Method for determining reactor coolant system leakage
Abstract
Abstract ACTOR COOLANT SYSTEM. THE DIRECT METHOD RELIES ON MEASUREMENTS OF RADIOACTIVITY PRODUCED BY SHORT HALF-LIVED NOBLE GAS ISOTOPES. MEASUREMENTS AT A VOLUME CONTROL TANK, WHICH IS PART OF THE REACTOR COOLANT SYSTEM, AND IN THE CONTAINMENT ATMOSPHERE PROVIDE SUFFICIENT INFORMATION TO DIRECTLY REDUCE THE REACTOR COOLANT SYSTEM LEAKAGE RATE. THE INVENTION PROVIDES INDIRECT AND DIRECT METHODS FOR DETERMINING LEAKAGE FROM A REACTOR COOLANT SYSTEM INSIDE THE REACTOR CONTAINMENT. THE INDIRECT METHOD RELIES ON THE COMPARSION OF QUANTITATIVE MEASUREMENTS OF A TRACER, SUCH AS TRITIUM, IN THE REACTOR COOLANT TO THE TRACER IN THE CONDENSATE COLLECTED BY THE CONTAINMENT COOLING COILS TO DETERMINE WHAT PART OF THE TOTAL COLLECTION, REPRSENTING ALL LEAKAGE, IS DERIVED FROM THE RE-
Inventors
- 👤 D Campbell
- 👤 J Locante
Bibliographic Details
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