Abstract
The basic structural features of RBMK reactor systems (absence of an overall external protective shell, disintegrating nature of the circulation loop, multichannel nature of the core, positive steam coefficient of reactivity, large mass of the high-heat-capacity graphite moderator), which predetermine the development of postulated serious unanticipated accidents and their control, are examined. Categories of core behavior for unanticipated accidents and types of accidents resulting in a definite type of damage are determined. The character of the flow of typical unanticipated accidents, possible approaches to controlling the consequences of accidents, and means for performing computational analysis of unanticipated accidents are examined.
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REFERENCES
General Tenets for Ensuring the Safety of Nuclear Power Plants OPB-88/97, Gosatomhadzor Rossii, Moscow (1997).
Report of Consulting Committee on Core Damage States for NPP's with RBMK Reactors, IAEA, Vienna (1996).
V. P. Vasilevskii, “Development of symptom-oriented emergency instructions for power-generating units with RBMK reactors,” Yearly Report of NIKIÉT, NIKIÉT, Moscow (1998), p. 69.
D. A. Afremov, V. E. Men'shikov, and Yu. M. Nikitin, “Investigation of cooldown conditions for the core in the No. 2 unit of the Leningrad nuclear power plant with prolonged loss of power for internal needs,” Yearly Report of NIKIÉT, NIKIÉT, Moscow, (2000), p. 95.
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Vasilevskii, V.P., Nikitin, Y.M., Petrov, A.A. et al. Characteristic Features of the Development of Serious Unanticipated Accidents in RBMK Reactors and Approaches to Controlling Such Accidents. Atomic Energy 90, 442–447 (2001). https://doi.org/10.1023/A:1012303513242
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DOI: https://doi.org/10.1023/A:1012303513242