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Erschienen in:
Nuclear Power Plant Facilities and Regulatory Guides Kapitel lesen Erstes Kapitel lesen

2011 | OriginalPaper | Buchkapitel

2. Loads and Material Properties for Nuclear Facilities – A General Survey

verfasst von : Prof. Dr. M.Y.H. Bangash

Erschienen in: Structures for Nuclear Facilities

Verlag: Springer Berlin Heidelberg

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Abstract

The probable failure assessment of structures for nuclear power facilities has bearings on the choice and postulation of the loads and load combinations, since the exact magnitude of the loads encountered in nuclear power plant design cannot be easily predicted. The loads are normally treated as random variables. These loads are generally defined in terms of probability of strength in different components/elements of structures for a nuclear facility.

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Vorheriges Kapitel Nuclear Power Plant Facilities and Regulatory Guides
Nächstes Kapitel Dynamic Finite Element Analysis
Literatur
1.
ANSI A58.l-l972. Building Code Requirements for Minimum Design Loads in Buildings and Other Structures. American National Standards Institute, 1972.
2.
Shah, H. C. et al. A Study of Seiimic Risk for Nicaragua, Part 1, The J. A. Blume Earthquake Engineering Center, Report No. 11, Dept. of Civil Engineering, Stanford University, 1975.
3.
Wiggins, J. H. Procedure of Determining Acceptable Risk Ground Motion Design Criteria. Technical. Report No. 75–1229, J. H. Wiggins Company, Redondo Beach, CA, 1975.
4.
Der Kureghian, A. and Ang, A. H-S. A Line Source Model for Seismic Risk Analysis, Structural Research Series No. 419, University. of Illinois at Urbana-Champaign, Urbana, II, October 1975.
5.
Specification for the Design, Fabrication and Erection of Structural Steel for Buildings. American Institute of Steel Construction, 1969.
6.
Uniform Building Code, 1976 edn, Vol. 1, International Conference of Building Officials, 1976.
7.
ACI Standard Building Code Requirements for Reinforced Concrete (ACI-3 18-71). American Concrete Institute, 1970.
8.
ASME Boiler and Pressure Vessel Code Section III, Division I. Rules for Construction of Nuclear Power Plant Components. American Society of Mechanical Engineers, 1974.
9.
ACI-ASME Joint Technical Committee. Code for Concrete Reactor Vessels and Containments. ASME Boiler and Pressure Vessel Code Section III, Division 2 and AC I Standard 359-74, 1975.
10.
ACI Standard Code Requirements for Nuclear Safety Related Concrete Structures (ACl-34977). American Concrete Institute, 1975.
11.
Specification for Steel Railway Bridges, Cooper E-72 Loading. American Railway Engineering Association, 1972.
12.
Standard Specification for Highway Bridges, H-20-S16 Loading. American Association of State Highway Officials.
13.
Federal Regulation 10 CFR Part 100, Reactor Site Criteria, Appendix A. Seismic and Geological Siting Criteria for Nuclear Power Plants. November 1973.
14.
Tong, W. H. Seismic Risk Analysis for Two-Sites Case. Publication No. R75-22, Department of Civil Engineering, M.I.T., May 1975.
15.
ANSI A58.l-1972, Building Code Requirements for Minimum Design Loads in Buildings and Other Structures, American National Standards Institute.
16.
Newmark, N. M. Overview of Seismic Design Margins. Paper presented at A.I.F. Workshop on Reactor Licensing and Safety, December. 1974.
17.
Hsieh, T., Okrent, D., and Apostolakis, O. E. On the Average Probability Distribution of Peak Ground Acceleration in the U.S. Continent Due to Strong Earthquakes. UCLA-ENG-75 16, University of California at Los Angeles, March 1976.
18.
Anderson, D. L., Chariwood, R. G., and Chapman, C. B. On seismic risk analysis of nuclear plants safety systems, Canadian Journal of Civil Engineering, Vol. 2, No. 4, 1975, pp. 558–571.CrossRef
19.
St. Amand, P. Two proposed measures of seismicity, Bulletin of the Seismological Society of America., Vol. 46, 1961.
20.
Howell, B. F., Jr., et al. Integrated and frequency band magnitude, two alternative measures of the size of an earthquake, Bulletin of the Seismological Society of America., Vol. 60, No. 3, 1970.
21.
Blume, J. A. An engineering intensity scale, Bulletin of the Seismological Society of America., Vol. 60, No. 1, 1970.
22.
Blume, J. A. and Monroe, R. E. The Special Matrix Method of Predicting Damage from Ground Motion, John A. Blume & Associates, Research Division, San Francisco, CA, for Nevada Operations Office, U.S. Atomic Energy Commission, 1971.
23.
Trifunac, M. D. and Brady, A. G. On the correlation of seismic intensity scales with the peaks of recorded strong ground motion, Bulletin of the Seismological Society of America., Vol. 65, No. 1, 1975, pp. 139–162.
24.
Richter, C. F. An instrumental earthquake scale, Bulletin of the Seismological Society of America., Vol. 25, 1935.
25.
Aki, K. Generation and Propagation of G Waves from Niigata Earthquake of June 16, 1964, part 2, Estimation of Earthquake Moment, Released Energy and Stress-Strain Drop from G-Wave Spectrum, Bulletin of the Earthquake Research Institute, Tokyo University, Vol. 44, 1966 pp. 73–88.
26.
Cornell, C. A. and Vanmarcke, E. H. The major influences on seismic risk. Proceedings of the 4th World Conference on Earthquake Engineering, Santiago, Chile, 1969.
27.
Algermissen, S. 1. Seismic risk studies in the United States. Proceedings of the 4th World Conference on Earthquake Engineering, Vol. 1, Santiago, Chile, 1969.
28.
Algermissen, S. T. and Perkins, D. M. Earthquake risk studies in the branch of seismicity and risk analysis. Presented at USGS Earthquake Studies Advisory Panel, Colorado School of Mines, Golden, CO, June 4–5, 1975.
29.
Liu, S. C. and Fagel, L. W. Seismic risk analysis– comparison of three different methods. for seismic regionalization, Bulletin of the Seismological Society of America., Vol. 65, No. 4, 1975, pp. 1023–1027.
30.
Esteva, L. Seismic prediction, a bayesian approach. Proceedings of the 4th World Conference on Earthquake Engineering, Vol. 1, Santiago, Chile, 1969.
31.
Mortgat, C. P. Bayesian Approach to Seismic Hazard Mapping. Ph.D. Thesis, Stanford University, 1976.
32.
Esteva, L. Regionalization Seismica de Mexico para fines de Ingenieria. Report 246, Institute of Engineering, National University of Mexico, Mexico City, 1970.
33.
Esteva, L. Seismic risk and seismic design input for nuclear power plants. Seismic Design for Nuclear Power Plants, ed. R.J. Hansen, MIT Press, Cambridge, MA, 1970, pp. 438–483.
34.
Cloud, W. K. and Perez, V. Unusual accelerograms recorded at Lima, Peru, Bulletin of the Seismological Society of America., Vol. 61, 1970, pp. 663–640.
35.
Schnabel, P. and Seed, H. B. Accelerations in rock for earthquakes in the western United States, Bulletin Seismological Society America, Vol. 63, 1973, pp. 501–516.
36.
Gupta, I. N. and Nuttli, O. W. Spatial attenuation of intensities for central U.S. earthquakes, Bulletin Seismological Society America, Vol. 66, No. 3, 1976, pp. 743–751.
37.
Seed, H. B., Murarka, R., Lysmer, J., and Idriss, I. M. Relationships of maximum acceleration, maximum velocity, distance from source and local site conditions for moderately strong earthquakes, Bulletin Seismological Society America, Vol. 66, No. 4, 1976, pp. 1323–1342.
38.
Cough, R. W. Earthquake analysis by response spectrum superposition, Bulletin Seismological Society America, Vol. 52, No. 3, 1962.
39.
Blume, J. A., Sharpe, R. L., and Dalal, J. S. Recommendations for Shape of Earthquake Response Spectra. John A. Blume and Associates, Engineers, San Francisco, CA, February 1973 (USAEC Report No. WASH-1254).
40.
Mohraz, B., Hall, W. J., and Newmark, N. M. A Study of Vertical and Horizontal Earthquake Spectra. Nathan N. Newmark Consulting Engineering Services, Urbana, IL, 1972 (USAEC Report No. WASH-1255).
41.
Seed, H. B., Ugas, C., and Lysmer, J. Site Dependent Spectra for Earthquake Resistant Design, Report No. EERC-74-l2, U.C. Berkeley, 1974.
42.
McGuire, R. K. Seismic Design Spectra and Mapping Procedures Using Risk Analysis Based Directly on Oscillator Response. Branch of Seismicity and Risk Analysis, USGS, Denver, CO, 1975.
43.
Trifunac, M. D. Preliminary empirical model for scaling Fourier amplitude spectra of strong ground acceleration in terms of earthquake magnitude, source-to-station distance, and recording site conditions, Bulletin Seismological Society America, Vol. 66, No. 4, 1976, pp. 1343–1373.
44.
Dobry, R. et al. Influence of magnitude, site conditions and distance on significant duration of earthquakes. The 6th World Conference on Earthquake Engineering, New Delhi, India, January 1977.
45.
Bolt, B. A. Duration of strong motion. Proceedings of the 5th World Conference on Earthquake Engineering, Paper 292, Rome, 1973.
46.
NRC Standard Review Plan Section 2.5.2.11.3, Vibratory Ground Motion Acceptance Criteria, U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, June 1975.
47.
Shakal, A. F. and Toksoz, M. N. Earthquake hazard in New England, Science, Vol. 195, 1977, pp. 171–173.
48.
Thom, H. C. S. New distributions of extreme winds in the United States, Journal of the Structural Division, ASCE, Vol. 94, No. ST7, Proc. Paper 6038, 1968, pp. 1787–1801.
49.
Simiu, E. Probabilistic models of extreme wind speeds: uncertainties and limitation. Proceedings of the 4th International Conference on Wind Effect on Structures and Buildings, London, England, September 1975, pp. 53–62.
50.
Russell, L. R. Probability distributions for hurricane effects, Journal of Waterways, Harbors and Coastal Engineering Division, ASCE, Vol. 97, No. WW 1, 1971, pp. 139–154.
51.
Tryggvason, B. V., Surry, D., and Davenport, A. G. Predicting wind-induced response in hurricane zones, Journal of the Structural Division, ASCE, Vol. 102, No. STI2, 1976, pp. 2333–2351.
52.
Sklarin, J. Probabilities of Hurricanes. Dept. of Civil Engineering, Research Report, MIT, Cambridge, MA, February 1977.
53.
Fujita, T. T. Estimates of Areal Probability of Tornadoes from Inflationary Reporting of their Frequencies. Satellite and Mesometeorology Research Project (University of Chicago), SMRP Research Paper No. 89, October 1970.
54.
Thom, H. C. S. Tornado probabilities, Monthly Weather Review, Oct–Dec 1963, pp. 730–736.
55.
Pautz, M. E. (ed.). Severe Local Storm Occurrences, 1955–1967, U.S. Department of Commerce, Environmental Science Services Administration, ESSA Tech. Memo. VBTM FCST 12, September 1969.
56.
USNRC, Regulatory Guide 1.76, Design Basis Tornado for Nuclear Power Plants, Directorate of Regulatory Standards, April 1974.
57.
Garson, R. C., Catalan, J. M., and Cornell, C. A. Tornado design winds based on risk, Journal of the Structural Division, ASCE, Vol. 101, No. ST9, 1975, pp. 1883–1897.
58.
Hoecker, W. H., Jr. Wind speed and air flow patterns in the Dallas tornado of April 2, 1957, Monthly Weather Review, Vol. 88, No. 5, 1960, pp. 167–180.
59.
Hoecker, W. H., Jr. Three dimensional pressure patterns of the Dallas tornado and some resultant implications, Monthly Weather Review, Vol. 89, No. 12, 1961, pp. 533–542.
60.
Wen. Y. K. and Ang, A. H-S. Tornado risk and wind effect on structures. Proceedings of the 4th International Conference on Wind Effect on Buildings and Structures, London, England, September 1975, pp. 63–73.
61.
Wen, Y. K. Note on analytical modeling in assessment of tornado risks. Proceedings of Symposium on Tornadoes, Assessment of Knowledge and Implications for Man, June 1976, Texas Tech University, Lubbock, TX.
62.
Wen, Y. K. Dynamic wind loads on tall buildings, Journal of the Structural Division, ASCE, Vol. 101, No. ST1, 1975, pp. 169–185.
63.
Kuo, H. L. Axisymmetric flow in the boundary layer of a maintained vortex, Journal of Atmospheric Sciences, Vol. 28, No. 1. 1971, pp. 20–41.
64.
McDonald, J. R., Minor, J. E., and Mehta, K. C. Tornado generated missiles. Specialty Conference on Structural Design of Nuclear Power Plant Facilities, Chicago, IL, December 17–18, 1973, Proceedings (PubI.: ASCE), Vol. II, pp. 543–556.
65.
McDonald et al. Tornado generated missiles. Int. Conf. Nuclear Plant Facilities, Dec. 1973 ASCE, Vol. 11, pp. 543–556.
66.
Abbey, R. F. and Fujita, T. T. Use of tornado path length and gradations of damage to assess tornado intensity probability. proceedings of the 9th Conference on Severe Local Storms, Norman, Oklahoma, 1975.
67.
Abbey, R. F. Risk probabilities associated with tornado windspeeds. Proceedings of the Symposium on Tornadoes, Assessment of Knowledge and Implication for Man, June 1976. Texas Tech University, Lubbock, TX.
68.
American Nuclear Society, ANS 24, Draft American National Standard, Tsunami Guidelines at Power Reactor Sites, ANSI N515, December 1975.
69.
Wiegel, R. L. Earthquake Engineering. Prentice-Hall, Englewood Cliffs, NJ, 1970.
70.
Gumbel, E. J. Statistical Theory of Extreme Values and Some Practical Applications, National Bureau of Standards, Applied Mathematics Series, No. 33, Superintendent of Documents, U.S. Government Printing Office, Washington, 1954.
71.
Gumbel, E. J. Statistics of Extremes. Columbia University Press, New York, NY, 1958.
72.
Wall, I. B. Probabilistic assessment of flooding hazard for nuclear power plants, Transactions of the American Nuclear Society, Vol.16, No.211, 1973; Nuclear Safety, Vol. 15, No. 4, 1974, pp. 399–408.
73.
Linsley, R. K., Kohler, M. A., and Pauthus, J. L. H. Hydrology for Engineers, 2nd edn. McGraw-Hill, New York, NY, 1975.
74.
Shane, R. M. and Lynn, W. R. Mathematical model for flood risk evaluation, Journal of the Hydraulics Division, ASCE, Vol. 90, No. HY6, 1964, pp. l–20.
75.
Linsley, R. K. and Franzini, J. B. Water Resources Engineering, 2nd edn. McGraw-Hill, New York, NY, 1972.
76.
Linsley, R. K., Kohler, M., and Paulhus, J. L. H. Applied Hydrology. McGraw-Hill, New York, NY, 1949.
77.
U.S. Weather Bureau. Rainfall Frequency Atlas of the United States for Durations from 30 Minutes to 24 Hours and Return Period from 1 to 100 Years, Weather Bureau Technical Paper No. 40, Washington, D.C., 1964.
78.
U.S. Weather Bureau. Seasonal Variation of the Probable Maximum Precipitation East of the 105th Meridian for Areas from 10 to 1000 Square Miles and Durations of 6, 12, 24 and 48 Hours, Hydrometeorological Report No. 33, U.S. Weather Bureau, 1956.
79.
Browzin, B. S. Statistical safety factor concept for determining the probable maximum flood. Specialty Conference on Structural Design of Nuclear Power Plant Facilities, Chicago, IL, December 1973; Proceedings (Publ. ASCE), Vol. II, pp. 557–570.
80.
USNRC Standard Review Plan, Section 2.4.3, Probable Maximum Flood (PMF) on Streams and Rivers, U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, September 1975.
81.
American Nuclear Society. Draft American National Standard, Guidelines for Determining Design Basis Flooding at Power Reactor Sites, ANSI N 170.
82.
USNRC Standard Review Plan, Section 3.5.1, U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, September 1975.
83.
Electric Power Research Institute. Tornado Missile Risk Analysis, EPRI NP- 154, Project 616-I, Topical Report 1, January 1975.
84.
Johnson, B. Tornado Missile Risk Analysis, Study Being Conducted for Boston Edison Power Company by Science Applications, Inc., Private Communication, 1976.
85.
Bush, S. H. Probability of damage to nuclear components due to Turbine Failure, U.S.A.E.C., ACRS, and Pacific Northwest Laboratories, Battelle Memorial Institute, November 6, 1972.
86.
Bush, S. H. Probability of damage to nuclear components due to turbine failure, Nuclear Safety, Vol. 14, No. 3, 1973, pp. 187–201.
87.
Emmert, H. D. Investigation of large steam-turbine spindle failure, Mechanical Engineering, Mechanical Engineering, 1956, p. 46.
88.
Rankin, A. W. and Seguin, B. R. Report of the investigation of the turbine-wheel fracture at Tanners Creek, Mechanical Engineering, 1956, p. 47.
89.
Schabtach, C., Fogleman, E. L., Rankin, A. W., and Winne, D. H. Report of the investigation of two generator-rotor fractures, Mechanical Engineering, p. 48, 1956.
90.
Peterson, R. E., Mochel, N. L., Conrad, J. D., and Gunther, D. W. Large rotor forgings for turbines and generators, Mechanical Engineering, p. 49, 1956.
91.
Lindley, A. L. G. and Brown, F. H. S. Failure of a 60-MW steam turbo-generator at Uskmouth Power Station, Proceedings of the Institution of Mechanical Engineers, Vol. 172, 1958, p. 627.
92.
Kalderon, D. Steam turbine failure at Hinkley Point ‘A’, Proceedings of the Institution of Mechanical Engineers, Vol. 186, 1972, p. 341. Hinkley Point ‘A’ Power Station, Proceedings of the Institution of Mechanical Engineers, Vol. 186, 1958, p. 379.
93.
Codier, E. O. Reliability growth in real life. Proceedings of the IEEE Annual Symposium on Reliability, Boston, January 1968;– Duane, J. T. General Electric Company Report DF62 MD300.
94.
Downs, J. E. Hypothetical Turbine Missiles—Probability of Occurrence, General Electric Co., Turbine Dept., Memo Report, March 1973.
95.
Analysis of the Probability of the Generation and Strike of Missiles from a Nuclear Turbine, Westinghouse Electric Corp., Steam Turbine Division Engineering, March 1974.
96.
Hagg, A. C. and Sankey, G. O. The containment of disk burst fragments by cylindrical shells, Transactions of the ASME, Journal of Engineering for Power, Vol. 96, 1974, pp. 114–123.
97.
Report Covering the Effects of a Turbine Accelerating to Destructive Overspeed, Westinghouse Electric Corp., Report 196/381 A, 1974.
98.
Report Covering the Effects of a High Pressure Turbine Rotor Fracture and Low Pressure Turbine Disc Fractures at Design Overspeed, Westinghouse Electric Corp., Report 196/381 B, 1974.
99.
Turbine Missile Analysis, Allis-Chalmers Power Systems Inc., Report Contained in Grand Gulf PSAR (Docket No. 50-416), Amendment 6, April 1973.
100.
Downs, J. E. Hypothetical Turbine Missile Data, 43-Inch Last Stage Bucket Units, General Electric Co., Turbine Dept., Memo Report, March 1973.
101.
Semanderes, S. N. Methods of Determining the Probability of a Turbine Missile Hitting a Particular Plant Region, WCAP-786I, Westinghouse Electric Corp., 1972.
102.
Semanderes, S. N. Method of determining missile impact probability, Transactions of the American Nuclear Society, Vol. 15, No. 1, 1972, p. 401.
103.
O’Connell, W. J., Bascheire, R. J. Design applications of turbine missile impact Analysis. Proceedings of the 2nd ASCE Specialty Conference on Structural Design of Nuclear Plant Facilities, New Orleans, LA, December 1975 (publ. ASCE), pp. 541–561.
104.
O’Connell, W. J. and Fortney, R. A. Turbine missile impact analysis: a detailed treatment, Transactions of the American Nuclear Society, Vol. 19, 1974, p. 231; EDS Nuclear Inc., Report, October 27, 1974.
105.
Swan, S. W. and Meleis, M. A method of calculating turbine missile strike and damage probabilities, Nuclear Safety, Vol. 16, 1975, pp. 443–451.
106.
Bhattacharya, A. K. and Chaudhuri, S. K. The Probability of a turbine missile hitting a particular region of a nuclear power plant, Nuclear Technology, Vol. 28, 1976, pp. 194–198.
107.
Johnson, B. et al. Analysis of the Turbine Missile Hazard to the Nuclear Thermal Power Plant at Pebble Springs, Oregon, Science Applications Inc. Report to the Portland General Electric Company, PGE-2012, January 1976.
108.
Hornyik, K. Hazards to nuclear plants from surface traffic accidents, Nuclear Technology, Vol. 25, 1975, pp. 651–657.
109.
USNRC Standard Review Plan, Section 3.5.1.6, Aircraft Hazards, U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, September 1975.
110.
Census of U.S. Civil Aircraft, Office of Management Systems, Federal Aviation Administration, Department of Transportation.
111.
Analysis of Aircraft Accident Data, U.S. Civil Aviation, National Transportation Safety Board, Department of Transportation.
112.
Chelapati, C. V., Kennedy, R. P., and Wall, I. B. Probabilistic assessment of aircraft hazard for nuclear power plants, Nuclear Engineering and Design, Vol. 19, 1972, pp. 333–364.
113.
Wall, I. B. and Augensteifl, R. C. Probabilistic assessment of aircraft hazard to a nuclear power plant – I, Transactions of the American Nuclear Society, Vol. 13, 1970, p. 217.
114.
Chelapati, C. V. and Wall, 1. B. Probabilistic assessment of aircraft hazard for nuclear power plants – II,” Transactions of the American Nuclear Society, Vol. 13, 1970, p. 218.
115.
Wall, I. B. Probabilistic assessment of aircraft risk for nuclear power plants, Nuclear Safety, Vol. 15, No. 3, 1974.
116.
Long Island Lighting Co., Shoreham Station (Docket 50-322), Amendment No. 3, February 1969.
117.
Solomon, K. A. Hazards associated with aircrafts and missiles, Transactions of the American Nuclear Society, Vol. 23, 1976, p. 312.
118.
Hornyik, K. Airplane crash probability near a flight target, Transactions of the American Nuclear Society, Vol. 16, 1973, p. 209.
119.
Hornyik, K. and Grund, J. E. Evaluation of air traffic hazards at nuclear power plants, Nuclear Technology, Vol. 23, 1974, pp. 28–37.
120.
NRC Regulatory Guide 1.70, Standard Format and Content of Safety Analysis Reports for Nuclear Power Plailts, LWR Edition, Revision 3, NUREG-75/094, U.S. Nuclear Regulatory Commission, Office of Standards Development, September 1975.
121.
Aircraft crash probabilities, Nuclear Safely, Vol. 17, 1976, pp. 312–314.
122.
Hahn, G. J. and Shapiro, S. S. Statistical Models in Engineering. Wiley, New York, NY, 1967.
123.
Julian, O. G. Synopsis of first progress report of committee on safety factors, Journal of the Structural Division, Proceedings of the ASCE, Vol. 83, No. ST4, 1957.
124.
Kececiouglu, D. Reliability analysis of mechanical components and systems, Nuclear Engineering and Design, Vol. 19, 1972, pp. 259–290.
125.
Report of ASCE-ACI Joint Committee on Ultimate Strength Design, Proc. Sep. No. 809, ASCE, Vol. 81, October 1955.
126.
Sexsmith, R. O. Reliability Analysis of Concrete Structures, Technical Report No. 83, Dept. of Civil Engineering, Stanford University, Stanford, CA, August 1967.
127.
Andersen, P. The Resistance to Combined Flexure and Compression of Square Concrete Members, University of Minnesota Engineering Experiment Station Technical Paper No. 29, University of Minnesota, 1941.
128.
Veist, E. and Hognestad, E. Sustained load strength of eccentrically loaded short reinforced concrete columns, ACI Proceedings, Vol. 52, 1956, pp. 727–755.
129.
Chelapati, C. V. and Wall, I. B. Probabilistic assessment of seismic risk for nuclear power plants, Transactions of the American Nuclear Society, Vol. 12, 1969, p. 684; Holmes and Narver, Inc. Report, December 1969.
130.
Hadjian, A. H. and Hamilton, C. W. Probabilistic frequency variations of concrete structures. 2nd International Conference on Structural Mechanics in Reactor Technology, Berlin, 1973; Paper K-3/5.
131.
Stevenson, J. D. and Moses, F. Reliability analysis of framed structures, Journal of the Structural Division, ASCE, Vol. 96, No. STI 1, Proc. Paper 7692, 1970.
132.
Riera, J. O. On the stress analysis of structures subjected to aircraft forces. Nuclear Engineering and Design. North Holland Publishing, Amsterdam, Holland, 1968, p. 8.
133.
Long Island Lighting Co., Shoreham Station (Docket 50-322), Amendment No. 3, February 1969.
134.
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.
135.
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, March 1975.
136.
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, March 1975.
137.
ANS 58.2 Committee, Design Basis for Protection of Nuclear Power Plants Against Effects of Postulated Rupture,” ANS-N 176, January 1977 (Draft).
138.
Marcal, P. V. Finite element analysis with material Nonlinearities theory and practice. Pressure Vessel and Piping Design and Analysis, Vol. 1. American Society of Mechanical Engineers, 1972, p. 486.
139.
AEC Standard Review Plan Section 3.8.1, Concrete Containment, U.S. Atomic Energy Commission, Directorate of Licensing, 1974.
140.
AEC Standard Review Plan Section 3.8.3, Concrete and Steel Internal Structure of Steel and Concrete Containments, U.S. Atomic Energy Commission, Directorate of Licensing, 1974.
141.
ASME code Section 3 Division 2. ACI code for PCCV and PCRV, Article CC 6000, 1989.
142.
Axcell, Containment cooling by water film, The Nuclear Engineer, Vol. 42, Number 1, 2001.
143.
Basu, K. Containment construction using HPC (i\EB) India. Proceedings of seminar on containments of nuclear reactors in conjunction with 15tn SMIRT, Seoul, 1999.
144.
Chataigner, Granger, Touret et al. Containment leakage under accident conditions. Proceedings of Seminar on Containment of Nuclear Reactors in Conjunction with 15th SMIRT, Seoul, 1999.
145.
Costaz. Le béton hautes performances (HPC), RGN No 4, 1992.
146.
Costaz (EDF Septen), 15–22 November, Infrastructures for energy, Keynote, IFTA Seminar on Civil Engineering and Architecture, 1992.
147.
Costaz, Picaut, Chataigner. Delayed Phenomena Analysis from French PWR 900 MW containment. Monitoring comparison with foreseen design values. SMIRT 10, 1989.
148.
Danish, Hansen, Liersch, Peter. Testing of a concrete containment model coated with a composite liner. SMIRT 14, Vol. 5 Div. H concrete structures. HW/2, 1997.
149.
Danisch, Hansen. Status report on German containment composite liner research. Proceedings of Seminar on Containment of Nuclear Reactor in Conjunction with 15th SMIRT, Seoul, 1999.
150.
De Larrare, Ithuralde, Acker, Chauvel. HPC for NPP, 2nd International Conference on Utilisation of HSC, Berkeley, ACISP, 1990.
151.
FIP – Fédération Internationale de la Précontrainte, state-of-art report: Design and construction of prestressed concrete reactor vessels, June 1978.
152.
Granger, Labbé. Mechanical and leak tightness behaviour of a containment mock-up under severe accident – SMIRT 14, Vol. 5 Div. H concrete structures. HW/l, 1997.
153.
Guinet, Decelle, Lancia, Barré. Design and erection of a large mock-up of containment under severe accident conditions – SMIRT 14, Vol. 5 Div. H concrete structures. HW/3, 1997.
154.
Hessheimer, Pace, Klamerus, Matsumoto, Costello Instrumentation and testing of a PCCV model –. SMIRT 14, Vol. 5 Div. H concrete structures. H03/4, 1997.
155.
IAEA – TECDOC-1025. Assessment and management of ageing of major nuclear power plant components important to safety: concrete containment buildings, June 1998.
156.
Irving, Hinley, and Palfrey. The design, analysis and testing of the 1/10 scale model of the sizewell B containment building. International Conference on Structural Design For Hazardous Loads, Institution of Structural Engineers, Brighton, UK, 17–19 April 1991.
157.
Jolivet, Richli, A seismic foundation system for nuclear power stations, SMIRT 4, Vol. K (b), 1977.
158.
Kikuchi, Kobanashi, Ichizono. SIT, Kashiwazahi Kariwa, RCCV. Structural Integrity test of reinforced concrete containment at Kashiwazaki-Kariwa. SMIRT 14. Vol. 5 Div. H concrete structures. H03/5 - H03/6, 1997.
159.
Klymov (State Research Institute of Building Construction, Kiev). Monitoring of stressed-strained state and forces in cables of prestressed containment shells of NPPs. Joint Wano/OECD-NEA. Workshop, Civaux, Poitiers, France, 1997.
160.
Klymov (State Research Institute of Building Construction). Results and Problems of Monitoring of Prestressed Containment of Nuclear Power Plants. OECD-NEA. Workshop, Tractebel-Brussels, Belgium, 2000.
161.
Kuroda et al. Recent advances in concrete containment vessels in Japan, Nuclear Engineering and Design, Vol. 140, 1993.
162.
Kuroda, Hasegawa. Recent topics on concrete containment vessels in Japan: verification of SIT and assurance of safety margins, Japan. Proceedings of Seminar on Containment of Nuclear Reactors in conjunction with 5tii SMIRT, Seoul, 1999.
163.
Libmann. Elements de Süreté Nucléaire – IPSN. Published by Lavoisier, France, 1997.
164.
Maliavine Atom Energoproject Russian Federation. Prestress losses in containments of VVER 1000 Units. Joint Wano/OECD-NEA. Workshop, Civaux, Poitiers, France, 1997.
165.
McFarlane, Smith, Davies, Millustry. In-service monitoring of AGR and PWR Nuclear Safety related Structures in the UK, Institution of Nuclear Engineers, September 1996, Cambridge, UK.
166.
McFarlane, Smith. Plant Life Management. European Commission, Directorate General, FISA 99 Symposium, Luxembourg, 1999.
167.
Martinet, Guinet, Roussel, Granger. Prestress losses in NPP containments: the EDF experience. Joint Wano/OECD-NEA. Workshop, Civaux, Poitiers, France, 1997.
168.
OECD-NEA Nuclear Regulation. Regulatory aspects of life extension and upgrading of MPPs. CNRA Special Issues, Meeting 2000 Report, January 2001.
169.
Picaut, Sidaner, Pastor, Lorteau. The dome of Daya Bay containment, design and construction, SMIRT 11, 1991.
170.
Proceedings of seminar on containment of Nuclear Reactor in Conjunction with 15th SMIRT, Seoul. Thomas Jueger Seminar, 1999.
171.
RCCG, Design and construction rules for civil works of PWR Nuclear Islands.
172.
Roy, Guinet, Barré. Concrete monitoring analysis during the prestressing of a containment and comparison with foreseen design values – SMIRT 14. Vol. 5 Div. H concrete structures, HO 1/2, 1997.
173.
Saito, H. et al. Experimental study on RCCV of ABWR plant. SMIRT 10, 1989.
174.
Setogawa, Sakarai, Funokoshi, Yemaguchi, Koike, Kamei, and Hagro. Structural Integrity tests of prestressed concrete containment vessels at Ohi NPP, SMIRT 12, Vol H, 1993.
175.
SFEN, Proceedings of International Conference on the EPR Project SMIRT 14, August 97, Vol. 5, Div. H concrete structures. H 04/3 PSA of typical 900 MW French nuclear containment. Grangier, Chataigner, November 1995.
176.
Smith, L.M. and Taylor, M.F. The Long term In-Service Performance of Corrosion Protection to Prestressing Tendons in AGR PCPVS, Joint Wano/OECD-NEA Workshop, Civaux, Poitiers, France, 1997.
177.
Smith, De Marneffe, Mathet, Contri. Civil Engineering Instrumentation on Nuclear Power Plants – An International Perspective, Institution of Nuclear Engineers, November 2000.
178.
Tamura, Watanabe, Kato, Yamaguchi, Koike, Komatsu. A delayed phenomena evaluation of prestressed concrete containment vessel at Tsuruga Unit 2 power station. SMIRT 11, 1991.
179.
UNSRC Reg. guide 1.35 ISI ungrouted tendons January 1976
180.
USNRC Reg. guide 1.90 ISI grouted tendons August 1977
181.
Xu Yao Zhang. Containment structure monitoring and prestress losses. Experience from Daya Bay NPP. Joint Wano/OECD-NEA. Workshop, Civaux, Poitiers, France, 1997.
182.
Eurocode-3, BSI, 1999, Revision 2002, 2009.
183.
Johnson, R.P. and Anderson, D. Designers’ Guide to EN 1994-1-1 Eurocode-4. Design of composite steel and concrete structures for buildings. Thomas Telford, 2004.
184.
Eurocode-3, Design of Steel Structures. BSI 2004.
185.
Shahrooz, B.M. (ed.). Composite Construction in Steel and Concrete. ASCE, New York, 2002, No IV, pp. 584–595.
186.
187.
BSI. Design of Structures for Earthquake Resistance, BSI, London, BSEN, 1994.
Metadaten
Titel
Loads and Material Properties for Nuclear Facilities – A General Survey
verfasst von
Prof. Dr. M.Y.H. Bangash
Copyright-Jahr
2011
Verlag
Springer Berlin Heidelberg
Buch
Structures for Nuclear Facilities

Print ISBN: 978-3-642-12559-1

Electronic ISBN: 978-3-642-12560-7

Copyright-Jahr: 2011

DOI
https://doi.org/10.1007/978-3-642-12560-7_2

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