Abstract
Ensuring integrity of nuclear fuel clad is most important from radiation safety point of view. The paper provides introduction to experimental and theoretical methods for evaluation of rewetting velocity. Quality Assurance (QA) checks on Emergency Core Cooling System (ECCS) in Nuclear Reactors are very important to ensure accurate coolant flow introduction and minimum radiation hazard during Loss of Coolant Accident (LOCA). In-depth knowledge of acceptable rate of temperature rise of fuel subsequent to LOCA and having fully reliable method to ensure that the same will not exceed the set limit is testimony of safe reactor operation. Spread of radioactive contamination and resultant radiation exposure from above contamination in nuclear reactors depends heavily on size and shape of split or rupture in clad. [10] Suggests that a plant operating with 0.125 percent pin-hole in fuel-clad defects showed in general, upto five-fold increase in contamination level and resultant whole-body radiation exposure rates in some areas of the plant when compared to a sister plant with high-integrity fuel. The checks on ECCS will protect environment and public from radiation exposure to remarkable extent.
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