Abstract
This lecture describes the principal types of unfired modern steam raiser, concentrating on land-based units in service in the power and process chemical industries; the methods used for the thermal design of the various types; and the common problems encountered during the operation of steam raising equipment.
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References
Collier, J.G., The Design of Boilers, in Heat Exchangers: Thermal Hydraulic Fundamentals and design, ed. Kakac, S., Bergles, A.E., and Mayinger, F., pp 619–646, Hemisphere Publishing Corporation, 1981.
The Shippingport Pressurised Water Reactor. Addison Wesley Publishing Company, (1958).
Styrikovich, M., The role of two-phase flows in nuclear power plants, Int. Seminar Momentum. Heat and Mass Transfer in Two-Phase Energy and Chemical Systems. Dubrovnik, Yugoslavia, 4–9 Sept. ICHMT, 1978.
Davis, R.J., and Hirst, B., Twin header bore welded steam generator for pressurized water reactors, Nucl. Energy, Vol. 18, pp. 133–140, April No. 2, 1979.
Garnsey, R., Corrosion of PWR steam generators, Nucl. Energy. Vol. 18., pp. 117–132, April No. 2, 1979.
Robertson, J.M., Dryout in horizontal hair-pin waste heat boiler tubes, A.I.Ch.E. Symp. Series 69, (131), 55, 1973.
Hinchley, P., The engineering of reliability into waste heat boiler systems, Proc. Inst. Mech. Engrs.. Vol. 193, No. 8, 1977.
Hinchley, P., Waste heat boilers: problems and solutions, Chem. Eng. Prog.. 73, 90, and Chem. Ing. Tech. 49, 553, 1977.
Webster, R. A., Three-dimensional thermal-hydraulic analysis of the PFR steam generator, 1st U.K. Nat. Heat Transfer Conference, pp 241–258, Leeds, 1984.
Sha, W.T., A new approach for rod bundle thermal hydraulic analysis, Proc Int’l Meeting on Nuclear Power Reactor Safety. Brussels, Oct 16–19, 1978.
Scruton, B., Gibb, J., and Chojnowski, B., Conventional power station boilers: Assessment of limiting thermal conditions for furnace wall tubes, CEGB Research, pp. 3–11, April 1985.
Scruton, B., and Chojnowski, B., The Assessment of Critical Heat Flux Margins for furnace wall tubes, Forshung in der Kraftwerkstechnik, pp 160–165, 1980.
Humphries, P., Derretí, G.F., and Scruton, B., Critical Heat Flux Characteristics for Vertical Steam Generating Tubes with Circumferentially non-uniform heating, 1st U.K. Nat. Heat Transfer Conference, pp 817–828, Leeds, 1984.
Styrikovich, M.A., and Miropolskii, Z.L., Dokl Akad. Nauk., SSSR, 71 (2), 1950.
Gardner, G.C., and Kubie, J., Flow of two liquids in sloping tubes: and analogue of high pressure steam and water, Int. J. Multiphase Flow. 2, 435–451, 1976.
Bailey, N.A., Dryout in the bend of a vertical U-tube evaporator, Personal Communication, 1977.
Schuller, R.B., and Cornwell, K., Dryout on the shell side of tube bundles. 1st U.K. Nat. Heat Transfer Conference, pp. 795–804, Leeds, 1984.
Leong, L.S., and Cornwell, K., Heat transfer coefficients in a reboiler tube bundle, The Chemical Engineer. No 343, pp 219–221, 1979.
Collier, J.G., Convective Boiling and Condensation. 2nd ed., McGraw Hill Book Co, 1981
Baroczy, C.J, A systematic correlation of two-phase pressure drop, Chem. Engng. Prog. Symp., Series 62, (64), pp.323. 1966.
Chisholm, D, Pressure gradients due to friction during flow of evaporating two-phase mixtures in smooth tubes and channels, Int. J. Heat Mass Transfer. 16, 347–358, 1973
Lombardi, C, and Peddrochi, E, A pressure drop correlation in two-phase flow, Energia Nucleare. 19 (2), 1972.
Martinelli, R.C., and Nelson, D.B, Prediction of pressure drop during forced circulation boiling of water, Trans. ASME 70. p.695, 1948.
Macbeth, R.V, Private Communication quoted in paper by Brittain, I, and Fayers, F.J, A review of UK developments in thermal-hydraulic methods for loss of coolant accidents, Paper presented at CSNI Meeting on Transient Two-Phase Flow. Toronto, 1976.
ESDU, The frictional component of pressure gradient for two-phase gas or vapour/liquid flow through straight pipes. Engineering Sciences Data Unit (ESDU), London, 1976.
Friedel, L, Mean void fraction and friction pressure drop: Comparison of some correlations with experimental data, European Two-Phase Flow Group Meeting. Grenoble, Paper A7, 1977.
Idsinga, W, An assessment of two-phase pressure drop correlations for steam-water systems. M.Sc. Thesis, MIT, 1975.
Ward, J.A., Private Communication, (HTFS), 1975.
Lockhart, R.W, and Martinelli, R.C, Proposed correlation of data for isothermal two-phase, two component flow in pipes, Chemical Engineering Process. 58 (4), 62–65, 1949.
Hughmark, G.A., Hold-up in gas-liquid flow, Chemical Engineering Process, 58 (4), 62–65, 1962.
Smith, S.L., Void fractions in two-phase flow. A correlation based on an equal velocity head model, Proc. Inst. Mech. Engrs. 184, Pt. 1, (36), 647–664, 1969.
Premoli, A., Di Francesco, D., and Prima, A, An empirical correlation for evaluating two-phase mixture density under adiabatic conditions, European Two-Phase Flow Group Meeting. Paper B9, Milan, 1970.
Chisholm, D., Research note: void fraction during two-phase flow, J. Mech. Engng. Sci., 15 (3), 235–236, 1973.
Thorn, J.R.S., Prediction of pressure drop during forced circulation boiling of water, Int. J. Heat Mass Transfer. 7,709–724, 1964.
Jones, A.B., Hydrodynamic stability of a boiling channel, KAPL-2170, 1961.
Bryce, W.M., A new flow-dependent slip correlation which gives hyperbolic steam-water mixture flow equations. AEEW-R1099, 1977.
ESDU, The gravitational component of pressure gradient for two-phase gas or vapour/liquid flow through straight pipes. Engineering Sciences Data Unit (ESDU), London, 1977.
Collier, J.G., Boiling outside tubes and tube bundles, Section 2.7.5., Heat Exchanger Design Handbook. Hemisphere Publishing Corp., 1983.
Palen, J.W., and Small, W.M., A new way to design kettle and internal reboilers, Hydrocarbon Processing, vol. 43, no. 11, pp 199–208, 1964.
Smith, R.A., Vaporisers — Selection. Design and Operation. Longmans/J. Wiley, 1986.
Freidel, L., Improved friction pressure drop correlations for horizontal and vertical two-phase flow, European Two-phase Flow Group meeting. Ispra, Italy, 1979.
Smith, R.A., private communication, 1987.
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© 1988 Kluwer Academic Publishers
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Collier, J.G. (1988). Nuclear Steam Generators and Waste Heat Boilers. In: Kakaç, S., Bergles, A.E., Fernandes, E.O. (eds) Two-Phase Flow Heat Exchangers. NATO ASI Series, vol 143. Springer, Dordrecht. https://doi.org/10.1007/978-94-009-2790-2_22
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DOI: https://doi.org/10.1007/978-94-009-2790-2_22
Publisher Name: Springer, Dordrecht
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