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Lamella heat exchangers, Laminar flow: Laminar flow control, of boundary layers, Lancaster, J F, Langelier index for water quality, Large eddy simulation, in prediction of turbulent boundary layers, Laws for turbulent flows: Layers of fluid, free convection heat transfer in, Le Fevre equations for free convective heat transfer, Leakage between streams, in shell-and-tube heat exchangers Leakage effects, on heat transfer and pressure drop in shell-and-tube heat exchangers, Leaks, in heat exchanger, sealing by explosive welding, Lebedev, M E, Lee and Kesler equation, for vapour pressure, L-footed fins, Lessing rings, characteristic of, as packings for fixed beds, Li equation, for critical temperature of mixtures, Lienhard and Dhir analysis of critical heat flux in pool boiling, Lienhard and Eichhorn criterion, for transition in critical heat flux mechanism in crossflow over single tube, Lift force: Liley, P E, Limb, D, Limpet coils: Linnhoff, B, Liquefaction, exergy analysis of, Liquid fluidized beds, Liquid fuels, properties of, Liquid hold-up, Liquid-liquid-gas flow, Liquid-liquid flow, Liquid metals: Liquid sheets, in direct contact heat transfer, Liquid-solid interfaces, fouling at, Liquids: Lister, D H, Local conditions hypothesis, for critical heat flux in flow boiling, Lockhart and Martinelli correlations: Lodge's rubberlike liquid (non-Newtonian), Logarithmic law region, Logarithmic mean temperature difference Longitudinal flow and heat transfer in tube banks, Long-tube vertical evaporator, Loss coefficient, Lost work in unit operations/exergy analysis, Louvered fins, in plate fin exchangers, Low-alloy steels: Low-finned tubes: Low-nickel steels, Lubricants, physical properties: Lucas methods

Index

HEDH
A B C D E F G H I J K L
Lamella heat exchangers, Laminar flow: Laminar flow control, of boundary layers, Lancaster, J F, Langelier index for water quality, Large eddy simulation, in prediction of turbulent boundary layers, Laws for turbulent flows: Layers of fluid, free convection heat transfer in, Le Fevre equations for free convective heat transfer, Leakage between streams, in shell-and-tube heat exchangers Leakage effects, on heat transfer and pressure drop in shell-and-tube heat exchangers, Leaks, in heat exchanger, sealing by explosive welding, Lebedev, M E, Lee and Kesler equation, for vapour pressure, L-footed fins, Lessing rings, characteristic of, as packings for fixed beds, Li equation, for critical temperature of mixtures, Lienhard and Dhir analysis of critical heat flux in pool boiling, Lienhard and Eichhorn criterion, for transition in critical heat flux mechanism in crossflow over single tube, Lift force: Liley, P E, Limb, D, Limpet coils: Linnhoff, B, Liquefaction, exergy analysis of, Liquid fluidized beds, Liquid fuels, properties of, Liquid hold-up, Liquid-liquid-gas flow, Liquid-liquid flow, Liquid metals: Liquid sheets, in direct contact heat transfer, Liquid-solid interfaces, fouling at, Liquids: Lister, D H, Local conditions hypothesis, for critical heat flux in flow boiling, Lockhart and Martinelli correlations: Lodge's rubberlike liquid (non-Newtonian), Logarithmic law region, Logarithmic mean temperature difference Longitudinal flow and heat transfer in tube banks, Long-tube vertical evaporator, Loss coefficient, Lost work in unit operations/exergy analysis, Louvered fins, in plate fin exchangers, Low-alloy steels: Low-finned tubes: Low-nickel steels, Lubricants, physical properties: Lucas methods
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Fouling in Nuclear Industry

DOI 10.1615/hedhme.a.000365

3.17 FOULING IN HEAT EXCHANGERS
3.17.9 Fouling in nuclear industry

A. Introduction

A commercial nuclear power reactor essentially consists of heat-transfer systems for converting the energy of fissioning uranium to electricity via a conventional steam-turbine cycle. The predominant type of reactor is water-cooled, in which the fission heat generated in the fuel is removed by water and transferred to steam. Such use of water as coolant raises the possibility that the systems can become subject to several fouling phenomena. As described in this article, some of those phenomena are found only in nuclear systems because of their unique characteristics.

The reactors described here are of two types: indirect-cycle, comprising the pressurized water reactors (PWRs) and pressurized heavy water reactors (PHWRs - more specifically, those of the CANDU ® design), and direct-cycle, comprising the boiling water reactors (BWRs). The indirect-cycle reactors have a primary coolant system to transfer heat from the reactor core to heat exchangers or steam generators where the secondary coolant boils to produce steam for the turbines, while the direct-cycle reactors have the water coolant boiling directly to steam in the core itself. Besides the primary and steam circuits, other water systems such as the condenser cooling, the various ancillary heat exchangers around the reactor and, in the CANDU alone, the separate moderator system, can experience fouling. The inexorable processes of corrosion are very much responsible.

B. Primary Heat Transport System

(a) Pressurized Water Reactors

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