Nothing Special   »   [go: up one dir, main page]

Majumdar, 1981 - Google Patents

Designing against low-cycle fatigue at elevated temperature

Majumdar, 1981

Document ID
11947689845019953954
Author
Majumdar S
Publication year
Publication venue
Nuclear Engineering and Design

External Links

Snippet

Factors that are important in determining low-cycle fatigue damage at elevated temperature are discussed. The linear damage rule for computing creep-fatigue damage is shown to be unsatisfactory in many situations. The damage-rate equations developed at Argonne …
Continue reading at www.sciencedirect.com (other versions)

Classifications

    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GASES [GHG] EMISSION, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors
    • Y02E30/40Other aspects relating to nuclear fission
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C17/00Monitoring; Testing ; Maintaining
    • G21C17/02Devices or arrangements for monitoring coolant or moderator
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/02Fuel elements
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C17/00Monitoring; Testing ; Maintaining
    • G21C17/06Devices or arrangements for monitoring or testing fuel or fuel elements outside the reactor core, e.g. for burn-up, for contamination
    • GPHYSICS
    • G01MEASURING; TESTING
    • G01NINVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
    • G01N3/00Investigating strength properties of solid materials by application of mechanical stress
    • GPHYSICS
    • G01MEASURING; TESTING
    • G01NINVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
    • G01N2203/00Investigating strength properties of solid materials by application of mechanical stress
    • G01N2203/0058Kind of property studied
    • G01N2203/006Crack, flaws, fracture or rupture
    • G01N2203/0062Crack or flaws

Similar Documents

Publication Publication Date Title
Billone et al. Ductile-to-brittle transition temperature for high-burnup cladding alloys exposed to simulated drying-storage conditions
Steinbrück et al. High-temperature oxidation and quench behaviour of Zircaloy-4 and E110 cladding alloys
Majumdar Designing against low-cycle fatigue at elevated temperature
Billone et al. Ductile-to-Brittle Transition Temperature for High Burnup Zircaloy-4 and ZIRLO (TM) Cladding Alloys Exposed to Simulated Drying Storage Conditions.
Hózer et al. Ballooning experiments with VVER cladding
Pastore et al. Modelling of fuel behaviour during loss-of-coolant accidents using the BISON code
Bouineau et al. A new model to predict the oxidation kinetics of zirconium alloys in a pressurized water reactor
Coleman et al. The effect of microstructure on delayed hydride cracking behavior of Zircaloy-4 fuel cladding—an International Atomic Energy Agency Coordinated Research Program
Williamson et al. Modelling of LOCA Tests with the BISON Fuel Performance Code
Dragunov et al. Stress–strain kinetics in calculations of high-temperature strength and longevity of reactor structures
Nickel et al. Development and qualification of materials for structural components for the high-temperature gas-cooled reactor
Eason et al. Disposition curves for irradiation-assisted stress corrosion cracking of austenitic stainless steels in light water reactor environments
Leary et al. Critical Review of Strain Measures for Characterisation of Fatigue Damage in ASME Section III Fatigue Assessments
Bouffioux et al. Interim Dry Storage of PWR Spent Fuel Assemblies: Development of a Long Term Creep Law to Assess the Fuel Cladding Integrity
Woodford et al. Stress relaxation testing as a basis for creep analysis and design of silicon nitride
Nickel et al. Aspects of design codes for metallic high temperature components
Jeong et al. Environmental fatigue crack propagation behavior of cast stainless steels under PWR condition
Yagnik et al. Effect of hydride distribution on the mechanical properties of zirconium-alloy fuel cladding and guide tubes
Hanlon The Effect of Testing Direction on DHC Growth Rate Using Zr-2.5 Nb Plate
Cho et al. Development of evaluation procedures for crack initiation from in-service flaws in candu zr-2.5 nb pressure tubes with hydrogen
Jeon et al. Computational simulation of cold work effect on PWSCC growth in Alloy 600TT steam generator
Shewfelt The ballooning of fuel cladding tubes: theory and experiment
Shewfelt Ballooning of CANDU pressure tubes. Model assessment
Sagar et al. Zircaloy-4 fuel pin failure under simulated loss-of-coolant-accident conditions: Creep and rupture
Desquines et al. A new model on radial hydride precipitation in Zircaloy-4 claddings under decaying stress and temperature transient