Explore Books on
nuclear pressure vessels
1-24 of 236 Books
Post-irradiation fracture toughness characterization of four lab-melt plates
Post-irradiation fracture toughness characterization of four lab-melt plates
By A. L. Hiser
Results of crack-arrest tests on irradiated A 508 class 3 steel
Results of crack-arrest tests on irradiated A 508 class 3 steel
By S. K. Iskander
Tensile test of 2500-kip prestressing tendons for the PCRV
Tensile test of 2500-kip prestressing tendons for the PCRV
By Vladimir Nicolayeff
GCFR 1/15-scale PCRV steam generator cavity closure half-thickness model test
GCFR 1/15-scale PCRV steam generator cavity closure half-thickness model test
By G. C. Robinson
H.B. Robinson-2 pressure vessel benchmark
H.B. Robinson-2 pressure vessel benchmark
By I. Remec
Ductile fracture toughness of modified A 302 grade B plate materials
Ductile fracture toughness of modified A 302 grade B plate materials
By D. E. McCabe
Reliability of reactor pressure components
Reliability of reactor pressure components
By International Symposium on Reliability of Reactor Pressure Components (1983 Stuttgart, Germany)
Reliability problems of reactor pressure components
By Symposium on Application of Reliability Technology to Nuclear Power Plants Vienna 1977.
Boiling-water reactor internals aging degradation study
Boiling-water reactor internals aging degradation study
By K. H. Luk
Crack-arrest tests on two irradiated high-copper welds
Crack-arrest tests on two irradiated high-copper welds
By S. K. Iskander
Application of a two-mechanism model for environmentally-assisted crack growth
Application of a two-mechanism model for environmentally-assisted crack growth
By G. Gabetta
A review of large-scale fracture experiments relevant to pressure vessel integrity under pressurized thermal shock conditions
A review of large-scale fracture experiments relevant to pressure vessel integrity under pressurized thermal shock conditions
By C. E. Pugh
Extrapolation of the J-R curve for predicting reactor vessel integrity
Extrapolation of the J-R curve for predicting reactor vessel integrity
By J. D. Landes
Improved embrittlement correlations for reactor pressure vessel steels
Improved embrittlement correlations for reactor pressure vessel steels
By E. D. Eason
Irradiation-anneal-reirradiation (IAR) studies of prototypic reactor vessel weldments
Irradiation-anneal-reirradiation (IAR) studies of prototypic reactor vessel weldments
By J. R. Hawthorne
Irradiation Embrittlement of Reactor Pressure Vessels (RPVs) in Nuclear Power Plants
Irradiation Embrittlement of Reactor Pressure Vessels (RPVs) in Nuclear Power Plants
By N. Soneda
Irradiation Embrittlement of Reactor Pressure Vessels (RPVs) in Nuclear Power Plants
Irradiation Embrittlement of Reactor Pressure Vessels (RPVs) in Nuclear Power Plants
By Naoki Soneda
Advances in non-destructive examination for structural integrity
By International Seminar on "Non-Destructive Examination in Relation to Structural Integrity" (2nd 1981 Paris, France)
Neutron exposure parameters for capsule 10.05 in the Heavy-Section Steel Irradiation Program tenth irradiation series
Neutron exposure parameters for capsule 10.05 in the Heavy-Section Steel Irradiation Program tenth irradiation series
By I. Remec
Pool critical assembly pressure vessel facility benchmark
Pool critical assembly pressure vessel facility benchmark
By I. Remec
Application surveillance programme results to reactor pressure vessel integrity assessment
By International Atomic Energy Agency
Marble Hill annealing demonstration evaluation
Marble Hill annealing demonstration evaluation
By C. B. Oland