共 50 条
- [1] 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
- [3] Burst Strength of Cylindrical Reinforced Concrete Reactor Vessel. Bautechnik, Ausgabe A, 1975, 52 (03): : 73 - 76
- [6] THERMAL AND STRUCTURAL ANALYSIS OF THE SUPPORT REGION OF AN LMFBR REACTOR VESSEL. Transactions of the International Conference on Structural Mechanics in Reactor Technology, 1979, G.
- [8] ANALYSIS OF A LARGE SADDLE SUPPORTED HORIZONTAL PRESSURE VESSEL. American Society of Mechanical Engineers (Paper), 1977, (77 -PVP-18):
- [9] INTEGRITY ASSESSMENT FOR NUCLEAR POWER PLANTS PRESSURE VESSEL. Nippon Genshiryoku Gakkaishi/Journal of the Atomic Energy Society of Japan, 1984, 26 (07): : 587 - 593
- [10] BRITTLE FRACTURE OF A BRICK-LINED PRESSURE VESSEL. Materials Performance, 1986, 25 (03): : 24 - 26