Grain Boundary Phosphorus Segregation in Thermally Aged Low Alloy Steels

References

• English , C. A. , Ortner , S. R. , Gage , G. , Server , W. L. and Rosinski , S. T. 2001 . “Review of phosphorus segregation and intergranular embrittlement in reactor pressure vessel steels” . In Effects of Radiation Materials , ASTM STP 1405 151 – 173 .
   Google Scholar
• Buswell , J. T. , Bolton , G. J. , Wootton , M. R. , Bischler , P. J. E. , Jones , R. B. , Jones , L. T. , Phythian , W. J. and Sinclair , R. R. 1993 . “The irradiation hardening and embrittlement of a mild steel submerged-arc weld” . In Effects of Radiation Materials , ASTM STP 1175 332 – 351 .
   Google Scholar
• Bischler , P. J. E. and Wild , R. K. 1996 . “A microstructural study of phosphorus segregation and intergranular fracture in neutron irradiated submerged-arc welds” . In Effects of Radiation Materials , ASTM STP 1270 260 – 273 .
   Google Scholar
• Miller , M. K. and Burke , M. G. 1993 . “An APFIM survey of grain boundary segregation and precipitation in irradiated pressure vessel steels” . In Effects of Radiation Materials , ASTM STP 1175 492 – 502 .
   Google Scholar
• Miller , M. K. , Jayaram , R. and Russell , K. F. 1995 . “Characterization of phosphorus segregation in neutron-irradiated Russian pressure vessel steel weld” . J. Nucl. Mater. , 225 : 215 – 224 .
   Google Scholar
• Jones , R. B. and Bolton , C. J. 1996 . “Neutron irradiation embrittlement studies in support of continued operation and validation by sampling of magnox reactor steel pressure vessel and components” . In Proc. 24^th Water Reactor Meeting, organized by USNRC, Oct. 1996
   Google Scholar
• Gurovich , B. A. , Kuleshovs , E. A. , Shtrombakh , Ya. I. , Zabusov , O. O. and Krasikov , E. A. 2000 . “Intergranular and intragranular phosphorus segregation in Russian pressure vessel steels due to neutron irradiation” . J. Nucl. Mater. , 279 : 259 – 272 .
   Web of Science ®Google Scholar
• Beer , W. B. and Buswell , J. T. 1999 . “The effect of heat treatment on phosphorus segregation in a submerged-arc weld metal” . In Effects of Radiation Materials , ASTM STP 1325 317 – 330 .
   Google Scholar
• Bolton , C. J. , Buswell , J. T. , Jones , R. B. , Moskovic , R. and Prist , R. H. 1996 . “The modelling of irradiation embrittlement in submerged-arc welds” . In Effects of Radiation Materials , ASTM STP 1270 103 – 118 .
   Google Scholar
• Nikolaeva , A. V. , Nikolaev , Y. A. and Kryukov , A. M. 1994 . “Grain boundary embrittlement due to reactor pressure vessel annealing” . J. Nucl. Mater. , 211 : 236 – 243 .
   Google Scholar
• McElroy , R. J. , English , C. A. , Foreman , A. J. , Gage , G. , Hyde , J. M. , Ray , P. H. N. and Vatter , I. A. 1999 . “Temper embrittlement, irradiation induced phosphorus segregation and implications for post-irradiation annealing of reactor pressure vessels” . In Effects of Radiation Materials , ASTM STP 1325 296 – 316 .
   Google Scholar
• Ohno , K. and Fukuya , K. 2000 . “Microstructural evolution in reactor pressure vessel steel under neutron irradiation” . J. Inst. Nucl. Saf. Syst. , : 100 [in Japanese]
   Google Scholar
• Erhart , H. and Grabke , H. J. 1981 . “Equilibrium segregation of phosphorus at grain boundaries of Fe-P, Fe-C-P, Fe-Cr-P, and Fe-Cr-C-P alloys” . Metal Sci. , 15 : 401 – 408 .
   Web of Science ®Google Scholar
• Hänsel , H. and Grabke , H. J. 1986 . “Grain boundary segregation of phosphorus and carbon in ferritic iron” . Scripta Metallurgica , 20 : 1641 – 1644 .
   Google Scholar
• Druce , S. G. , Gage , G. and Jordan , G. 1986 . “Effect of ageing on properties of pressure vessel steels” . Acta Metal. , 34 : 641 – 652 .
   Google Scholar
• Kubo , H. , Sakanashi , M. and Kimura , A. 2002 . Abstract of 132^nd Annual Meeting of Japan Institute on Metals 563 [in Japanese]
   Google Scholar
• Vatter , I. A. and Hippslley , C. A. 1990. . “Review of thermal ageing data and its application to operating reactor pressure vessels” . In NEA/CSNI Workshop on Safety Assessment of Reactor Pres sure Vessels Espoo, Finland, Oct
   Google Scholar
• Druce , S. G. , English , C. A. , Foreman , A. J. E. , MocEloy , R. J. , Vatter , I. A. , Bolton , C. J. , Buswell , J. T. and Jones , R. B. 1996 . “The modelling of irradiation-enhanced phosphorus segregation in neutron irradiated reactor pressure vessel submerged-arc welds” . In Effects of Radiation Materials , ASTM STP 1270 119 – 137 .
   Google Scholar