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by N. Soneda
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Post-irradiation fracture toughness characterization of four lab-melt plates
A. L. Hiser
Results of crack-arrest tests on irradiated A 508 class 3 steel
S. K. Iskander
GCFR 1/15-scale PCRV steam generator cavity closure half-thickness model test
G. C. Robinson
H.B. Robinson-2 pressure vessel benchmark
I. Remec
Tensile test of 2500-kip prestressing tendons for the PCRV
Vladimir Nicolayeff
Nuclear heat transport
M. M. El-Wakil
Reliability problems of reactor pressure components
Symposium on Application of Reliability Technology to Nuclear Power Plants Vienna 1977.
Irradiation-anneal-reirradiation (IAR) studies of prototypic reactor vessel weldments
J. R. Hawthorne
Reliability of reactor pressure components
International Symposium on Reliability of Reactor Pressure Components (1983 Stuttgart, Germany)
Ductile fracture toughness of modified A 302 grade B plate materials
D. E. McCabe
