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1-3 of 3
Greg D. Morandin
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Proceedings Papers
Proc. ASME. PVP2002, Transportation, Storage, and Disposal of Radioactive Materials, 17-26, August 5–9, 2002
Paper No: PVP2002-1609
Abstract
Ontario Power Generation (OPG) is transferring irradiated fuel from its CANDU nuclear generating stations in Ontario Canada, that has been cooled for a minimum of 10 years in the Irradiated Fuel Bay (IFB), into Dry Storage Containers (DSC). The Picketing Used Fuel Dry Storage Facility has been in operation for 6 years and over 200 DSC’s have been loaded to date. During the loading operation a DSC is lifted out of the IFB and craned over a wall into a decontamination pit (DP). This operation requires that the lid of the DSC be in place before the container is removed from the IFB. A lid clamp is used, which sits around the perimeter of the lid and maintains the boundary between the mating lid and container flange plates, to ensure that the lid is retained under normal and abnormal conditions. In the event of a crane failure, there is a potential for the DSC to impact the intermediate wall between the IFB and the DP. This may result in the DSC toppling over the wall and either falling into the DP or toppling back into the IFB. Both the IFB and the DP have floor impact pads to prevent structural damage. The lid clamp must demonstrate the ability to maintain the containment boundary under these postulated accident scenarios. A finite element model of the Dry Storage Container and the proposed lid clamp has been developed to assess the structural integrity of the lid clamp design. The postulated accident scenarios consider are a 9.9 meter drop in a centre of gravity over top edge orientation, in a top down flat end orientation and a near side drop orientation onto an impact pad representative of the IFB pad. Only the centre of gravity and near side orientations are presented in this paper. The simulations were carried out on a DEC ALPHA workstation using an in-house three dimensional non-linear multi-purpose finite element code entitled H3DMAP version 6.
Proceedings Papers
Proc. ASME. PVP2003, Flow-Induced Vibration, 117-125, July 20–24, 2003
Paper No: PVP2003-2081
Abstract
Successful life management of steam generators requires an ongoing operational assessment plan to monitor and address all potential degradation mechanisms. A degradation mechanism of concern is tube fretting as a result of flow-induced vibration. Flow induced vibration predictive methods routinely used for design purposes are based on deterministic nonlinear structural analysis techniques. In previous work, the authors have proposed the application of probabilistic techniques to better understand and assess the risk associated with operating power generating stations that have aging re-circulating steam generators. Probabilistic methods are better suited to address the variability of the parameters in operating steam generators, e.g., flow regime, support clearances, manufacturing tolerances, tube to support interactions, and material properties. In this work, an application of a Monte Carlo simulation to predict the propensity for fretting wear in an operating re-circulation steam generator is described. Tube wear damage is evaluated under steady-state conditions using two wear damage correlation models based on the tube-to-support impact force time histories and work rates obtained from nonlinear flow induced vibration analyses. Review of the tube motion in the supports and the impact/sliding criterion shows that significant tube damage at the U-bend supports is a result of impact wear. The results of this work provide the upper bound predictions of wear damage in the steam generators. The EPRI wear correlations for sliding wear and impact wear indicate good agreement with the observed damage and, given the preponderance of wear sites subject to impact, should form the basis of future predictions.
Proceedings Papers
Proc. ASME. PVP2004, Computer Technology and Applications, 39-45, July 25–29, 2004
Paper No: PVP2004-2744
Abstract
The response of buildings to a pressure pulse from a shock wave is becoming more critical to design assessments. The severe loading transients resulting from such events, provides unique challenges to analytical modelling and simulation of building survivability. In this paper, a nonlinear explicit three dimensional blast simulation of a building is undertaken with critical contents located in the most susceptible locations in order to provide an assessment of potential damage and the impact on the contents of interest. In the work described in this paper, the source and orientation of the blast relative to the building are outlined. Using developed blast procedures, the amplitude and impulse of the blast shock wave due to specified blast parameters are determined for the front, sides, roof and rear of the building. These are applied to finite element models of the building. A state-of-the-art, large deformation, non-linear finite element code that is well suited to this class of problem, is used in the blast simulations. The results indicate that the building is severely damaged, however, the internal building area, in the vicinity of the critical contents, is intact and the main roof trusses remain attached.