Has BWR Fuel Development Increased RIA Risk During Nuclear Heating?

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Recent developments in BWR fuel, including increased enrichment and part-length fuel rods, have raised concerns about higher reactivity insertion risks during nuclear heating, particularly during control rod withdrawal. The potential for significant reactivity insertion during a postulated rod drop accident is highlighted, especially when adjacent control rods are removed. There is skepticism about the adequacy of current analysis methods that focus solely on critical zero power (CZP) and hot zero power (HZP) conditions, as the most limiting scenarios may occur at intermediate power levels. The interplay between control rod worth and negative feedback mechanisms at elevated temperatures complicates the assessment of reactivity risks. Further investigation and calculations are encouraged to better understand these dynamics and ensure compliance with reactivity insertion accident (RIA) limits.
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It seems that the recent developments in BWR fuels (increased enrichment, added uranium mass at the bottom, part-length fuel rods especially in the corners) have changed the control rod reactivity values in such a way that the potential reactivity insertion caused by the postulated rod drop accident is potentially quite high at certain points during nuclear heating. More specifically, at the stage when CR:s adjacent tho those already withdrawn are being taken out of the core. This may result into quite large reactivity insertions and it is not trivial that the RIA limits of fuel are fulfilled at every point (up until the spectral effect finally cuts the CR reactivity values), if the situation has not been considered thoroughly at some stage during the gradual fuel development.

I was wondering if someone else has come up with this issue, and if there are some findings that might be of interest? Especially the behaviour of Doppler and other feedback mechanisms during the heating phase would be interesting. I am planning to do some generic calculations on my own, but it would be nice to know if someone has already done something in this direction.
 
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Yes, that is a very good report concerning the consequences of the postulated CR drop. However, even there on page 143 it is suggested that analyses are performed either at CZP (where the enthalpy rise has traditionally been limiting) or at HZP (which has traditionally been close to the maximum reactivity insertion point). What I'm mainly concerned is the validity of using only these two points, as it seems that the most limiting point might actually lie somewhere in between, or perhaps at a few % power, depending on the reloading pattern and the withdrawal sequence.

There are two competing effects: the CR worth, which tends to be the largest at a certain point rather late in the in the withdrawal sequence, and the negative feedbacks, which are more effective at increased temperature. Using just the CZP and HZP points in the analyses might fail to catch the most limiting transient.
 
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