Heat-up and cooldown pressure temperature limit curves according to appendix G to the asme code section III
Description
The technical specifications for light water reactors impose pressure-temperature limits on the reactor coolant pressure boundary during operation to assure protection against non-ductile failure. The operation limit curves are the permissible pressure-temperature relationships that avoid the unstable propagation of a reference crack in the vessel wall during the reactor heat-up and cooldown. These limits are calculated in accordance with the recommendations of Appendix G to the ASME Code Section III which are based upon the principles of linear fracture mechanics. Flaws in the weld metal or in the base material are assumed to be axial oriented and to have a semi-elliptical shape either on the inside or outside surfaces of the vessel. The stress intensity factor is calculated at the tip of the crack for combined thermal and mechanical loads and compared to the stress intensity factor allowed by the code. (J.S.)
Additional details
Publishing Information
- Publisher
- Centre d'Etudes de Saclay.
- Imprint Place
- Gif-sur-Yvette (France)
- ISBN
- 2-7272-0177-X
- Imprint Title
- Principles of fracture mechanics applications in nuclear power plants
- Imprint Pagination
- 394 p.
- Journal Page Range
- p. 357-361.
Conference
- Title
- International Seminar on Structural Integrity.
- Acronym
- SISSI 94
- Dates
- 28-29 Apr 1994.
- Place
- Saclay (France).
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 27041717
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BENDING; COMPRESSION STRENGTH; COMPUTERIZED SIMULATION; CRACK PROPAGATION; DAMAGING NEUTRON FLUENCE; DEFECTS; DUCTILITY; DYNAMIC LOADS; ELASTICITY; FRACTURE MECHANICS; FRACTURE PROPERTIES; HYDROSTATICS; MECHANICAL TESTS; PRESSURE VESSELS; REACTOR COOLING SYSTEMS; REACTOR OPERATION; REACTOR SHUTDOWN; REACTOR START-UP; SAFETY ANALYSIS; SERVICE LIFE; STATIC LOADS; STEADY-STATE CONDITIONS; STRESS INTENSITY FACTORS; THERMAL FATIGUE; THERMAL STRESSES; TRANSIENTS; WATER COOLED REACTORS; WELDED JOINTS
- Descriptors DEC
- CONTAINERS; COOLING SYSTEMS; DEFORMATION; FATIGUE; JOINTS; LIFETIME; MATERIALS TESTING; MECHANICAL PROPERTIES; MECHANICS; NEUTRON FLUENCE; OPERATION; REACTOR COMPONENTS; REACTORS; SHUTDOWN; SIMULATION; START-UP; STRESSES; TENSILE PROPERTIES; TESTING