Testing the IVV-2M fuel element bundle in the graphite pulse reactor (IGR) under emergency loss-of-flow conditions and A pulsed growth in energy release
KeywordsGraphite Energy Release Fuel Element Pulse Reactor Pulse Growth
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- 1.J. Lau, C. Blahnik, and O. Akalin, “CANDU fuel behavior under severe fuel damage conditions,” Nuclear Power. Perform and Satisfy: Proc. International Conference, Vienna, September 28-October 20, Vol. 4, IAEA, Vienna (1988), pp. 257–273.Google Scholar
- 2.V. I. Andreev, V. I. Kolyadin, and V. V. Yakolev, “Methodological aspects of studying the behavior of fuel elements under nonstationary conditions,” At. Tekh. Rubezhom, No. 3, 3–7 (1985).Google Scholar
- 3.I. Ya. Belen'kii, M. A. Gotovskii, G. A. Kirsanov, and B. S. Fokin, “Experimental investigation of the thermal-physical state of the core of the PIK reactor for a sharp drop in pressure,” Problems of Atomic Science and Engineering, Series Physics and Engineering of Nuclear Reactors [in Russian], No. 1 (1990), pp. 34–38.Google Scholar
- 4.D. O. Kalninysh, P. A. D'yakov, B. V. Dysikov, et al., “Investigation of operating conditions of fuel elements for partial uncovering of the core,” At. Énerg.,70, No. 3, 197–199 (1991).Google Scholar
- 5.N. Kjaer-Pederson, “Fuel operational limits based on Studsvik international projects data,” Trans. Am. Nucl. Soc.,52, 604–606 (1986).Google Scholar
- 6.I. V. Kurchatov, S. M. Feinberg, N. A. Dollezhal', et al., “Graphite pulsed reactor,” Report No. 322-a [in Russian], in: 3rd International Conference on the Peaceful Uses of Atomic Energy, Geneva (1964).Google Scholar
© Plenum Publishing Corporation 1992