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A typical initiating event for the UTOP is a control rod withdrawal.
Control rod withdrawal in BWRs induces large power steps in the adjacent fuel assemblies.
The measured dose equivalent rates showed good agreement with the predictions considering the control rod withdrawal effect.
The overall nonlinear system is simulated for typical perturbations, e.g., control rod withdrawal and increase in steam demand.
In addition, step of the CRSS and operational logic should be determined by a safety analysis results for control rod withdrawal transients.
It is, however, not possible to follow inner control rod withdrawal and precisely know the location of the perturbation in the core.
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The reactor becomes free from accidents induced by unexpected control rods withdrawal during power operation.
The PRORIA code analyzes the transient response of the core against the reactivity increase caused by the control rod rapid withdrawal.
To illustrate the methodology and applicability of the developed modelling approach, assessment results of a control rod (CR) withdrawal accident during subcritical conditions are presented and compared with those obtained by the JAEA.
The withdrawal of a control rod can be limited by a control rod stop system (CRSS), which has been designed to prevent an over power excursion by reactivity insertion.
Results from a previous paper indicated that it is possible to detect changes in neutron source distribution initiated by an inadvertent withdrawal of outer control rod with in-vessel fission chambers located azimuthally around the core.
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