Method of supervising the channel stability in reactor cores of

Details Method of supervising the channel stability in reactor cores of Method of supervising the channel stability in reactor cores of

1980-04-22

1982-03-16

Walsh, Donald P.

Induced nuclear reactions: processes, systems, and elements

Testing, sensing, measuring, or detecting a fission reactor...

376216, 376246, G21C 700

Patent

active

043199593

ABSTRACT:
In supervising the channel stability of a nuclear reactor, the thermal power and the coolant flow quantity in each fuel assembly are determined by signals produced by a plurality of neutron flux detectors installed in the nuclear reactor, and signals regarding other operating conditions of the reactor, and the thermo-hydrodynamic stability of each fuel assembly is judged by the above-mentioned thermal power and coolant flow quantity as well as the measured values of such parameters as inlet subcooling of the core and of the pressure in the reactor vessel. Or the stability limit of a selected one of the parameters is determined. Then, the threshold of the thermo-hydrodynamic stability or the stability limit is compared with the actually measured value thereof so as to determine a stability margin.

REFERENCES:
patent: 4080251 (1978-03-01), Musick
Thie, Joseph A., "Core Motion Monitoring", Nuclear Technology, vol. 45, Aug. 1979.
Carew, J. F., "Process Computer Performance Evaluation Accuracy", Ge. E. 58/730/FD & SA, WCC/6-74.
Laney, Sr., et al., "The Thermal Hydraulics of a Boiling Water Nuclear Reactor", ANS 1977.
Jones, A. B, "Hydrodynamic Stability of a Boiling Channel", KAPL-2170, Oct. 2, 1961.
Ishii, Mamoru, "Thermally Induced Flow Instabilities in Two Phase Mixtures in Thermal Equilibrium", Georgia Inst. of Tech., Phd., 1971-Univ. Microfilms 71-28,095.
Saha, et al., "An Experimental Investigation of the Thermally Induced Flow Oscillations in Two-Phase Systems", ASME, Jul. 25, 1975.

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