Zusammenfassung
Die Sicherheit eines Kernreaktorsystems hängt in erster Linie von dem kernphysikalischen Entwurf des Systems ab, der darauf hinzielt, dem Reaktor inhärent stabile Betriebscharakteristiken zu verleihen. Inhärente Stabilität bedeutet, daß bei einer Störung des Betriebs durch irgendeinen Einfluß die normalen Betriebsbedingungen allein durch die kernphysikalischen Charakteristiken des Systems automatisch wiederhergestellt werden, ohne daß die Hinzuziehung äußerer Hilfsmittel erforderlich ist. Eine große Zahl der bis jetzt entwickelten Kernreaktor-Typen besitzt die Eigenschaft der inhärenten Stabilität in mehr oder weniger ausgeprägtem Maße. Derzeit liegt jedoch noch nicht genügend Erfahrung für den Entwurf unbedingt zuverlässiger Systeme vor. Um den Reaktor steuern und unzureichende inhärente Stabilitätseigenschaften ergänzen zu können, werden in die Reaktorkonstruktion Kontrollvorrichtungen (Kontrollstäbe) eingebaut. Zusätzlich werden Sicherheitsstäbe und andere Apparaturen vorgesehen, um den Reaktor stillegen zu können, wenn der Betrieb sich gefährlichen Bedingungen nähert.
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Literatur zu 18
Mccullough, C. R., M. M. Mills u. E. Teller: The Safety of Nuclear Reactors. Proceedings of the International Conference on the Peaceful Uses of Atomic Energy Vol. 13: Legal, Administrative, Health and Safety Aspects of Large-Scale Use of Nuclear Energy, S. 79–87. New York: United Nations 1956
Mccullouas, C. R.: Safety Aspects’ of Nuclear Reactors. The Geneva Series on the Peaceful Uses of Atomic Energy. Princeton/New York/Toronto/London: D. Van Nostrand 1957
Mccullough, C. R.: The Experience in the United States with Reactor Operation and Reactor Safeguards. Second United Nations International Conference on the Peaceful Uses of Atomic Energy, Genf, 1.-13. September 1958, Paper No. A/CONF. 15/P/1551
Burnett, T. J.: Reactors, Hazard VS Power Level. Nuclear Science and Engineering Vol. 2 (1957) S. 382–393
Parker, G. W., u. G. E. Creek: The Volatilisation of Fission Products by Melting of Reactor Fuel Plates. ORNL–CF–57–6–87, Juli 1957
Rodgers, S. J., W. A. Mcallister, G. E. Kennedy U. J. W. Mausteller: Release and Distribution of Fission Products from Molten Zirconium-Uranium Assemblies. Annual Meeting of the American Nuclear Society, Gatlinburg, Tennessee, 15.-17. Juni 1959
Leonard, B. P., JR.: Hazards Associated with Fission Product Release. Second United Nations International Conference on the Peaceful Uses of Atomic Energy, Genf, 1.-13. September 1958, Paper No. A/CONF. 15/P/428
United States Department of Commerce, Weather Bureau: Meteorology and Atomic Energy. AECU-3066, Juli 1955
United States Atomic Energy Commission: Theoretical Possibilities and Consequences of Major Accidents in Large Nuclear Power Plants. WASH-740, März 1957
Kuper, J. B. II., u. F. P. COWAN: Exposure Criteria for Estimating the Consequences of a Catastrophe in a Nuclear Plant. Second United Nations International Conference on the Peaceful Uses of Atomic Energy, Genf, 1.-13. September 1958, Paper No. A/CONF. 15/P/430
Gomberg, H. J.: A Quantitative Approach to Evaluation of Risk in Locating a Reactor on a Given Site. Second United Nations International Conference on the Peaceful Uses of Atomic Energy, Genf, 1.-13. September 1958, Paper No. A/CONF. 15/P/436
Siddall, E.: Statistical Analysis of Reactor Safety Standards. Nucleonics Vol. 17 (1959) No. 2, S. 64–69
Gray, J. L.: Reconstruction of the NRX-Reactor at Chalk River. The Engineering Journal, Oktober 1953
Gilbert, F. W.: Decontamination of the Canadian Reactor. Chemical Engineering Progress Vol. 50 (1954) S. 267–271
Hatfield, G. W.: A Reactor Emergency with Resulting Improvement. Mechanical Engineering Vol. 77 (1955) S. 124–126
Hurst, D. G., u. A. G. WARD: Canadian Research Reactors. Progress in Nuclear Energy, Series II: Reactors Vol. 1, S. 37–38. London/New York: Pergamon Press 1956
Mawson, C. A.: Waste Disposal into the Ground. Proceedings, International Conference on the Peaceful Uses of Atomic Energy Vol. 9: Reactor Technology and Chemical Processing, S. 676–678. New York: United Nations 1956
The Windscale Incident. Nuclear Engineering Vol. 2 (November 1957) No. 20, S. 453 —454
The Windscale Report: A Summary. Nuclear Engineering Vol. 3 (August 1958) No. 29, S. 338
Mclean, A. S., H. J. Dunster, H. Howells U W. L. TEMPLETON: District Surveys Following the Windscale Incident. Second United Nations International Conference on the Peaceful Uses of Atomic Energy, Genf, 1.-13. März 1958, Paper No. A/CONF. 15/P/316
Cottrell, A. H., et al.: Theory of Annealing Kinetics Applied to the Release of Stored Energy from Irradiated Graphite in Air-Cooled Reactors. Second United Nations International Conference on the Peaceful Uses of Atomic Energy, Genf, 1.-13. September 1958, Paper No. A/CONF. 15/P/2485
Rimmer, D. E.: The Validity of the Constant Activation Energy Model for the Release of Stored Energy in Graphite. AERE-R 3061, August 1959
Schultz, M. A.: The Control System. In H. ETHERINGTON (Hrsgb.): Nuclear Engineering Handbook, Section 8–2. New York/Toronto/London: McGraw-Hill 1958
Problems of Nuclear Ship Propulsion. Nuclear Engineering Vol. 2 (März 1957 ) No. 12, S. 93–95
Mains, R. M.: Shock and Vibration in Naval Reactors. KAPL-M-RMM-2, 31. Oktober 1957
Fayram, R. A., A. T. Bierland U. J. D. Randall: Hazards Evaluation for Nuclear Merchant Ships. Advances in Nuclear Engineering Vol. I, S. 470–475. London/New York/Paris: Pergamon Press 1957
Leverett, M. C.: Some Views on Aircraft Nuclear Propulsion. Meeting of the Metropolitan Section of the Society of Automotive Engineers, New York, 24. März 1959, Paper No. S. 191
Gamertsfelder, C. C.: Safety Aspects of Nuclear-Powered Aircraft. Annual Meeting of the Health Physics Society, Gatlinburg, Tennessee, 17.-20. Juni 1959
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Jaeger, T. (1960). Reaktor-Schadensfälle und ihre Konsequenzen. In: Grundzüge der Strahlenschutztechnik. Springer, Berlin, Heidelberg. https://doi.org/10.1007/978-3-662-01152-2_18
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