Guia practica para uso de ASME II

Relationship Deformation Cracking

Alloy690inPWR

Fatigue Reactor Components

A Flow-partitioned Deformation Zone Model for Defect Formation During Friction Stir Welding

IAEA 1556 Assessment and management of ageing of major nuclear power plant components important to safety PWR pressure vessels 2007 update.pdf

Using the Engineer Literature

Welding

Effect of Commercial Cladding on the Fracture Behavior

ASME Code Calculation BMI Repair

Fatigue Testing in Socket Welds

Thermal and mechanical analysis of weld

Investigations on Partial Penetration Welded Nozzle

Reactor Vessel Cladding

LEAK IN CONTROL ROD DRIVE MECHANISM HOUSING

A Review of Fatigue Failures in LWR Plants in Japan

Clevis Bolts Material 2

Clevis Bolts Material 3

WELD-OP-I

Weld Theory