Park et al., 2011 - Google Patents
Dynamic response of a nuclear fuel rod impacting on elastoplastic gapped supportsPark et al., 2011
- Document ID
- 5499846645419234442
- Author
- Park N
- Suh J
- Jeon K
- Publication year
- Publication venue
- Nuclear engineering and design
External Links
Snippet
The paper concerns the study of the vibrational behavior of a fuel rod supported by elastoplastic supports. Nuclear fuel rods in reactor conditions are always exposed to turbulent flow, which in turn creates random vibrations. Shock vibration can also occur as a …
- 230000004044 response 0 title abstract description 27
Classifications
-
- G—PHYSICS
- G06—COMPUTING; CALCULATING; COUNTING
- G06F—ELECTRICAL DIGITAL DATA PROCESSING
- G06F17/00—Digital computing or data processing equipment or methods, specially adapted for specific functions
- G06F17/50—Computer-aided design
- G06F17/5009—Computer-aided design using simulation
- G06F17/5018—Computer-aided design using simulation using finite difference methods or finite element methods
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/02—Fuel elements
- G21C3/04—Constructional details
-
- Y—GENERAL 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
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GASES [GHG] EMISSION, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
- Y02E30/40—Other aspects relating to nuclear fission
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| Mohany et al. | Modelling of fuel bundle vibration and the associated fretting wear in a CANDU fuel channel | |
| Kim | The study on grid-to-rod fretting wear models for PWR fuel | |
| Hassan et al. | Damping-controlled fluidelastic instability forces in multi-span tubes with loose supports | |
| Hu et al. | Effects of gap size and excitation frequency on the vibrational behavior and wear rate of fuel rods | |
| Lu et al. | CASL virtual reactor predictive simulation: Grid-to-rod fretting wear | |
| Jiang et al. | Spent nuclear fuel system dynamic stability under normal conditions of transportation | |
| Knudsen et al. | Vibro-impact dynamics of a periodically forced beam | |
| Rubiolo | Probabilistic prediction of fretting-wear damage of nuclear fuel rods | |
| Wang et al. | Simulation of dynamic characteristics of NHR200-II fuel assembly | |
| Nazari et al. | Numerical investigation of the modal characteristics for a VVER-1000 fuel assembly | |
| Park et al. | Dynamic response of a nuclear fuel rod impacting on elastoplastic gapped supports | |
| Kim | The effect of fuel rod supporting conditions on fuel rod vibration characteristics and grid-to-rod fretting wear | |
| Akbar Gholampour et al. | A new unconditionally stable time integration method for analysis of nonlinear structural dynamics | |
| Choi et al. | Vibration analysis of a dummy fuel rod continuously supported by spacer grids | |
| Sawadogo et al. | Time domain simulation of the vibration of a steam generator tube subjected to fluidelastic forces induced by two-phase cross-flow | |
| Brunetto et al. | Extension of the OFFBEAT fuel performance code to finite strains and validation against LOCA experiments | |
| Elbanhawy et al. | Modelling of fully-flexible fuel bundles | |
| Hassan et al. | Evaluation of the integrity of steam generator tubes subjected to flow induced vibrations | |
| Pandey et al. | Understanding the mechanics of creep deformation to develop a surrogate model for contact assessment in CANDU® fuel channels | |
| Huang et al. | Towards modeling of Grid to Rod and the effect of its nonlinear dynamic behaviors on grid-to-rod fretting wear | |
| Park et al. | Indirect estimation method of the turbulence induced fluid force spectrum acting on a fuel rod | |
| Shen et al. | A multi‐layer thermo‐mechanical coupling hysteretic model for high damping rubber bearings at low temperature | |
| Park et al. | Development of a simplified pressurized water reactor fuel assembly nonlinear model | |
| Jin et al. | Nonlinear model for assessing seismic resilience in nuclear fuel assemblies | |
| Park et al. | Nonlinear empirical model to simulate displacement-dependent structural behavior of a PWR fuel assembly |