Sedlak M.,Midwest Generation EME LLC |
Chen K.,Siemens AG |
Klempner G.,AMEC NSS Ltd |
Mayor K.,Alstom |
And 2 more authors.
IEEE Power and Energy Society General Meeting | Year: 2013
This report is a progress report by the Generator Subcommittee of the Electrical Machinery Committee of the IEEE Power and Energy Society, Working Group No. 8 ('IEEE C50.13 Review & Compare'). The working group is comparing the 2005 revision of the IEEE C50.13 standard for large round rotor synchronous generators with recent revisions of comparable International Electrotechnical Commission (IEC) 60034 standards. In this paper the working group reports progress made since starting in 2007, summarizes completed results, and outlines plans for next steps. Included are highlights of an incrementally improved C50.13 that is to be submitted for balloting in 2013 and highlights of future improvements that will be pursued after 2013. Also included is a synopsis of suggestions provided to the IEC for harmonization of IEC 60034 with IEEE C50.13. Finally, the paper includes an overview of a 2012 PES panel session to discuss grid code impacts on electric machine design and performance. © 2013 IEEE.
Pun-Quach D.,AMEC NSS Ltd |
Sermer P.,AMEC NSS Ltd |
Hoppe F.M.,McMaster University |
Nainer O.,Bruce Power |
Phan B.,Ontario Power Generation
Nuclear Technology | Year: 2013
This paper presents a best estimate plus uncertainty (BEPU) methodology applied to dryout, or critical channel power (CCP), modeling based on a Monte Carlo approach. This method involves the identification of the sources of uncertainty and the development of error models for the characterization and separation of epistemic and aleatory uncertainties associated with the CCP pa rameter. Furthermore, the proposed method facilitates the use of actual operational data leading to improvements over traditional methods, such as sensitivity analysis, which assume parametric models that may not accurately capture the possible complex statistical structures in the system input and responses. best estimate plus uncertainty analysis, epistemic error and aleatory variation, confidence and tolerance intervals.
Li B.,AMEC NSS Ltd |
Neill D.,Bruce Power |
Vijay D.K.,AMEC NSS Ltd
American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP | Year: 2014
In one Ontario CANDU reactor unit, the horizontal feeders are interlinked with feeder spacer rods, which are installed to prevent the contact between adjacent feeders. In the normal operating conditions, spaces do not carry any loads. Therefore, the individual feeder model is used without spacers for the horizontal feeders. This reactor unit is under extensive fuel channel shifting in order to extend the life time. The axial shifting of channels is expected to put additional loads on spacers and may constrain feeder movement. In order to determine how the spacer affects the feeder stress and feeder movement due to the extensive fuel channel shifting, multifeeder models that include spacers are created for stress analysis. Multi-feeder modelling capability is not readily available in AUTOPIPE. A novel approach of inter connecting feeders with structural elements is developed for AUTOPIPE. A significant increase in feeder stress under the extensive fuel channel shift loading condition is found when the feeder spacers are included in the model. However, the feeder stresses for Design, Level A&B loading under fuel channel shift configuration meet the ASME B&PV Code NB-3600 stress limit requirements. The feeder spacer assessment results also show that the structural integrity of feeder spacers is not affected by the fuel channel shifting. In addition, this study confirmed that it is unnecessary to release the feeder spacers to prevent spacer break or feeder overstress during the post fuel channel sifting operation, thus saving significant outage time to achieve shifting configuration. Copyright © 2014 by ASME.
Mahmood S.L.,Babcock |
Adibi-Asl R.,AMEC NSS Ltd. |
Daley C.G.,Memorial University of Newfoundland
Journal of Pressure Vessel Technology, Transactions of the ASME | Year: 2013
Simplified limit analysis techniques have already been employed for limit load estimation on the basis of linear elastic finite element analysis (FEA) assuming elastic-perfectly-plastic material model. Due to strain hardening, a component or a structure can store supplementary strain energy and hence carries additional load. In this paper, an iterative elastic modulus adjustment scheme is developed in context of strain hardening material model utilizing the "strain energy density" theory. The proposed algorithm is then programmed into repeated elastic FEA and results from the numerical examples are compared with inelastic FEA results. Copyright © 2013 by ASME.
Parmar R.,AMEC NSS Ltd |
Ngo K.,AMEC NSS Ltd |
Cruchley I.,Bruce Power
Canadian Nuclear Society - 32nd Annual Conference of the Canadian Nuclear Society and 35th CNS/Can Student Conference 2011 | Year: 2011
In 2007, Bruce Power undertook a project, in partnership with AMEC NSS Limited, to develop a Generation Risk Assessment (GRA) model for its Bruce B Nuclear Generating Station. The model is intended to be used as a decision-making tool in support of plant operations. Bruce Power has recognized the strategic importance of GRA in the plant decision-making process and is currently implementing a pilot GRA application. The objective of this paper is to present the scope of the GRA model development project, methodology employed, and the results and path forward for the model implementation at Bruce Power. The required work was split into three phases. Phase 1 involved development of GRA models for the twelve systems most important to electricity production. Ten systems were added to the model during each of the next two phases. The GRA model development process consists of developing system Failure Modes and Effects Analyses (FMEA) to identify the components critical to the plant reliability and determine their impact on electricity production. The FMEAs were then used to develop the logic for system fault tree (FT) GRA models. The models were solved and post-processed to provide model outputs to the plant staff in a user-friendly format. The outputs consisted of the ranking of components based on their production impact expressed in terms of lost megawatt hours (LMWH). Another key model output was the estimation of the predicted Forced Loss Rate (FLR).
Mostafa H.E.,McMaster University |
El-Dakhakhni W.W.,McMaster University |
Mekky W.F.,AMEC NSS Ltd
Journal of Reinforced Plastics and Composites | Year: 2010
This article presents the development of a cost-effective lightweight protection technique for explosives transporting container and storage facilities employing surface-mounted Rigid Polyurethane Foam (RPF) plates. Different RPF specimens were prepared with different densities and sand particle reinforcement ratios ranging between 0% (unreinforced) and 30%. Mechanical properties characterization was conducted to optimize an RPF formulation to be tested under blast loading using different experimental techniques. Explosive scaling laws were utilized to relate indoor blast test results (performed with small explosive charges) to real-life blast scenarios. Small RDX explosive charges were placed and detonated inside RPF specimens to correlate the size of the resulting cavity to the explosive charge weight and the RPF density. Another set of experiments were conducted to evaluate the maximum deformation depth of lead witness plates resulting from blast waves. In these latter experiments, explosive charges were mounted on the free surface of RPF plates. In general, test results demonstrated the capability of reinforced RPF as a light weight cost-effective technique to mitigate blast load hazard. © 2010 The Author(s).
Mostafa H.E.,Military Technical College |
Mekky W.F.,AMEC NSS Ltd. |
El-Dakhakhni W.W.,McMaster University
Journal of Materials in Civil Engineering | Year: 2014
The unintentional initiation of munitions during production, storage, transportation, and handling is among the main sources of explosive hazard. Such unintentional initiation of explosives is termed sympathetic detonation, in which the detonation of a single explosive unit (or warhead) triggers the detonation of another, and subsequently starts a chain reaction. Because of this, the demand for resilient lightweight ammunition-separation systems within shipping or storage containers is increasing. This paper presents the development and testing of a cost-effective lightweight rigid polyurethane foam (RPF) separation system. The scaled gap test approach discussed is used as a practical tool to investigate the initiability of acceptor explosive charges by a blast wave generated from donor charges through the RPF as a blast wave attenuation medium. Different RPF specimens were prepared with different densities and silt particle mix ratios ranging from 0% (no silt) to 30%. The study results demonstrate the capability of the RPF as a lightweight cost-effective technique to attenuate the blast wave effects on acceptor explosives to safe levels. © 2014 American Society of Civil Engineers.
Venkatraman K.,University of Saskatchewan |
Dalai A.K.,University of Saskatchewan |
Humphries R.,AMEC NSS Ltd
International Conference on Nuclear Engineering, Proceedings, ICONE | Year: 2015
The Province of Saskatchewan and Hitachi Canada have established a collaborative relationship to research design options and conduct feasibility analyses of Small Modular Reactor (SMR) technology with the goal of safely and reliably generating clean energy and helping to achieve a low-carbon society. The focus of this study is to optimize the design of an SMR Balance of Plant (BOP) for the supply of steam and heat to various residential, industrial and commercial applications. The study includes a review to examine if waste heat available from the proposed SMR could be used for producing potable water using nuclear desalination technology. It is in the context that large volumes of groundwater and brackish water are available in Saskatchewan, Canada. The existing literature on desalination processes are being reviewed, including technologies for water production such as Multiple Effect Distillation (MED), Multi Stage Flash (MSF), and Reverse Osmosis (RO). The review includes comparison of various technologies for energy efficiency and overall economics of the process. The Desalination Economic Evaluation program (DEEP) computer model available from International atomic energy agency (IAEA) is also used as a tool for examination. Factors such as salinity of the feedwater, advantages gained by pre-heating the feedwater and efficient utilization of waste heat generated in the SMR showed that technology based on RO will be the most cost effective technology. The conclusions are also supported in previous reviews done by GE and AMEC for the government of Alberta, Canada. The quality of product water produced using RO technology depends on impurities in the feed water. Therefore, trials in a pilot plant and in a semi commercial plant are proposed as next steps. Copyright © 2015 by JSME.
Abdelsalam U.,AMEC NSS Ltd |
Vijay D.,AMEC NSS Ltd
American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP | Year: 2010
This paper addresses the application of the design by analysis rules of the ASME B&PV Code SEC III Division 1 NB-3200 criteria on degraded Class 1 piping. A tight radius pipe bend with a local thin area (LTA) located on the inner surface and super imposed on general thinning region is considered using a detailed FEA model implementing idealized smooth axial and circumferential thickness profiles. A location dependent thinning rate function is developed (based on the smoothed profiles and the assumed original thickness distribution) to predict the wall thickness distribution at the end of an arbitrary evaluation period. Internal pressure and dead weight loads are statically applied. Linear elastic analysis is performed and the results are checked against the ASME Code criteria for the primary stress intensity. It is demonstrated that a "local" wall thickness considerably below the pressure based thickness for the corresponding straight pipe segment meets the requirements of the ASME Code SEC III for the primary stresses. The effect of the extent of the local thin area in the axial direction is explored. This paper also compares the allowable pressure obtained from elastic analysis of NB-3221 and limit analysis of NB-3228.1. Copyright © 2010 by ASME.
Abdelsalam U.,AMEC NSS Ltd.
American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP | Year: 2010
This paper addresses the primary stress requirements for the pressure loading of tight radius pipe bends according to the ASME Code SEC III NB-3200 (Design by Analysis). Solid FEA models are constructed to represent a tight radius pipe bend with general and local internal wall thinning. The wall thickness variation is considered using uniform and non-uniform axial and circumferential profiles. It is demonstrated that for a tight radius bend with wall thickness equal to the pressure based thickness of the corresponding straight pipe, the linear elastic criteria of NB-3221 are significantly exceeded. Results are presented to show the minimum acceptable wall thickness using uniform thickness distributions. The allowable wall thickness criterion of the ASME Code SEC XI Code Case N-597-2 is examined using a finite element model implementing the recommended thickness distribution along the circumferential direction. It is demonstrated that this distribution achieves a uniform stress intensity over the entire bend (uniform strength). A local thin area (LTA) centered at the intrados of the bend is superimposed on a general thinned area and the axial and circumferential extents are varied. FEA results are presented to demonstrate Code compliance and its dependency on the axial and circumferential extents of the LTA and the thickness of the surrounding material. Copyright © 2010 by ASME.