Results and recommendations from the reactor chemistry and corrosion tasks of the reactor materials program
Within the general context of extended service life, the Reactor Materials Program was initiated in 1984. This comprehensive program addressed material performance in SRS reactor tanks and the primary coolant or Process Water System (PWS) piping. Three of the eleven tasks concerned moderator quality and corrosion mitigation. Definition and control of the stainless steel aqueous environment is a key factor in corrosion mitigation. The Reactor Materials Program systematically investigated the SRS environment and its effect on crack initiation and propagation in stainless steel, with the objective of improving this environment. The purpose of this report is to summarize the contributions of Tasks 6, 7 and 10 of the Reactor Materials Program to the understanding and control of moderator quality and its relationship to mitigation of stress corrosion cracking.
- Research Organization:
- Savannah River Site (SRS), Aiken, SC (United States)
- Sponsoring Organization:
- USDOE; USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC09-89SR18035
- OSTI ID:
- 5036031
- Report Number(s):
- WSRC-TR-90-477; ON: DE92018129
- Country of Publication:
- United States
- Language:
- English
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36 MATERIALS SCIENCE
ALUMINIUM
STRESS CORROSION
PRODUCTION REACTORS
REACTOR MATERIALS
STAINLESS STEEL-304
CRACK PROPAGATION
CRACKS
MODERATORS
REACTOR COOLING SYSTEMS
SAVANNAH RIVER PLANT
WATER CHEMISTRY
ALLOYS
AUSTENITIC STEELS
CHEMICAL REACTIONS
CHEMISTRY
CHROMIUM ALLOYS
CHROMIUM-NICKEL STEELS
COOLING SYSTEMS
CORROSION
CORROSION RESISTANT ALLOYS
ELEMENTS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
HIGH ALLOY STEELS
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
METALS
NATIONAL ORGANIZATIONS
NICKEL ALLOYS
REACTOR COMPONENTS
REACTORS
STAINLESS STEELS
STEEL-CR19NI10
STEELS
US AEC
US DOE
US ERDA
US ORGANIZATIONS
220600* - Nuclear Reactor Technology- Research
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360105 - Metals & Alloys- Corrosion & Erosion