Theoretical investigation of reactor primary-coolant pipe, welds, and fitting. [PWR; BWR]
Technical Report
·
OSTI ID:5958253
This report contains the analyses resulting from the first year of investigation. 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 those 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. As a third phase of this investigation, stress intensity factors for surface cracks in pressurized and thermally shocked cylinders were derived.
- Research Organization:
- Washington Univ., Seattle (USA). Dept. of Mechanical Engineering
- OSTI ID:
- 5958253
- Report Number(s):
- EPRI-231; ON: DE82900081
- Country of Publication:
- United States
- Language:
- English
Similar Records
Theoretical investigation of reactor primary coolant pipe, welds and fittings. Technical report. [PWR]
Dynamic crack propagation in pipes. [PWR; BWR]
Theoretical investigation of pipe fracture: a summary. Final report
Technical Report
·
Sun Jun 01 00:00:00 EDT 1975
·
OSTI ID:7355945
Dynamic crack propagation in pipes. [PWR; BWR]
Technical Report
·
Sat Feb 28 23:00:00 EST 1981
·
OSTI ID:6547184
Theoretical investigation of pipe fracture: a summary. Final report
Technical Report
·
Thu May 01 00:00:00 EDT 1986
·
OSTI ID:5708742
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BLOWDOWN
BWR TYPE REACTORS
COOLING SYSTEMS
CRACKS
ENERGY SYSTEMS
ENERGY TRANSFER
FAILURES
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MECHANICS
PIPE FITTINGS
PIPES
PRESSURE DROP
PRIMARY COOLANT CIRCUITS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTORS
SAFETY
STRESSES
THERMAL STRESSES
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BLOWDOWN
BWR TYPE REACTORS
COOLING SYSTEMS
CRACKS
ENERGY SYSTEMS
ENERGY TRANSFER
FAILURES
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MECHANICS
PIPE FITTINGS
PIPES
PRESSURE DROP
PRIMARY COOLANT CIRCUITS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTORS
SAFETY
STRESSES
THERMAL STRESSES
WATER COOLED REACTORS
WATER MODERATED REACTORS