Effects of annealing time on the recovery of Charpy V-notch properties of irradiated high-copper weld metal
- 1. Oak Ridge National Lab., TN (United States). Metals and Ceramics Div.
Description
One of the options to mitigate the effects of irradiation on reactor pressure vessels is to thermally anneal them to restore the toughness properties that have been degraded by neutron irradiation. An important issue to be resolved is the effect on the toughness properties of reirradiating a vessel that has been annealed. This paper describes the annealing response of irradiated high-copper submerged-arc weld HSSI 73W. For this study, the weld has been annealed at 454 C (850 F) for lengths of time varying between 1 and 14 days. The Charpy V-notch 41-J (30-ft-lb) transition temperature (TT41J) almost fully recovered for the longest period studied, but recovered to a lesser degree for the shorter periods. No significant recovery of the TT41J was observed for a 7-day anneal at 343 C (650 F). At 454 C for the durations studied, the values of the upper-shelf impact energy of irradiated and annealed weld metal exceeded the values in the unirradiated condition. Similar behavior was observed after aging the unirradiated weld metal at 460 and 490 C for 1 week
Availability note (English)
MF available from INIS under the Report Number; Also available from OSTI as DE96010733; NTIS; US Govt. Printing Office Dep.Files
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Additional details
Publishing Information
- Imprint Pagination
- 18 p.
- Report number
- CONF-940657--13
Conference
- Title
- 17. symposium on effects of radiation on materials.
- Dates
- 20-23 Jun 1994.
- Place
- Sun Valley, ID (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 27064991
- Subject category
- S36: MATERIALS SCIENCE; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- COPPER ALLOYS; EXPERIMENTAL DATA; FRACTURE PROPERTIES; MITIGATION; NUCLEAR POWER PLANTS; PHYSICAL RADIATION EFFECTS; PRESSURE VESSELS; TEMPERATURE RANGE 0400-1000 K; WELDED JOINTS
- Descriptors DEC
- ALLOYS; CONTAINERS; DATA; INFORMATION; JOINTS; MECHANICAL PROPERTIES; NUCLEAR FACILITIES; NUMERICAL DATA; POWER PLANTS; RADIATION EFFECTS; TEMPERATURE RANGE; THERMAL POWER PLANTS; TRANSITION ELEMENT ALLOYS
Optional Information
- Contract/Grant/Project number
- Contract AC05-84OR21400
- Funding organization
- Nuclear Regulatory Commission, Washington, DC (United States).