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Showing 1 to 12 of 12 for “"Fuel Bundle"”.
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Experimental characterization of the dynamic response of a mock-up CANDU fuel bundle
… 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 using a …
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Development of a 37-element fuel bundle for the production of molybdenum-99 in CANDU power reactors.
… 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 U-235 with a fission yield of 6.1%, the proposed designs use enriched uranium in the Mo-99 …
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Neutronic characterization of a Molybdenum-99-producing CANDU fuel bundle and implications for reactivity-device worth and refuelling strategies
… 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 to the standard CANDU bundle (SCB) under normal, steady-state, …
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Numerical Investigations of the Fluid Flow and Heat Transfer and Construction of Control System for the Canadian Supercritical Water-Cooled Reactor Power Plant
… the supercritical water in the nuclear reactor fuel bundle, and the construction of the linear dynamic model and the design of the control system for the Canadian SCWR power plant. Firstly, the fluid flow and heat transfer of the supercritical water in the vertical tube and the rod bundle is …
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Critical power characteristics of axially heterogeneous tight bundle designs
… prediction of the dryout critical power in fuel rod bundles is challenging and has important implications for the economy and safety of Boiling Water Reactors (BWRs). This is especially true for the tight bundle design of the Resource-Renewable BWR (RBWR) proposed by Hitachi, Ltd. Unlike a …
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Design of annular fuel for high power density BWRs
… BWR plants by switching from the current solid fuel to annular fuel cooled both on its inside and outside surfaces. The GE 8x8 bundle dimensions and fuel to moderator ratio are preserved as a reference to enable applications in existing reactors. A methodology is developed and VIPRE code …
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Thermal aspects of high efficiency channel with conventional and alternative fuels in SuperCritical water-cooled reactor (SCWR) applications
… of 350°C and 625°C. Consequently, the sheath and fuel centerline temperatures are higher in SCWRs than those of the current nuclear reactors. Previous studies have shown that the sheath and fuel centerline temperatures could exceed the design and industry accepted limits of 850°C and 1850°C, …
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Stability analysis of natural circulation in BWRs at high pressure conditions
… Design features of the ESBWR, including shorter fuel bundle and use of part-length rods in the assemblies, tend to improve the thermal-hydraulic stability performance. However, the thermal-hydraulic stability margin is still lower than that of a typical BWR at rated conditions. In …
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Investigation of pressure-tube and calandria-tube deformation following a single channel blockage event in ACR-700
… resulting in rapid coolant boil-off and fuel overheating. Melting of the Zircaloy (Zry) components of the fuel bundle (cladding, end plates and end caps) can occur, with relocation of some molten material to the bottom of the PT. The hot spot caused by the molten Zry/PT interaction may …
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Crash Analysis of Degraded Concrete Containment Structures
… that houses the basket of the spent nuclear fuel bundle. The concrete of dry cask structures will degrade due to the natural aging and the environmental effect shrinkage, creep, heat transfer, moisture diffusion, and Alkali-Silica Reaction (ASR). Long-term creep and shrinkage of vertical dry …
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An evaluation of the net breeding capability of heterogeneously-fuelled pressure-tube heavy water reactors with the thorium fuel cycle
The thorium fuel cycle is a promising future option for an alternative to uranium. The pressure tube heavy water reactor (PT-HWR) has for decades been considered capable of achieving net breeding on the thorium fuel cycle, but this capability has not been conclusively demonstrated. The goal of this …
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Specifics of forced-convection heat transfer in a vertical 7-element bundle cooled with upward flow of SuperCritical Water
… Transfer specifics for SuperCritical Water in bundle configurations is required. Many empirical Nusselt number (Nu) correlations derived from bare tubes are available, with only one derived from a bundle. No assessments of Nu correlations are available for 7-rod bundle datasets, representing …