共 50 条
- [1] Assessment of neutron irradiation-induced grain boundary embrittlement by phosphorous segregation in a reactor pressure vessel steel EFFECTS OF RADIATION ON MATERIALS: 22ND SYMPOSIUM, 2006, 1475 : 212 - +
- [4] NUMERICAL SIMULATION OF IRRADIATION-INDUCED GRAIN-BOUNDARY PHOSPHOROUS SEGREGATION IN REACTOR PRESSURE VESSEL STEELS USING RATE THEORY MODEL WITH FIRST-PRINCIPLES CALCULATIONS ASME PRESSURE VESSELS AND PIPING CONFERENCE 2009, VOL 1: CODES AND STANDARDS, 2010, : 395 - 402
- [7] IRRADIATION-EMBRITTLEMENT OF REACTOR PRESSURE VESSEL STEEL PROCEEDINGS OF THE 18TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING 2010, VOL 5, 2011, : 93 - 96
- [8] Irradiation-induced Cu aggregations in Fe: An origin of embrittlement of reactor pressure vessel steels PHYSICAL REVIEW B, 2001, 63 (13):
- [9] Effect of neutron flux on low temperature irradiation embrittlement of reactor pressure vessel steel J Nucl Mater, 1-2 (78-90):