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Showing 10 out of a total of 2111 results for community: International Association for Structural Mechanics in Reactor Technology (IASMiRT). (0.004 seconds)

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Modelling of high cycle fatigue crack initiation and growth based on real polycrystalline microstructure

M. Niffenegger; V. H. Solaz (IASMiRT, 2017-08-20)
Development of Multi-Metallic layered composite(MMLC) Accident-Tolerant fuel cladding

J. H. Moon; S. G. Kim; C. B. Bahn (IASMiRT, 2017-08-20)
Cracks in concrete containment - comparing the self-healing potential under variable air and steam loads between real scale and laboratory scale

M. Zemann; N. Herrmann; K. Willers; L. Gerlach; H. Müller (IASMiRT, 2017-08-20)
Effect of welding residual stress on the creep buckling behavior of fast breeder reactor

F.Liu; F.Z.Xuan (IASMiRT, 2017-08-20)
Unified constitutive modeling of three alloys under a wide range of temperature

Y. Takahashi (IASMiRT, 2017-08-20)
Stress intensity factor estimation for defective pipe elbows

Y. Lei; P. Budden (IASMiRT, 2017-08-20)
Pressurized thermal shock (pts) analysis in german nuclear power plants

S. Fricke; Th. Riekert; M. Braun (IASMiRT, 2017-08-20)
Nonlinear analysis rules comparison - benchmark first results and recommendations

C.Faidy; A.Wasylyk (IASMiRT, 2017-08-20)
Concrete strength evaluation of massive concrete structures based on the data obtained from decommissioning nuclear power plant

K. Yokokura; H. Wada; O. Kontani; I. Maruyama (IASMiRT, 2017-08-20)
An evaluation of the carburised microstructure of ferritic 9Cr-1Mo steel following exposure to hot CO2 gas

C. Liu; P. J. Heard; P. E. J. Flewitt; T. B. Scott; J. Pearson; A. Shin (IASMiRT, 2017-08-20)

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