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This chapter attempts to review the state of the art of methods of analysis and design of the concrete reactor pressure vessels and their components. Existing vessels have been examined for elastic, inelastic and cracking conditions.
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Waters T. C. and Barrett N. T. Prestressed concrete pressure vessels for nuclear reactors. Journal of British Nuclear Energy Society, 1963.
Frankline Institute Laboratories, State of art of prestressed concrete pressure vessels for nuclear power reactors—A critical review of literature, USEAC Report ORNL-TM-812, Oak Ridge National Laboratory, 1964.
Rashid Y. R. Analysis of axisymmetric composite structures by the finite element. Nuclear Engineering Design, Vol. 3, 1966, pp. 163–182. CrossRef
Rashid Y. R. Ultimate strength analysis of prestressed concrete pressure vessels. Nuclear Engineering Design Vol. 7, 1968, pp. 334–344. CrossRef
Good Paster D. W. et al. Design and analysis of multi-cavity prestressed concrete reactor vessels, Nuclear Enq. Des. Vol. 46, 1978, pp. 101–107. CrossRef
Orr R. S. and Holland D. A. Theoretical analysis of model spherical vessels, Conference on PCPV, London. Paper 33, 1967.
Bangash Y. et al. The influence of thermal creep on the operational behaviour of complex structures. International Conference Fundamental Creep & Shrinkage, Laussanne, Switzerland.
Morice P. B. Discussion on Group F papers on design and analysis of vessel structures, Conference on PCPV, London, 1967, pp. 397–434.
Zudans Z and Tans C. P. Feasibility study of prestressed concrete pressure vessel design, USAEC Report ORNLTM-813, Oak Ridge National Laboratory, 1967.
Papers on ultimate load tests, Conference on PCPV Model Techniques, British Nuclear Energy Society, Papers 3–14, 1968.
Sozen et al. Strength and behaviour of prestressed concrete vessels for nuclear reactors. Vols. 1, 2. University of Illinois USA, 1969.
ACI-BAM Concrete for nuclear reactors. Proceedings of mt. Seminar at Bundesantalt für Materialspriifungin, Berlin. ACI Special Publication SP-34. Vols. 1,11,111 Papers SP34-12/67168/69, 1970.
ACI-BAM concrete for nuclear reactors. Proceedings of mt. Seminar at Bundesanstalt für Marerialsprüfungin Berlin. ACI Special Publication SP-34, Vols. 1,11,111 Papers SP34-7/9/I0/70/39, 1970.
CEC and BAM Proceedings of the First International Conference on Structural Mechanics in Reactor Technology, 20–24, Berlin, Vol. 4, Reactor Pressure Vessels Part H Prestressed Concrete Pressure Vessels’. Papers H3/4–H5/8, 1971.
CEC and BAM Proceedings of the Second International Conference on Structural Mechanics in Reactor Technology, 844 M, 1973.
Marsh R. O. and Melese G. B. Prestressed concrete pressure vessels. Nucleonics Vol.23 No. 9, 1975, pp. 63–74.
Bender M. A status report on prestressed concrete reactor vessels, pressure vessel technology. Nuclear structural engineering. Vols. 1, 2, 1965, pp. 83–90, pp. 206–223. CrossRef
Jaeger T. A. Note on stress analysis of prestressed concrete reactor vessels. Nuclear structural engineering I, 1965 pp. 133–136.
Tottenham H. and Kanchi M. B. (1966) Structural characteristics of cylindrical pressure vessels of medium thickness. Nuclear Engineering Design Vol. 4, 1966, pp. 177–192. CrossRef
Kanchi M. B. Elastic theories of thick plates and shells, CE Dept. Report No. CEII-65, University of Southampton.
Private communication from UKAEA, 1967.
Common D. K. and Hannah I. W. Specifications of concrete vessels for gas-cooled reactors. Paper 7, Conference on PCPV, London, 1967.
Finigen A. Ultimate analysis of Dungeness B vessels. Conference on PCPV. Paper 31 Group F, 1967.
Zbirohowskj-Kuscja K. and Carlton D. Analysis of vessel structures with particular reference to Wylfa, Conference on PCPV, Inst. of Civil Engrs, London. Paper 30, 1967.
Brown A. H. The Oldbury vessels, Conference PCPV. Paper 1 Group A, March (1967). Paper I Group A, (1967). (b) Harris A. J. and Hay J. D. Rupture design of the Oldbury vessels, Conference PCPV. Paper No. 29, Group F, 1967.
Gomez A. E. et al. Lumped parameter analysis of cylindrical prestressed concrete reactor vessels. University of Illinois, Chicago Vols 1, 2, USA, 1968.
Koerner R. J. Over pressure analysis of prestressed concrete pressure vessels, Nuclear Engineering and Design, 1970.
CEC and Transactions of the Third International Conference on Structural Mechanics in Reactor Technology, 1–5, London, Vol. 3, Reactor VesselsPart H. Structural Analysis of Prestressed Concrete Reactor Pressure Vessels, 1975.
Richart F. E. et al. A study of the failure of concrete under combined compressive Stresses. Engineering Experiment Station Bulletin No. 185, University of Illinois, Chicago, 1928.
Glucklich J. On the compression failure of plain concrete T and AM Report No. 215, University of Illinois, Chicago 1962.
Balmer G. G. Shearing strength of concrete under high triaxial stress—computation of Mohr’s envelope as a curve. Struct. Research Lab. Report No. SP-23 USBR, 1949.
Westergaard H. M. On the resistance of ductile materials to combined stresses in two or three directions perpendicular to one another. Journal Franklin Institute 189, 1920, pp. 627–640. CrossRef
Nadai A. Theory of flow and fracture of solids. Vol. 1, McGraw-Hill Newyork, NY, 1950.
Merkle J. G. An engineering approach to multiaxial plasticity. ORNL-4138, 1967.
Sandbye P. A plastic theory for plain concrete. Bygnings-statiske meddelelser 36, 41–62, Teknisk Forlag. Copenhagen, 1965.
Newman K. and Newman J. B. Failure theories and design criteria for plain concrete. Structure, solids, solid mechanics, Wiley Interscience, London, 1971 pp. 963–995.
Wästlund G. Nyc ron angaende betongens grundläggende hallfasthetsegenskabar. Betong Haft 3, Stockholm, 1937.
Bresler B. and Pister K. S. Failure of plain concrete under combined stresses. Transactions ASCE, Vol. 122, 1957.
McHenry D. and Karni J. Strength of concrete under combined tensile and compressive stresses. J.ACI. 1958.
Schleicher F. per spannungszustand an der fliessgrenze (plasticitatsbedingung). Zietschrift für Angewandte mathematik und mechanik. Band 6 Heft 3. Berlin, 1926.
Vile G. W. D. The strength of concrete under short term static biaxial stress. The structure of concrete and its behaviour under load—Proceedings Int. Conference, London, 1968 pp. 275–288.
Smith G. M. Failure of concrete under combined tensile and compressive stresses. Journal of Allergy and Clinical Immunology, Vol. 50, No. 2, 1953, pp. 137–147.
Bresler B. and Pister K. S. Strength of concrete under combined stresses. Journal of Allergy and Clinical Immunology Vol. 55, No. 3, 1958, pp. 321–345.
Bellamy C. J. Strength of concrete under combined stresses. Journal of Allergy and Clinical Immunology 367–380.
Akroyd T. N. W. Concrete under triaxial stress. Magazine of concrete research Vol. 13, No. 39, 1961, pp. 11–118. CrossRef
Nishizawa N. Strength of concrete under combined tensile and compressive loads. Japan Cement Engineering Association Review, 1961 pp. 126–131.
Cambell Allen D. Strength of concrete under combined tensile and compressive loads. Constructional Review, Vol. 35, 1962, pp. 29–37.
Sigvaldason O. T. Failure characteristics of concrete, Ph.D Thesis, University of London, 1965.
Baker A. L. L. (a) An analysis of deformation and failure characteristics of concrete. Magazine of Concrete Research, Vol. 11 No. 33, 1959, pp. 119–128. (b) A criterion of concrete failure. Proc. Inst. Civ. Vol. 45, 1970, pp. 269–278. CrossRef
Anson M. An investigation into a hypothetical deformation and failure mechanism for concrete. Ph.D Thesis, University of London, 1962.
Hopkins and Pruger. The load carrying capacities of circular plates, Journal of Mechanics and Physics Society 2 (1) 1954.
Bangash Y. Prestressed concrete reactor vessel Timesaving ultimate load analysis. J. Inst Nucl. Engg: Vol. 13, No. 4, 1972.
Bangash Y. A basis for the design of bonded reinforcement in the prestressed concrete reactor vessels Paper 7478S. Supplement (viii). Inst. of Cu. Enqrs 1972.
Smee D. J. The Effect of aggregate size and concrete strength on the failure of concrete under multi-axial compression, Civil Engineering Transaction, Inst of Enqineer's Australia. Vol. CE9, No. 2, 1967 339–344.
Private communication from The Nuclear Power Group Company Risely, Lancashire, 1968, U.K.
Corum J. M. and Smith J. E. Use of small models in design and analysis of prestressed concrete reactor vessels ORNL-4346, IJ.S.A, 197
Smith J. R. Problems in assessing the correlation between the obseived and predicted behaviour of models Pipcr 10. Model Techniques for Prestrcsse(l Concrete Pressure Vessels, liNES, London, 1969.
Treharne and I)avics. Tests on samples and calculation of standard deviations for bonded reinforcement Private Reprt, 1969.
Paul et al. Mortar models of prestressed concrete reactor vessels, J. St. Dir. ASC’E, February 1969.
Brown G. Advances in the gas-cooled reactor. l.ecture joint session of lEE. 1. MECH. E and liNES, University of Strathclyde, Glasgow I 6 Available from British Nuclear Energy Society, 1968.
Buchert K. P. et al. (1978) Analysis of reinforced concrete containment vessels considering concrete cracking Nuclear Eng. Des. 46. 101–107. CrossRef
Argyris J. H. et al. Finite element analysis of inelastic structural behaviour. Nuclear Eng. Des Vols. 46, 23, 1978, pp. 5–262. MathSciNet
6th Conference on SMIRT, Paris, Vol J (a), J (b), 1981.
6th Conference on SMIRT, Paris, Vol. M, 1981.
5th Conference on SMIRT, Berlin, Papers HI to H30, 1979.
Bangash Y. The automated three-dimensional cracking analysis of prestressed concrete vessels, 6th Conference on SMIRT, Paris, Paper H3/2, 1981.
Kotulla B. et al. Three-dimensional analysis of stresses and crack development in prestressed thick-walled cylinders, 6th Conference on SMIRT, Paris, Paper H3/1, 1981.
Cheung K. C. An assessment of long-term structural behaviour of an asymmetric multi-cavity PCRV, 6th Conference on SMIRT, Paris, August 1981, Paper H3/9, 1981.
- Concrete Reactor Pressure Vessels
Prof. Dr. M.Y.H. Bangash
- Springer Berlin Heidelberg
- Chapter 5