An analysis of the dynamics of the RBMK-1000 reactor for rupture of the pressurized collector at low power
In order to evaluate the safety of the RBMK-1000 reactor, one must study the behavior of the reactor in emergency situations at low power. In this case the core is filled with water, close to the saturation state, and disturbances producing steam in the core may for a positive void coefficient lead to an appreciable power increase. In this article, the authors consider the maximum projected emergency; rupture of the pressurized collector under conditions close to those reached at Power Plant 4 of the Chernobyl Nuclear Power Station just before the 1986 accident. The objective is to determine the possible consequences of the maximum projected emergency at lower power and to estimate the effectiveness in such situations of the measures taken since 1986 to increase the safety of nuclear power stations with RBMK reactors. A numerical analysis was performed on the basis of a general-loop thermohydraulic program Relap5/mod2, including in the algorithm the inverse effect of coolant density on the reactor kinetics, using a precise model with six groups of delayed neutrons.
- OSTI ID:
- 62502
- Journal Information:
- Atomic Energy (New York), Vol. 75, Issue 2; Other Information: PBD: Feb 1994; TN: Translated from Atomnaya Energiya; 75: No. 2, 88-92(Aug 1993)
- Country of Publication:
- United States
- Language:
- English
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