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Pellet-Clad Interaction in Water Reactor Fuels: Seminar by OECD - Organisation for Economic Co-operation and

By OECD - Organisation for Economic Co-operation and Development

This document communicates the result of a global seminar which reviewed fresh growth within the box of pellet-clad interplay in gentle water reactor fuels. It additionally attracts a entire photograph of present realizing of proper phenomena and their impression at the nuclear gas rod, lower than the widest attainable stipulations. cutting-edge wisdom is gifted for either uranium-oxide and mixed-oxide fuels.

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Extra resources for Pellet-Clad Interaction in Water Reactor Fuels: Seminar Proceedings, Aix-en-Provence, France, 9-11 March 2004

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The damage in the clad is limited to a crack. The clad maintains its structural integrity and the fuel temperature is not affected by the PCI failure mechanisms, which is not the case for DNB or LOCA situations. In particular, there is no direct contact between fuel pellet and primary coolant. The main consequence of PCI failure is a contamination of the primary coolant by fission gases. The risk of PCI failure during Class 2 transients was considered while NPPs were already in the operating phase, so it was not conceivable to apply the standard design basis rules.

For that reason the control blade sequence exchanges are performed at reduced reactor power. g. Rod A5 in Figure 2) may be subjected to significant power ramps. Figure 3 shows the changes of the axial power distribution in a rod close to a control blade calculated with the MICROBURN-B2 BWR Core Simulator of AREVA [9]. Three incremental control blade pulls of two notches each at 92% core power were followed by return to 100% power. Figure 4 illustrates the evolution of the nodal LHGR. 3 kW/m after return to full power.

7% at which point the turbine/generator was brought on-line. At this power level, the Group D control rods had been withdrawn to 40%. Power was increased to the next hold point of approximately 29% as the control rods were withdrawn to 75%. During the hold, the reactor power was increased very slowly to 30% power, the threshold at which power ramp rate restrictions are imposed. Based on the times and power levels, it is estimated that the 32 Figure 1. Typical start-up of a US PWR power ascension rate from 12 to 29% was accomplished at a rate of approximately 16%/hr.

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