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Analysis of the irradiation creep and growth of KMRR structural materials of zircaloy-4

Technical Report:

Abstract

With relation to the dimensional stability and mechanical integrity of the KMRR core Zircaloy-4 structures during long-term irradiation, in-pile creep/growth behaviors of Zircaloy-4 were investigated by means of stress relaxation tests under neutron irradiation in TRIGA MK-III reactor to secure optimum conditions for the fabrication of of Zircaloy structure for dimensional stability. Since the Zircaloy core structure would be {beta}-treated to maximize dimensional stability, the optimum condition for increasing the toughness as well as strength of {beta}-treated Zircaloy was also investigated. The cooling rate of 5 deg C/sec to llO deg C/sec was found to show the maximum toughness and strengh. In the in-pile stress relaxation tests under the fast neutron flux of 1.2xlO{sup 17} n/m{sup 2}sec at 373 deg K in core of the TRIGA Mark-lll reactor, the 50 {mu}m thick foils of {alpha}/{beta} heat treated Zircaloy-4 specimens showed that creep strain of {alpha}-annealed specimens is slightly higher than that of {beta}-annealed specimens. From the result, plate matrix and its welded parts of Zircaloy-4 structures would be negligible when the Zircaloy core materials are properly {beta}-heat treated. Low cycle fatigue life and strength were measured for the {alpha}/{beta} heat treated and proton beam irradiated specimens. The fatigue life of  More>>
Authors:
Rheem, Karp Soon; Kim, Seon Jin; Han, Jung Ho; Jeong, Young Hwan; Lee, Deuk Hyun; Park, Gi Sung [1] 
  1. Korea Atomic Energy Research Inst., Daeduk (Korea, Republic of)
Publication Date:
Feb 01, 1991
Product Type:
Technical Report
Report Number:
KAERI/RR-968/90
Reference Number:
SCA: 420500; 360103; PA: AIX-23:014917; SN: 92000646919
Resource Relation:
Other Information: PBD: Feb 1991
Subject:
42 ENGINEERING; 36 MATERIALS SCIENCE; ALLOY-ZR98SN-4; BUILDING MATERIALS; IRRADIATION; ANNEALING; CREEP; FATIGUE; PROTON BEAMS; STRESS RELAXATION; TRIGA-3-SEOUL REACTOR; 420500; 360103; MATERIALS TESTING; MECHANICAL PROPERTIES
OSTI ID:
10113177
Research Organizations:
Korea Atomic Energy Research Inst., Daeduk (Korea, Republic of)
Country of Origin:
Korea, Republic of
Language:
Korean
Other Identifying Numbers:
Other: ON: DE92615086; TRN: KR9100121014917
Availability:
OSTI; NTIS (US Sales Only); INIS
Submitting Site:
INIS
Size:
63 p.
Announcement Date:
Jun 30, 2005

Technical Report:

Citation Formats

Rheem, Karp Soon, Kim, Seon Jin, Han, Jung Ho, Jeong, Young Hwan, Lee, Deuk Hyun, and Park, Gi Sung. Analysis of the irradiation creep and growth of KMRR structural materials of zircaloy-4. Korea, Republic of: N. p., 1991. Web.
Rheem, Karp Soon, Kim, Seon Jin, Han, Jung Ho, Jeong, Young Hwan, Lee, Deuk Hyun, & Park, Gi Sung. Analysis of the irradiation creep and growth of KMRR structural materials of zircaloy-4. Korea, Republic of.
Rheem, Karp Soon, Kim, Seon Jin, Han, Jung Ho, Jeong, Young Hwan, Lee, Deuk Hyun, and Park, Gi Sung. 1991. "Analysis of the irradiation creep and growth of KMRR structural materials of zircaloy-4." Korea, Republic of.
@misc{etde_10113177,
title = {Analysis of the irradiation creep and growth of KMRR structural materials of zircaloy-4}
author = {Rheem, Karp Soon, Kim, Seon Jin, Han, Jung Ho, Jeong, Young Hwan, Lee, Deuk Hyun, and Park, Gi Sung}
abstractNote = {With relation to the dimensional stability and mechanical integrity of the KMRR core Zircaloy-4 structures during long-term irradiation, in-pile creep/growth behaviors of Zircaloy-4 were investigated by means of stress relaxation tests under neutron irradiation in TRIGA MK-III reactor to secure optimum conditions for the fabrication of of Zircaloy structure for dimensional stability. Since the Zircaloy core structure would be {beta}-treated to maximize dimensional stability, the optimum condition for increasing the toughness as well as strength of {beta}-treated Zircaloy was also investigated. The cooling rate of 5 deg C/sec to llO deg C/sec was found to show the maximum toughness and strengh. In the in-pile stress relaxation tests under the fast neutron flux of 1.2xlO{sup 17} n/m{sup 2}sec at 373 deg K in core of the TRIGA Mark-lll reactor, the 50 {mu}m thick foils of {alpha}/{beta} heat treated Zircaloy-4 specimens showed that creep strain of {alpha}-annealed specimens is slightly higher than that of {beta}-annealed specimens. From the result, plate matrix and its welded parts of Zircaloy-4 structures would be negligible when the Zircaloy core materials are properly {beta}-heat treated. Low cycle fatigue life and strength were measured for the {alpha}/{beta} heat treated and proton beam irradiated specimens. The fatigue life of {beta}-annealed specimens reduced to 1/5 of that of the {alpha}-annealed. Reduction in fatigue life of {beta}-annealed specimens was attributed to the annihilation of textured structures during the cycling of Zircaloy specimens. The effect of proton beam irradiation on the low cycle fatigue life was negligible at room temperature. (Author).}
place = {Korea, Republic of}
year = {1991}
month = {Feb}
}