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NTIS 바로가기Nuclear engineering and design : an international journal devoted to the thermal, mechanical and structural problems of nuclear energy, v.116 no.3, 1989년, pp.423 - 441
Watashi, K. , Kanazawa, S. , Umeda, H. , Koid, A. , Imazu, A. , Yoshida, H.
To improve the damage evaluation methods in the design code for Fast Breeder Reactors (FBRs), a series of creep-fatigue tests of structural models under thermal transient loadings are going on at Oarai Engineering Center of the Power Reactor and Nuclear Fuel Development Corporation (PNC). Test model...
Nucl. Engrg. Des. Iida 98 305 1987 10.1016/0029-5493(87)90008-2 Simplified analysis and design for elevated temperature component of MONJU
Nakanishi Vol. E 37 1985 Thermal transient test facility for structures
Kitagawa 409 1987 Proc. Int. Conf. on the Role of Fracture Mechanics in Modern Technology A creep-fatigue crack propagation study on type 304 stainless steel
ZAIRYOU Taira 28 308 414 1979 Evaluation of J integral for characterization of creep-fatigue crack growth
Engrg. Fract. Mech. Aoki 16 3 405 1982 10.1016/0013-7944(82)90118-7 Elastic-plastic analysis of cracks in thermally-loaded structures
Watashi Vol. L 93 1987 Creep-fatigue strength evaluation of a thick walled vessel under thermal transient loadings
Engrg. Fract. Mech. Stonesifer 16 625 1982 10.1016/0013-7944(82)90017-0 On the study of the (ΔT)c and C? integrals for fracture analysis under nonsteady creep
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