1. Methodological Directions on the Calculation of the Critical Coolant Flow Rate in the Accidental Rupture of the Circulational Loop of an Atomic Power Plant with an RBMK Reactor. MU 34-70-142-86 [in Russian], Minénergo SSSR, Moscow (1986).
2. V. A. Grigor'ev (ed.), Heat and Mass Transfer. Thermal-Engineering Experiments: A Handbook [in Russian], Énergoizdat, Moscow (1982), pp. 111?113.
3. K. Ardron and A. Furness, ?A study of critical flow models used in reactor blowdown analysis,? Nucl. Eng. Des.,39, 117?121 (1976).
4. G. Wallis, ?Critical two-phase flow,? Int. J. Multiphase Flow,6, No. 1-2, 97?112 (1980).
5. V. E. Cheremin, ?Increasing the efficiency of devices limiting the flow rate and maximum reactive stress in the reactor-loop rupture in atomic power plants,? Autor's Abstract of Candidate's Dissertation, Odessa Polytechnic Institute, Odessa (1985).