Published September 1992
| Version v1
Journal article
Irradiation-induced grain and lath boundary segregation in ferritic-martensitic steels
Creators
- 1. Inst. of Polymer Technology and Materials Engineering, Loughborough Univ. of Technology (United Kingdom)
- 2. Materials and Chemistry Div., Harwell Lab. (United Kingdom)
Description
The temperature dependence of irradiation-induced nonequilibrium segregation of Si and P to grain boundaries has been modelled in bcc ferritic iron, taken to represent ferritic-martensitic steels. The relevant point defect properties required for analysis are documented and the approximations used to circumvent lack of precise data on point defect formation, migration and solute binding energies highlighted. Analytical electron microscopy results are presented on solute segregation to lath boundaries in fast reactor irradiated FV448 martensitic steel, and compared with calculated behaviour. Predictions of enhanced interfacial Si segregation after irradiation at 400deg C are in accord with experimental observations. (orig.)
Additional details
Publishing Information
- Journal Title
- Journal of Nuclear Materials
- Journal Volume
- 191-194
- Journal Issue
- pt.B
- Journal Page Range
- p. 858-861.
- ISSN
- 0022-3115
- CODEN
- JNUMAM
Conference
- Title
- 5. international conference on fusion reactor materials (ICFRM-5).
- Dates
- 17-22 Nov 1991.
- Place
- Clearwater, FL (United States).
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 24031548
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY; S36: MATERIALS SCIENCE; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- CHEMICAL COMPOSITION; CHROMIUM STEELS; DOSE RATES; EXPERIMENTAL DATA; FERRITIC STEELS; FIRST WALL; FISSION NEUTRONS; MARTENSITIC STEELS; PHOSPHORUS ADDITIONS; PHYSICAL RADIATION EFFECTS; RADIATION DOSES; SEGREGATION; SILICON ADDITIONS; TEMPERATURE DEPENDENCE; TEMPERATURE RANGE 0273-0400 K; TEMPERATURE RANGE 0400-1000 K; THERMONUCLEAR REACTOR MATERIAL
- Descriptors DEC
- ALLOYS; BARYONS; CARBON ADDITIONS; CHROMIUM ALLOYS; DATA; ELEMENTARY PARTICLES; FERMIONS; HADRONS; HIGH ALLOY STEELS; INFORMATION; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS; NEUTRONS; NUCLEONS; NUMERICAL DATA; RADIATION EFFECTS; STAINLESS STEELS; STEELS; TEMPERATURE RANGE; THERMONUCLEAR REACTOR WALLS