The modelling of irradiation embrittlement in submerged-arc welds
- 1. Nuclear Electric plc, Berkeley (United Kingdom). Berkeley Technology Centre
Description
Until very recently, the irradiation embrittlement behavior of submerged-arc welds has been interpreted in terms of two mechanisms, namely a matrix damage component and an additional component due to the irradiation-enhanced production of copper-rich precipitates. However, some of the weld specimens from a recent accelerated re-irradiation experiment have shown high Charpy shifts which exceeded the values expected from the measured shift in yield stress. Microstructural examination has revealed the occurrence of intergranular fracture (IGF) in these specimens, accompanied by grain boundary segregation of phosphorus. Theoretical models were developed to predict the parametric dependence of irradiation-enhanced phosphorus segregation on experimental variables. Using these parametric forms, along with the concept of a critical level of segregation for the onset of IGF instead of cleavage, a three mechanism trend curve has been developed. The form of this trend curve, taking into account IGF as well as matrix and copper embrittlement, is thus mechanistically based. The constants in the equation, however, are obtained by a statistical fit to the actual Charpy shift database
Additional details
Publishing Information
- Publisher
- American Society for Testing and Materials.
- Imprint Place
- West Conshohocken, PA (United States)
- ISBN
- 0-8031-2016-8
- Imprint Title
- Effects of radiation on materials: 17. international symposium
- Imprint Pagination
- [1175 p.].
- Series
- ASTM special technical publication, 1270.
- Journal Page Range
- p. 103-118.
- ISSN
- 1050-7515
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
- 28075666
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- EMBRITTLEMENT; MATHEMATICAL MODELS; MICROSTRUCTURE; PHYSICAL RADIATION EFFECTS; PRESSURE VESSELS; STEELS; SUBMERGED ARC WELDING; WELDED JOINTS
- Descriptors DEC
- ALLOYS; ARC WELDING; CARBON ADDITIONS; CONTAINERS; CRYSTAL STRUCTURE; FABRICATION; IRON ALLOYS; IRON BASE ALLOYS; JOINING; JOINTS; RADIATION EFFECTS; TRANSITION ELEMENT ALLOYS; WELDING
Optional Information
- Secondary number(s)
- CONF-940657--.