Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Container materials may undergo any of several modes of degradation in this environment, including: undesirable phase transformations due to lack of phase stability; atmospheric oxidation; general aqueous corrosion; pitting; crevice corrosion; intergranular stress corrosion cracking (IGSCC); and transgranular stress corrosion cracking (TGSCC). This paper is an analysis of data from the literature relevant to the pitting, crevice corrosion, and stress corrosion cracking (SCC) of these alloys. Though all three austenitic candidates have demonstrated pitting and crevice corrosion in chloride-containing environments, Alloy 825 has the greatest resistance to these forms of localized attack. Both types 304L and 316L stainless steels are susceptible to SCC in acidic chloride media. In contrast, SCC has not been documented for Alloy 825 under comparable conditions. Gamma irradiation has been found to enhance SCC of Types 304 and 304L stainless steels, but it has no detectable effect on the resistance of Alloy 825 to SCC. Furthermore, while microbiologically induced corrosion effects have been observed for 300-series stainless steels, nickel-based alloys such as Alloy 825 seem to be immune to such problems. Of the copper-based alloys, CDA 715 has the best overall resistance to localized attack. Its resistance to pitting is comparable to that of CDA 613 and superior to that of CDA 102. Observed rates of dealloying in CDA 715 are less than those observed in CDA 613 by orders of magnitude. The resistance of CDA 715 to SCC in tarnishing ammonical environments is comparable to that of CDA 102 and superior to that of CDA 613. Its resistance to SCC in nontarnishing ammonical environments is comparable to that of CDA 613 and superior to that of CDA 102. 22 refs., 8 figs., 4 tabs.
Localized Corrosion and Stress Corrosion Cracking of Candidate Materials for High-level Radioactive Waste Disposal Containers in the US
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Container materials may undergo any of several modes of degradation in this environment, including: undesirable phase transformations due to lack of phase stability; atmospheric oxidation; general aqueous corrosion; pitting; crevice corrosion; intergranular stress corrosion cracking (IGSCC); and transgranular stress corrosion cracking (TGSCC). This paper is an analysis of data from the literature relevant to the pitting, crevice corrosion, and stress corrosion cracking (SCC) of these alloys. Though all three austenitic candidates have demonstrated pitting and crevice corrosion in chloride-containing environments, Alloy 825 has the greatest resistance to these forms of localized attack. Both types 304L and 316L stainless steels are susceptible to SCC in acidic chloride media. In contrast, SCC has not been documented for Alloy 825 under comparable conditions. Gamma irradiation has been found to enhance SCC of Types 304 and 304L stainless steels, but it has no detectable effect on the resistance of Alloy 825 to SCC. Furthermore, while microbiologically induced corrosion effects have been observed for 300-series stainless steels, nickel-based alloys such as Alloy 825 seem to be immune to such problems. Of the copper-based alloys, CDA 715 has the best overall resistance to localized attack. Its resistance to pitting is comparable to that of CDA 613 and superior to that of CDA 102. Observed rates of dealloying in CDA 715 are less than those observed in CDA 613 by orders of magnitude. The resistance of CDA 715 to SCC in tarnishing ammonical environments is comparable to that of CDA 102 and superior to that of CDA 613. Its resistance to SCC in nontarnishing ammonical environments is comparable to that of CDA 613 and superior to that of CDA 102. 22 refs., 8 figs., 4 tabs.
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Container materials may undergo any of several modes of degradation in this environment, including: undesirable phase transformations due to lack of phase stability; atmospheric oxidation; general aqueous corrosion; pitting; crevice corrosion; intergranular stress corrosion cracking (IGSCC); and transgranular stress corrosion cracking (TGSCC). This paper is an analysis of data from the literature relevant to the pitting, crevice corrosion, and stress corrosion cracking (SCC) of these alloys. Though all three austenitic candidates have demonstrated pitting and crevice corrosion in chloride-containing environments, Alloy 825 has the greatest resistance to these forms of localized attack. Both types 304L and 316L stainless steels are susceptible to SCC in acidic chloride media. In contrast, SCC has not been documented for Alloy 825 under comparable conditions. Gamma irradiation has been found to enhance SCC of Types 304 and 304L stainless steels, but it has no detectable effect on the resistance of Alloy 825 to SCC. Furthermore, while microbiologically induced corrosion effects have been observed for 300-series stainless steels, nickel-based alloys such as Alloy 825 seem to be immune to such problems. Of the copper-based alloys, CDA 715 has the best overall resistance to localized attack. Its resistance to pitting is comparable to that of CDA 613 and superior to that of CDA 102. Observed rates of dealloying in CDA 715 are less than those observed in CDA 613 by orders of magnitude. The resistance of CDA 715 to SCC in tarnishing ammonical environments is comparable to that of CDA 102 and superior to that of CDA 613. Its resistance to SCC in nontarnishing ammonical environments is comparable to that of CDA 613 and superior to that of CDA 102. 22 refs., 8 figs., 4 tabs.
Localized Corrosion and Stress Corrosion Cracking of Candidate Materials for High-level Radioactive Waste Disposal Containers in the US
Author: J. C. Farmer
Publisher:
ISBN:
Category : Corrosion resistant alloys
Languages : en
Pages : 13
Book Description
Container materials may undergo any of several modes of degradation in this environment, including: undesirable phase transformations due to lack of phase stability; atmospheric oxidation; general aqueous corrosion; pitting; crevice corrosion; intergranular stress corrosion cracking (IGSCC); and transgranular stress corrosion cracking (TGSCC). This paper is an analysis of data from the literature relevant to the pitting, crevice corrosion, and stress corrosion cracking (SCC) of these alloys. Though all three austenitic candidates have demonstrated pitting and crevice corrosion in chloride-containing environments, Alloy 825 has the greatest resistance to these forms of localized attack. Both types 304L and 316L stainless steels are susceptible to SCC in acidic chloride media. In contrast, SCC has not been documented for Alloy 825 under comparable conditions. Gamma irradiation has been found to enhance SCC of Types 304 and 304L stainless steels, but it has no detectable effect on the resistance of Alloy 825 to SCC. Furthermore, while microbiologically induced corrosion effects have been observed for 300-series stainless steels, nickel-based alloys such as Alloy 825 seem to be immune to such problems. Of the copper-based alloys, CDA 715 has the best overall resistance to localized attack. Its resistance to pitting is comparable to that of CDA 613 and superior to that of CDA 102. Observed rates of dealloying in CDA 715 are less than those observed in CDA 613 by orders of magnitude. The resistance of CDA 715 to SCC in tarnishing ammonical environments is comparable to that of CDA 102 and superior to that of CDA 613. Its resistance to SCC in nontarnishing ammonical environments is comparable to that of CDA 613 and superior to that of CDA 102.
Publisher:
ISBN:
Category : Corrosion resistant alloys
Languages : en
Pages : 13
Book Description
Container materials may undergo any of several modes of degradation in this environment, including: undesirable phase transformations due to lack of phase stability; atmospheric oxidation; general aqueous corrosion; pitting; crevice corrosion; intergranular stress corrosion cracking (IGSCC); and transgranular stress corrosion cracking (TGSCC). This paper is an analysis of data from the literature relevant to the pitting, crevice corrosion, and stress corrosion cracking (SCC) of these alloys. Though all three austenitic candidates have demonstrated pitting and crevice corrosion in chloride-containing environments, Alloy 825 has the greatest resistance to these forms of localized attack. Both types 304L and 316L stainless steels are susceptible to SCC in acidic chloride media. In contrast, SCC has not been documented for Alloy 825 under comparable conditions. Gamma irradiation has been found to enhance SCC of Types 304 and 304L stainless steels, but it has no detectable effect on the resistance of Alloy 825 to SCC. Furthermore, while microbiologically induced corrosion effects have been observed for 300-series stainless steels, nickel-based alloys such as Alloy 825 seem to be immune to such problems. Of the copper-based alloys, CDA 715 has the best overall resistance to localized attack. Its resistance to pitting is comparable to that of CDA 613 and superior to that of CDA 102. Observed rates of dealloying in CDA 715 are less than those observed in CDA 613 by orders of magnitude. The resistance of CDA 715 to SCC in tarnishing ammonical environments is comparable to that of CDA 102 and superior to that of CDA 613. Its resistance to SCC in nontarnishing ammonical environments is comparable to that of CDA 613 and superior to that of CDA 102.
Review of Models Relevant to the Prediction of Performance of High-level Radioactive-waste Disposal Containers
Author: J. C. Farmer
Publisher:
ISBN:
Category : Radioactive waste disposal in the ground
Languages : en
Pages : 37
Book Description
Austenitic and copper-based alloys are candidate materials for fabrication of the metal containers to be used in disposing of high-level radioactive waste at the prospective repository at Yucca Mountain, Nevada. The selection of the alloy that is best suited for this application will be based in part on predictions from models of alloy degradation under repository conditions. To help develop predictive models, we have reviewed numerous mechanisms and models in the literature that are relevant to two worst-case scenarios: container failure by localized corrosion and container failure by stress corrosion cracking. The models considered fall into the following categories: (1) initiation of pits on passive surfaces of austenitics; (2) propagation of pits on active metal surfaces; (3) propagation of pits on surfaces covered by salt films; (4) initiation of cracks at pits; (5) propagation of cracks on active metal surfaces; (7) propagation of cracks due to film-induced cleavage of the base metal; (8) crevice corrosion on active metal surfaces; and (9) crevices that behave like active-passive concentration cells.
Publisher:
ISBN:
Category : Radioactive waste disposal in the ground
Languages : en
Pages : 37
Book Description
Austenitic and copper-based alloys are candidate materials for fabrication of the metal containers to be used in disposing of high-level radioactive waste at the prospective repository at Yucca Mountain, Nevada. The selection of the alloy that is best suited for this application will be based in part on predictions from models of alloy degradation under repository conditions. To help develop predictive models, we have reviewed numerous mechanisms and models in the literature that are relevant to two worst-case scenarios: container failure by localized corrosion and container failure by stress corrosion cracking. The models considered fall into the following categories: (1) initiation of pits on passive surfaces of austenitics; (2) propagation of pits on active metal surfaces; (3) propagation of pits on surfaces covered by salt films; (4) initiation of cracks at pits; (5) propagation of cracks on active metal surfaces; (7) propagation of cracks due to film-induced cleavage of the base metal; (8) crevice corrosion on active metal surfaces; and (9) crevices that behave like active-passive concentration cells.
Energy Research Abstracts
Stress Corrosion Cracking of Candidate Waste Container Materials
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Six alloys have been selected as candidate container materials for the storage of high-level nuclear waste at the proposed Yucca Mountain site in Nevada. These materials are Type 304L stainless steel (SS), Type 316L SS, Incology 825, P-deoxidized Cu, Cu-30%Ni, and Cu-7% Al. The present program has been initiated to determine whether any of these materials can survive for 300 years in the site environment without developing through-wall stress corrosion cracks, and to assess the relative resistance of these materials to stress corrosion cracking (SCC). A series of slow-strain-rate tests (SSRTs) in simulated Well J-13 water which is representative of the groundwater present at the Yucca Mountain site has been completed, and crack-growth-rate (CGR) tests are also being conducted under the same environmental conditions. 13 refs., 60 figs., 22 tabs.
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Six alloys have been selected as candidate container materials for the storage of high-level nuclear waste at the proposed Yucca Mountain site in Nevada. These materials are Type 304L stainless steel (SS), Type 316L SS, Incology 825, P-deoxidized Cu, Cu-30%Ni, and Cu-7% Al. The present program has been initiated to determine whether any of these materials can survive for 300 years in the site environment without developing through-wall stress corrosion cracks, and to assess the relative resistance of these materials to stress corrosion cracking (SCC). A series of slow-strain-rate tests (SSRTs) in simulated Well J-13 water which is representative of the groundwater present at the Yucca Mountain site has been completed, and crack-growth-rate (CGR) tests are also being conducted under the same environmental conditions. 13 refs., 60 figs., 22 tabs.
ERDA Energy Research Abstracts
Progress Report on the Scientific Investigation Program for the Nevada Yucca Mountain Site
Author:
Publisher:
ISBN:
Category : Radioactive waste disposal
Languages : en
Pages : 84
Book Description
Publisher:
ISBN:
Category : Radioactive waste disposal
Languages : en
Pages : 84
Book Description
Radioactive Waste Management
Author:
Publisher:
ISBN:
Category : Radioactive waste disposal
Languages : en
Pages : 364
Book Description
Publisher:
ISBN:
Category : Radioactive waste disposal
Languages : en
Pages : 364
Book Description
Yucca Mountain Site Characterization Project Bibliography, 1994-1995
Degradation Mode Survey Galvanic Corrosion of Candidate Metallic Materials for High-level Radioactive Waste Disposal Containers
Author: Ajit K. Roy
Publisher:
ISBN:
Category : Corrosion resistant alloys
Languages : en
Pages : 46
Book Description
This report presents the results of a literature review on galvanic corrosion between candidate metals and alloys currently being considered for the waste package containers.
Publisher:
ISBN:
Category : Corrosion resistant alloys
Languages : en
Pages : 46
Book Description
This report presents the results of a literature review on galvanic corrosion between candidate metals and alloys currently being considered for the waste package containers.