Test procedures used in the UK Alloy X-750 evaluation program
Creators
Description
As a result of an increased incidence of stress corrosion cracking (SCC) of alloy X-750 control rod guide tube support pins installed in the primary circuit of operating pressurized water reactors, UKAEA and CEGB have developed a program to investigate the effectiveness of changes in pin design and material condition required to minimize the occurrence of stress corrosion cracking. Three modifications that are most likely to be beneficial in reducing the susceptibility of SCC are as follows: 1. A high-temperature solution anneal (1093 degree C, 2000 degree F) prior to the single aging treatment (704 degree C, 1300 degree F). 2. Reducing the pin maximum nominal shank stress by lowered installation torque. 3. Revising the pin design to reduce the stress concentration factor. Reducing the maximum shank stress and the bolt head/shank concentration factor has lowered the maximum peak stress at the shoulder by approximately 25 percent. Material/heat treatment modifications will be evaluated using U-bends, bent beam, and dynamic strain tests. Design changes and material/heat treatment conditions will be evaluated using notched bar tensile tests. 5 figs
Additional details
Publishing Information
- Imprint Title
- Proceedings: 1986 workshop on advanced high-strength materials
- Imprint Pagination
- 578 p.
- Journal Page Range
- p. 12.1-12.14.
- Report number
- EPRI-NP--6363
Conference
- Title
- Workshop on advanced high-strength materials.
- Dates
- 12-13 Mar 1986.
- Place
- Clearwater Beach, FL (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 21036842
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- AGING; ALLOY-NI73CR15FE7TI3; ANNEALING; CONTROL ROD DRIVES; CORROSION RESISTANCE; CRACKS; FAILURES; FASTENERS; HEAT TREATMENTS; MATERIALS TESTING; MICROSTRUCTURE; MODIFICATIONS; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTOR MATERIALS; SIZEWELL-B REACTOR; SPECIFICATIONS; STRESS CORROSION; STRESS INTENSITY FACTORS; UNITED KINGDOM
- Descriptors DEC
- ALLOYS; ALUMINIUM ADDITIONS; CHEMICAL REACTIONS; CHROMIUM ALLOYS; COOLING SYSTEMS; CORROSION; CORROSION RESISTANT ALLOYS; CRYSTAL STRUCTURE; DEVELOPED COUNTRIES; ENRICHED URANIUM REACTORS; EUROPE; HEAT RESISTING ALLOYS; INCONEL ALLOYS; IRON ALLOYS; MATERIALS; NICKEL ALLOYS; NICKEL BASE ALLOYS; NIOBIUM ADDITIONS; POWER REACTORS; REACTOR COOLING SYSTEMS; REACTORS; TESTING; THERMAL REACTORS; TITANIUM ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-8603261--.