Induced nuclear reactions: processes – systems – and elements – Testing – sensing – measuring – or detecting a fission reactor... – Leak detection
Patent
1988-11-17
1990-07-03
Wasil, Daniel D.
Induced nuclear reactions: processes, systems, and elements
Testing, sensing, measuring, or detecting a fission reactor...
Leak detection
G21C 1706
Patent
active
049389173
ABSTRACT:
This invention teaches improved apparatus for the method of detecting a breach in cladded fuel used in a nuclear reactor. The detector apparatus is located in the primary heat exchanger which conveys part of the reactor coolant past at least three separate delayed-neutron detectors mounted in this heat exchanger. The detectors are spaced apart such that the coolant flow time from the core to each detector is different, and these differences are known. The delayed-neutron activity at the detectors is a function of the delay time after the reaction in the fuel until the coolant carrying the delayed-neutron emitter passes the respective detector. This time delay is broken down into separate components including an isotopic holdup time required for the emitter to move through the fuel from the reaction to the coolant at the breach, and two transit times required for the emitter now in the coolant to flow from the breach to the detector loop and then via the loop to the detector. At least two of these time components are determined during calibrated operation of the reactor. Thereafter during normal reactor operation, repeated comparisons are made by the method of regression approximation of the third time component for the best-fit line correlating measured delayed-neutron activity against activity that is approximated according to specific equations. The equations use these time-delay components and known parameter values of the fuel and of the part and emitting daughter isotopes.
REFERENCES:
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patent: 4415524 (1983-11-01), Gross et al.
Nuclear Radiation Detection, Price, Sections 10.10-10.11, (McGross-Hill, New York 1964).
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"Equivalent Recoil Area Concept for Delayed Neutron Signal Characterization", Transactions of the American Nuclear Society, vol. 35, 11/80.
Argonne National Laboratory, ANL-RDP-111, Cissel et al, pp. 6.3814 6.42, (12/83).
"System for On-Line Characterization of Delayed Neutron Signals", Transaction of the American Nuclear Society, vol. 47, pp. 444-445, 11/84.
Argonne National Laboratory, ANL-80-55, Gross, 7/80.
Gross Kenny C.
Lambert John D. B.
Poloncsik John
Fisher Robert J.
Glenn Hugh G.
Moser William R.
The United States of America as represented by the United States
Wasil Daniel D.
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