Programs and methods for testing in the MIR research reactor fuel elements of water-cooled reactors under conditions simulating transient and emergency regimes

Author:

Alekseev A. V.,Burukin A. V.,Izhutov A. L.,Kalygin V. V.,Kiseleva I. V.,Ovchinnikov V. A.,Shulimov V. N.

Publisher

Springer Science and Business Media LLC

Subject

Nuclear Energy and Engineering

Reference9 articles.

1. V. V. Goncharov, Research Reactors: Design and Development, Nauka, Moscow (1986).

2. V. A. Kuprienko, “Main stages of the history of and results of studies on the MIR reactor,” in: Collected Works of the Research Institute of Atomic Reactors, Dimitrovgrad (1997), No. 4, pp. 3–17.

3. A. V. Alekseev,V. V. Kalygin, A. P. Malkov, et al., “Formation of the neutron-physical conditions for testing in the MIR reactor VVER fuel elements in nonstationary regimes with increasing power,” At. Énerg., 104, No. 5, 279–284 (2008).

4. V. V. Kalygin, I. V. Kiseleva, A. P. Malkov, and V. N. Shulimov, “Formation of the neutron-physical conditions for testing in the MIR reactor VVER fuel elements in loss-of-coolant accident regimes,” Izv. Vyssh. Uchebn. Zaved. Yad. Energetika, No. 2, 58–65 (2008).

5. A. V. Burukin, A. F. Grachev, V. V. Kalygin, et al., “Tests in the MIR reactor of VVER fuel elements in regimes with an abrupt power increase,” ibid., pp. 66–73.

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