Title of article :
Development and overall testing of the traditional MTC estimation based on noise diagnostics at all four units of the Paks NPP
Author/Authors :
Kiss، نويسنده , , Sلndor and Lipcsei، نويسنده , , Sلndor and Végh، نويسنده , , Jلnos، نويسنده ,
Issue Information :
روزنامه با شماره پیاپی سال 2011
Pages :
9
From page :
2933
To page :
2941
Abstract :
Moderator Temperature Coefficient (MTC) of reactivity is an important parameter of nuclear reactors and its value should be in a specific range during the reactor operation. Determining MTC with traditional methods is performed through deviating the reactor state from the normal operation. Noise diagnostics has the potential to provide an MTC estimation method during normal operation without changing the reactor state. aper overviews the developments made on the traditional noise based estimators and the steps of their application in VVER-440 type reactors. Modifications were made to consider the effect of propagating perturbations through geometry and coolant velocity and to compensate the frequency response of the slow thermocouples. Frequency dependence of H1 was calculated in high resolution which involved the revision of the method applied for reading the MTC value earlier (see the details in Kiss et al., 2010a,b). igations were performed at all four units of the Paks NPP to verify the dependence of the results on specific core features (e.g. on core loading patterns) and instrumentation of the individual units. For a better comparison of the results, a common frequency range of the evaluation was chosen for all units, thus this range was made narrower and its weight went closer to the frequency range affected by power feedback. Absolute values of the estimated MTC are smaller than the reference value due to the effect of feedback and low coherence. During the investigated fuel cycles estimations were quite close to the reference for two units (the deviation was around 10%), while the agreement was only moderate for the other two units (here the deviation was around 40%).
Journal title :
Nuclear Engineering and Design Eslah
Serial Year :
2011
Journal title :
Nuclear Engineering and Design Eslah
Record number :
1591116
Link To Document :
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