Structural Mechanics in Reactor Technology

Front Cover
F.H. Wittmann
CRC Press, Jan 1, 1987 - Technology & Engineering - 6800 pages
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Contents

Development and application of the CRAMP code for fast reactor core
3
Seismic analysis of a large FBR coreSome SNR2 preliminary calculations
27
An assessment of LMR reactor core vertical acceleration under seismic events
43
Experimental and analytical study of creep cracks damage in high temperature
59
FCorsi A Fabi PDi Giamberardino G Botti G Pasquale VDapor
73
Analysis of piping response to thermal and operational transients
89
Erosion effects due to a hot liquid jet impinging obliquely on a solid plate
107
Elastic creepfatigue evaluation for ASME Code
123
Buckling of cylindrical shells
157
Stability of inner baffleshell of pool type LMFBRExperimental and
173
Buckling analyses for shell and plate structures of the SNR2 reactorblock
185
Shear buckling of cylindrical vessels benchmarkexercise
199
Plastic buckling of short cylinders with axial temperature distribution under
219
Experience obtained from the construction of Super Phenix 1 reactor
233
Fast breeder reactor 1500 MWScale model of a safety vessel anchored to
253
Fast breeder reactor primary pump discharge sphere support device
271

Effect of primary static stress on torsional low cycle fatigue of stainless steel
137

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