Review of phosphorus segregation and intergranular embrittlement in reactor pressure vessel steels

Institution of Chemical Engineers Symposium Series

Volumn , Issue 148, 2000, Pages 151-173

  English, Colin A ^a   Ortner, Susan R ^a   Gage, Gareth ^a   Server, William L ^a   Rosinski, Stan T ^a  

^a RICARDO UK LTD   (United Kingdom)

Author keywords

Grain boundaries; HAZ; Intergranular embrittlement; Phosphorus segregation; Thermal anneal heat treatment

Indexed keywords

AGING OF MATERIALS; ANNEALING; BRITTLE FRACTURE; EMBRITTLEMENT; GRAIN BOUNDARIES; HEAT AFFECTED ZONE; NEUTRON IRRADIATION; PHOSPHORUS; PRESSURE VESSELS; PRESSURIZED WATER REACTORS; PYROLYSIS; SEGREGATION (METALLOGRAPHY);

REACTOR PRESSURE VESSEL (RPV) STEELS;

STEEL TESTING;

EID: 0034459070     PISSN: 03070492     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (30)

1. Effects of manganese on the grain boundary segregation, bulk and grain boundary diffusivity of phosphorus in ferrite
2. Neutron radiation embrittlement studies in support of continued operation and validation by sampling of magnox reactor steel pressure vessels and components
3. Development of embrittlement prediction models for U.S. power reactors and the impact of heat-affected zone to thermal annealing
4. Experimental tests of irradiation-anneal-reirradiated effects on mechanical properties of RPV plate and weld materials
5. On the effect of flux and composition on irradiation hardening at 60°C
6. Quantification of microstructural effects on thermal aging of induced embrittlement in pressure vessel steels
7. Temper embrittlement, irradiation induced phosphorus segregation and implications for post-irradiation annealing of reactor pressure vessels
8. Investigation of temper embrittlement in reactor pressure vessel steels following thermal aging, irradiation, and thermal annealing
9. The modelling of irradiation-enhanced phosphorus segregation in neutron-irradiated reactor pressure vessel submerged arc welds
10. Palisades annealing recovery and irradiation program evaluation of the recovery of hardness and the incidence of intergranular fracture after post-irradiation annealing
11. Temper embrittlement of pressure vessel steels
12. An APFIM survey of grain boundary segregation and precipitation in irradiated pressure vessel steels
13. Irradiation embrittlement of reactor pressure vessel steels due to mechanisms other than radiation hardening
14. Temper embrittlement of phosphorus on thermal and neutron embrittlement of pressure vessel steels
15. Analysis of radiation embrittlement results from a French forging examined in the second phase of an iaea-co-ordinated research program
16. Comparison of observed and predicted data on radiation induced grain boundary phosphorus segregation In VVER steels
17. Embrittlement, hardening, and grain boundary composition in an irradiated and thermally aged Fe-P-C alloy
18. A microstructural examination of irradiated reactor pressure vessel weld samples