共 50 条
- [21] EVALUATION ON CONSTRAINT EFFECT OF REACTOR PRESSURE VESSEL UNDER PRESSURIZED THERMAL SHOCK PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE - 2013, VOL 1B: CODES AND STANDARDS, 2014,
- [22] EVALUATION OF THE J INTEGRAL AND THE CLADDING EFFECT OF A CRACK IN THE REACTOR PRESSURE VESSEL. Bulletin of the JSME, 1986, 29 (258): : 4026 - 4030
- [25] EXPERIMENTAL CHARACTERIZATION OF INCLUSIONS AND IMPURITIES IN PLATES AND WELDS OF REACTOR PRESSURE-VESSEL STEELS JOURNAL OF METALS, 1982, 34 (08): : 49 - 49
- [26] RADIATION PROTECTION EXPERIENCE WITH NRX REACTOR VESSEL CHANGE AMERICAN INDUSTRIAL HYGIENE ASSOCIATION JOURNAL, 1971, 32 (05): : 11 - &
- [30] Residual stresses evaluation in welds and implications for design for pressure vessel applications JOURNAL OF PRESSURE VESSEL TECHNOLOGY-TRANSACTIONS OF THE ASME, 2006, 128 (04): : 638 - 643