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A number of nuclear power stations exist worldwide. This chapter concentrates on British, American, Canadian and European research and commercial reactors and nuclear power stations. The directory exists on the past, present and future planning for the NPS and are continuously being updated. In this chapter carefully selected nuclear stations with various design parameters have been clearly dealt with.
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Hojgaard, E., Kallero, K. E., and Nilsson, L. B. New Type of Reactor Containment of Prestressed Concrete. Report ANS Winter Meeting, 1968.
Gimstedt, Haga, I., Wassberg, R., and Nilsson, L. B. Articles on Oskarshamn 1 Nuclear Power Station. Nuclear Engineering International. 1970.
Lindbo, T. and Boye-moller, K. Design and construction of concrete containment for BWR. J 2/6, Second SMiRT Conference, Berlin, 1973.
Margen, P. H. and Menon, S. Preparation for exploitation of prestressed concrete reactor vessels for light water reactors. NUCLEX 72, Basel, 1972.
HAY, J. D. and EADIE, D. McD. The prestressed concrete pressure vessels for Hinkley Point ‘B’ and Hunterston ‘B’. Paper No. SM.ll 1/31. Symposium on Advanced and High Temperature Gas-cooled Reactors. Jülich, Germany, October, 1968.
Burrow, R. E. D. and WILLIAMS, A. J. Hartlepool advanced gas-cooled reactor—reactor pressure vessel. Nuclear Engineering International. Vol. 14, No. 162, 1969.
Menon, S., Rasmussen, I., Tarandi, T., and Kraemer, W. Scandinavian PCRV development: present status and planned Work, 1973–75. H 3/9, Second SMiRT Conference, Berlin, 1973.
Burrow, R. E. D. and Brunton, J. D. Developments in large prestressing systems for nuclear pressure vessels. FIP Sixth International Congress. Prague, 1970.
Mckean, J. D., Tyrell, J., Lawson D. S., and Burrow, R. E. D. Heysham nuclear power station. Nuclear Engineering International Vol. 16, No. 186, 1971.
BS.4975. Specification for prestressed concrete pressure vessels for nuclear reactors. British Standard Institution, 1973.
TAN, C. A Study of the Design and Construction Practices of Prestressed and Reinforced Concrete Containment Vessels. The Franklin Institute Research Laboratories, Philadelphia, 1969, p. 506.
Kulka, F. and Wahl, H. W. American practices in the design of prestressed concrete containment structures. PCI Journal, 1968.
Schupack, M. Large post-tensioning tendons. PCI Journal, 1972.
Wahl, H. W. and Kosiba, R. J. Design and construction aspects of large prestressed concrete (PWR) containment structures. ACI Journal, 1969.
Lorenz, H. Design of the concrete containment vessel for the R. E. Ginna nuclear power plant. Nuclear Engineering and Design Vol. 6, 1967, pp. 360–366.
Preliminary Safety Analysis Report. Bellefonte Nuclear Plant, Docket No. 50438 and No. 50-439, Tennessee Valley Authority. Private Communications TVR 1990.
ACI-ASME Technical Committee on Concrete Pressure Components for Nuclear Service. Proposed standard code for concrete reactor vessels and containments, copyright 1973.
United Engineers and Constructors, Seabrook Station Containment Aircraft Impact Analysis, Prepared for Public Service Co. of New Hampshire, Seabrook, New Hampshire, Revision 1, January, 1975.
NRC Standard Review Plan Section 3.6.1, Plant Design for Protecting Against Postulated Piping Failures in Fluid Systems Outside Containment U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, 1975.
NRC Standard Review Plan Section 3.6.2. Determination of break locations and dynamic effects associated with postulated rupture of piping, U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulations, 1975.
ANS 58.2 Committee. Design basis for protection of nuclear power plants against effects of postulated rupture, ANS-N 176, 1977 (Draft).
CEGB Private Communications on British Nuclear Power Stations, 1979.
UKAEA Private Communications on British Nuclear Power Stations: Winfirth, 1984.
TNPG Group. Design of nuclear power stations belonging to TNPG consortium inclusive of Mccalpine Engineering 1979.
NRC list of regulatory guides related to nuclear power stations listed below and other guides:
The following NRC Regulatory guides apply in particular to containment structural design and construction:
Regulatory Guide 1.10—Mechanical (Cadweld) Splices in Reinforcing Bars of Category I Concrete Structures.
Regulatory Guide 1.15—Testing of Reinforcing Bars for Category I Concrete Structures.
Regulatory Guide 1.18—Structural Acceptance Test for Concrete Primary Reactor Containments.
Regulatory Guide 1.19—Non-destructive Examination of Primary Containment Liner Welds.
Regulatory Guide 1.29—Seismic Design Classification.
Regulatory Guide 1.35—In-service Inspection of Ungrouted Tendons in Prestressed Concrete Containment Structures.
Regulatory Guide 1 .46—Protection Against Pipe Whip Inside Containment.
Regulatory Guide 1.54—Quality Assurance Requirements for Protective Coatings Applied to Water-Cooled Nuclear Power Plants.
Regulatory Guide 1.55—Concrete Placement in Category I Structures.
Regulatory Guide 1.57—Design Limits and Loading Combinations for Metal
Primary Reactor Containment System Components.
Regulatory Guide 1.59—Design Basis Floods for Nuclear Power Plants.
Regulatory Guide 1.60—Design Response Spectra for Seismic Design of Nuclear Power Plants.
Regulatory Guide 1.61—Damping Values for Seismic Design of Nuclear Power Plants.
Regulatory Guide 1 .76—Design Basis Tornado for Nuclear Power Plants.
KWU. German nuclear power stations. Private Communications, 1982.
EDF. French nuclear power stations. Private Communications, 1983.
Asea. Atom. Private Communications (1981–1984) Stockholm, Sweden, 1981–1984.
AECL Pressurised Heavy Water Reactors: Candu stations, 1979–1984.
Japan (JNC) Private Communications Otawa, Tokyo. Private Communications on FBR stations, 1979–1985.
Swedish CNPW & CDL. Swedish Commercial Nuclear Power BWR Plants and Ancillaries. Private communications, Sweden. Stockholm, 1983–1987.
BNES. Fast Breeder Reactor Core and Fuel Structural Behaviour British Nuclear Energy Society, London. Conference held in Inverness 4.6 June 1990 Scotland.
BNES. Fast Reactor Power Stations. Proceeding of International conference, 1974, ICE Building, London, 1974.
Munce. J. F. The Architecture in the Nuclear Age. I Life Books Ltd, 1964.
I mechE Proceedings of the Symposium on Berkeley and Bradwell Nuclear Power Stations. The Institution of Mechanical Engineers, London, 1963.
APC SGHWR Atomic Power Constructions Ltd, Surrey, England, 1966.
BNES Steam Generating and Other Heavy Water Reactors. British Nuclear Society. Proceedings London, 1968.
CEGB Proof of Evidence on the Design of Sizewell-B PWR, 1982.
SMIRT Proceedings: (SMiRT 1–13 Vol. 8–10) Each Proceedings Structural Mechanics in Reactor Technology Proceedings No. 1–13. Nuclear Engineering & Design Journals, 1970–2001.
IJNE International Journals of Nuclear Engineering. 1969–2007, London, UK
JNE & D International Journal of Nuclear Engineering And Design. Elsevier, Holland, 1979–2008.
- Nuclear Power Plant Facilities and Regulatory Guides
Prof. Dr. M.Y.H. Bangash
- Springer Berlin Heidelberg
- Chapter 1