Published May 1995
| Version v1
Book
Assessments related to cracking in austenitic steels in UK prototype fast reactor (PFR)
Description
Cracking of the PFR reheater and superheater vessel shells by a material ageing mechanism has led to the need to consider the effects of possible similar cracking in other reactor components. This paper describes the structural integrity studies carried out to establish the safety case for the Core Support Structure and the Intermediate Heat Exchangers in the presence of possible defects. (author). 10 refs., 8 figs., 1 tab
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. 345-356.
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
- 27041895
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BRITTLENESS; COALESCENCE; COLD WORKING; COMPUTERIZED SIMULATION; CONES; CRACK PROPAGATION; CYLINDERS; DAMAGING NEUTRON FLUENCE; DEFECTS; DESIGN BASIS ACCIDENTS; DUCTILITY; EVAPORATORS; FAILURE MODE ANALYSIS; FINITE ELEMENT METHOD; FRACTURE MECHANICS; FRACTURE PROPERTIES; IN-VESSEL HEAT EXCHANGERS; INDUSTRIAL RADIOGRAPHY; INTERGRANULAR CORROSION; MANUFACTURING; MECHANICAL STRUCTURES; MOLTEN METAL-WATER REACTIONS; PFR REACTOR; PIPES; PLASTICITY; PLATES; PRESSURE TUBES; PRESSURE VESSELS; PRIMARY COOLANT CIRCUITS; PROBABILISTIC ESTIMATION; REACTOR CORES; REACTOR MONITORING SYSTEMS; REACTOR OPERATION; RISK ASSESSMENT; SECONDARY COOLANT CIRCUITS; SEGREGATION; SERVICE LIFE; SHELLS; SODIUM; STAINLESS STEEL-321; STAINLESS STEEL-347; STEAM GENERATORS; STRAIN AGING; STRAIN HARDENING; STRESS ANALYSIS; SUBMERGED ARC WELDING; SULFUR; SUPPORTS; TEMPERATURE RANGE 0400-1000 K; THERMAL FATIGUE; THERMAL FRACTURES; THERMAL STRESSES; THREE-DIMENSIONAL CALCULATIONS; TITANIUM CARBIDES; TITANIUM NITRIDES; ULTRASONIC TESTING; UNITED KINGDOM; WELDED JOINTS
- Descriptors DEC
- ACCIDENTS; ACOUSTIC TESTING; AGING; ALKALI METALS; ALLOYS; ARC WELDING; AUSTENITIC STEELS; BOILERS; BREEDER REACTORS; CALCULATION METHODS; CARBIDES; CARBON ADDITIONS; CARBON COMPOUNDS; CHEMICAL REACTIONS; CHROMIUM ALLOYS; CHROMIUM-NICKEL STEELS; CONTAINERS; COOLING SYSTEMS; CORROSION; CORROSION RESISTANT ALLOYS; DEVELOPED COUNTRIES; ELEMENTS; EPITHERMAL REACTORS; EUROPE; FABRICATION; FAILURES; FAST REACTORS; FATIGUE; FBR TYPE REACTORS; FRACTURES; HARDENING; HEAT EXCHANGERS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; JOINING; JOINTS; LIFETIME; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; MATERIALS; MATERIALS TESTING; MATERIALS WORKING; MECHANICAL PROPERTIES; MECHANICS; METALS; NEUTRON FLUENCE; NICKEL ALLOYS; NIOBIUM ADDITIONS; NITRIDES; NITROGEN COMPOUNDS; NONDESTRUCTIVE TESTING; NONMETALS; NUMERICAL SOLUTION; OPERATION; PNICTIDES; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SIMULATION; SODIUM COOLED REACTORS; STAINLESS STEELS; STEEL-CR18NI10TI; STEEL-CR18NI11NB; STEELS; STRESSES; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; TEMPERATURE RANGE; TENSILE PROPERTIES; TESTING; TITANIUM ADDITIONS; TITANIUM COMPOUNDS; TRANSITION ELEMENT ALLOYS; TRANSITION ELEMENT COMPOUNDS; TUBES; VAPOR GENERATORS; WELDING; WESTERN EUROPE