Theoretical investigation of reactor primary coolant pipe, welds and fittings. Technical report. [PWR]

Technical Report · Sun Jun 01 04:00:00 EDT 1975

OSTI ID:7355945

Emery, A F; Kobayashi, A S; Love, W J

A dynamic analytical model for a running axial crack in a cylindrical shell was developed and used to study the propagation of cracks due to a steady initial pressure and cracks arising during instantaneous pressurization. A thermal hydraulic two phase depressurization model which permits depressurization to occur by leakage through an axial crack was also developed to permit the study of axial running cracks subjected to the varying pressure caused by leakage. Stress intensity factors for surface cracks in pressurized and thermally shocked cylinders were also derived.

• Research Organization: Washington Univ., Seattle (USA). Dept. of Mechanical Engineering
• OSTI ID: 7355945
• Report Number(s): PB-244431
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
COOLING SYSTEMS
CRACKS
JOINTS
LEAKS
MATHEMATICAL MODELS
PIPE FITTINGS
PIPES
PRIMARY COOLANT CIRCUITS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
STRESSES
THERMAL STRESSES
WATER COOLED REACTORS
WATER MODERATED REACTORS
WELDED JOINTS