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- [21] Investigation of the Beltline Welding Seam and Base Metal of the Greifswald WWER-440 Unit 1 Reactor Pressure Vessel JOURNAL OF ENGINEERING FOR GAS TURBINES AND POWER-TRANSACTIONS OF THE ASME, 2011, 133 (05):
- [22] EXPERIENCE WITH THE APPLICATION OF DIAGNOSTIC SYSTEMS AT WWER-440 KERNENERGIE, 1988, 31 (03): : 106 - 110
- [23] Application of Small Punch Testing Methods for Monitoring of WWER-440 Reactor Pressure Vessels Irradiation Embrittlement DETERMINATION OF MECHANICAL PROPERTIES OF MATERIALS BY SMALL PUNCH AND OTHER MINIATURE TESTING TECHNIQUES, 2ND INTERNATIONAL CONFERENCE SSTT, 2012, : 154 - 158
- [25] Assessment of the master curve approach on three reactor pressure vessel steels International Journal of Fracture, 2003, 119 : 161 - 178
- [26] MASTER CURVE APPROACH FOR SOME JAPANESE REACTOR PRESSURE VESSEL STEELS PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE - 2008, VOL 6, PT A AND B, 2009, : 855 - 862
- [27] Hydrogen embrittlement of the pressure vessel structural materials in a WWER-440 nuclear power plant SPECIAL ISSUE OF FOR THE FIFTH INTERNATIONAL SYMPOSIUM ON INNOVATIVE NUCLEAR ENERGY SYSTEMS, 2017, 131 : 379 - 385
- [30] ANALYSIS OF ACTINIDES IN THE PRIMARY COOLANT OF A WWER-440 TYPE REACTOR JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY-ARTICLES, 1993, 170 (02): : 399 - 409