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Showing 1 to 20 of 47 for “"CANDU"”.
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CANDU pressure/calandria tube emergency water injection system
Thesis (Nucl.E.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering; and, (S.M.)--Massachusetts Institute of Technology, Dept. of Mechanical Engineering, February 1999.
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A Barkhausen Noise Testing System for CANDU Feeder Pipes
… evaluation (NDE) of residual stresses in CANDU reactor feeder pipes. The system consists of a four-channel arbitrary waveform flux control system (FCS), and the spring-loaded tetrapole prototype (SL4P) BN probe. The combination of the FCS and SL4P was shown to provide repeatable BN …
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Irradiation induced damage in CANDU spacer material Inconel X-750
… such as spacers in CANada Deuterium Uranium (CANDU) fuel channels. Prior to their application in commercial reactors, accelerated irradiation tests had been conducted in liquid metal fast reactors. Results did not indicate any problem stemming from significant fast neutron irradiation. …
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Localization of a robotic crawler for CANDU fuel channel inspection
… of a pipe crawling robot for the purpose of CANDU fuel channel inspection. The pipe crawling robot shall be capable of deploying the existing CIGAR (Channel Inspection and Gauging Apparatus for Reactors) sensor head. The main focus of this thesis is the design of the localization system for …
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Improved 3D modelling of CANDU reactors using transport-fitted diffusion coefficients
… the neutronic physics behavior of the core in CANDU pressure tube type heavy water reactors with natural-uranium fuel, two levels of calculations are required. Initially, lattice-level transport calculations are carried out to obtain, with high detail and accuracy, the flux distribution inside …
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Design and enhancements for a CANDU robotic fuel channel inspection system
… for use inside Canadian Deuterium Uranium (CANDU) reactor fuel channels. A dual cable management system was developed to hold the necessary cables for the robotic crawler to operate and provide additional odometry data. A deployment scheme for the robotic inspection system integrated into …
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Computational fluid dynamic investigations of flow through an aged CANDU pressure tube
… fluid dynamics simulations of twelve simplified CANDUTM 37M fuel bundles sitting in both as-received and aged pressure tubes were performed with Hydra in this work. The predicted coolant flow behaviour of two cases were compared in order to investigate the impact of pressure tube deformation (sag …
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Design and development of a robotic crawler for CANDU fuel channel inspection
… design of a new robotic crawler drive unit for CANDU fuel channel inspection, a complete design and screening process was done in order to fulfil the objective of this research. A brief explanation of CANDU reactors is provided along with a discussion of the inspection systems that are currently …
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Experimental characterization of the dynamic response of a mock-up CANDU fuel bundle
… discusses the vibration response of a mock-up CANDU 37M fuel bundle. The experiments are performed using non-invasive methods of vibration measurement by means of high-speed cameras and laser displacement sensors. The contact dynamics between the fuel bundle and the pressure tube are replicated …
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Communication protocols, queuing and scheduling delay analysis in CANDU SCWR hydrogen co-generation model
… Deuterium Uranium-Super Critical Water Reactor (CANDU-SCWR) hydrogen plant and a discrete-time controller, sensor and actuator block, that are connected via a communication network, such as e.g. controller area network (CAN), Ethernet or wireless networks. Issues associated with NCSs are …
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Moderator displacers for reducing coolant void reactivity in CANDU reactors: a neutronics scoping study.
When the coolant is voided in a CANDU lattice, the net reactivity change is positive, due primarily to the fact that the coolant and moderator are separated and the coolant volume is much smaller than the moderator volume. The modest loss in moderation occurring when coolant is lost does not offset …
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Transport-theory-equivalent diffusion coefficients for node-homogenized neutron diffusion problems in CANDU lattices
… Full-core neutronic calculations for CANDU reactors are therefore performed customarily using two-energy-group diffusion theory (no angular dependence) for a node-homogenized reactor model. The work presented here is concerned with reducing the loss in accuracy entailed when going from …
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Development and optimization of new generation start-up instrumentation systems (SUI) for domestic CANDU reactors
… standardized and used across all of the domestic CANDU stations is proposed. Finally, benefits of Hierarchical Control Chart (HCC) methodology for all stages of plant life management, such as system design, development, operation and maintenance are demonstrated. Keywords: Task Breakdown and …
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Generating and Simulating CANDU® Fuel Channel Eddy Current Data to Demonstrate Multi-Parameter Extraction Capabilities
… current probe known as the gap probe is used in CANDU® (CANadian Deuterium Uranium) nuclear reactors to verify that Pressure Tube to Calandria Tube (PT-CT) gap in Fuel Channels is larger than the minimum requirement. Contact between the two tubes can severely reduce the structural integrity of …
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A Computational Fluid Dynamics based model that predicts wall shear stress in CANDU outlet feeder pipes
Wall thinning of carbon steel in CANDU reactor outlet feeder pipes due to Flow Accelerated Corrosion (FAC) is identified as one of the challenges for CANDU reactors since it would force them to shut down due to safety reasons. Several models have been developed over time to predict the corrosion …
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Development of a 37-element fuel bundle for the production of molybdenum-99 in CANDU power reactors.
In this study, the potential use of CANDU power reactors for the production of Mo-99 is assessed. Five different modifications of a 37-element fuel bundle that could be used for the production of Mo-99 in existing CANDU type power reactors are explored. Since Mo-99 is generated by the fission of …
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Optimization of DUPIC cycle environmental and economic performance
… of the DUPIC (Direct Use of Spent PWR Fuel In CANDU) cycle was made to analyze cycle performance relative to that of PWR and CANDU fuel cycles in terms of uranium utilization and spent fuel production efficiency. The DUPIC cycle was found to be most efficient in terms of minimizing spent fuel …
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Neutronic characterization of a Molybdenum-99-producing CANDU fuel bundle and implications for reactivity-device worth and refuelling strategies
Operating CANDU reactors can potentially produce significant quantities of Molybdenum-99 due to their ability to be refuelled online, high thermal neutron flux and fuel-design flexibility. A Molybdenum-producing bundle (MPB) has previously been designed for that purpose and shown to be equivalent …
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