test data showed that the high temperature solution annealed (HTSA) material had undergone less radiation strengthening than mill annealed (MA) material. Elongations of approximately 10% were measured in the HTSA material compared to 2% in the MA material. 13 refs., 24 figs., 10 tabs.},
doi = {},
url = {https://www.osti.gov/biblio/5736866}, journal = {},
number = ,
volume = ,
place = {United States},
year = {1991},
month = {1}
}

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