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Additional info for Advanced Thermal-Hydraulic, Neutronic Codes Vol 2 (csni-r2001-2-vol2)
This type of code is used to demonstrate compliance with DNBR/CPR-requirements. Modern fuel bundle designs with part length rods and large water holes pose new challenges to the subchannel codes. The proper prediction of the void distribution within the bundle, especially near the non-heated water rods, may require improvements in the so-called lateral void drift modelling. ) These correlations have fuel-design specific formulations, in which burnup-dependence is normally not considered. CPR/DNB is determined based on channel averaged parameters.
E. PWRs with high energy cores) affected. 6 Test programs In this chapter, a few examples of research programs are given that contribute to investigating the phenomena and mechanisms of fuel behaviour under transient / accident conditions. 1 ANL test program Because the expected outcome of a LOCA is strongly dependent on flow blockage and cladding embrittlement, the large amounts of corrosion, enhanced oxidation rates, and reduced cladding ductility experienced at high burnup are likely to have a significant effect.
In summary, changes in core management do not directly upset safety limits or margins; as long as satisfactory modelling is available to describe the phenomena occurring in currently designed and operated cores, safety limits are not affected. 3 MOX In the past reprocessing appeared a viable option in some countries. Thus, contracts with reprocessing companies were put in place resulting in a certain quantity of fissile Pu, which can be used together with UO2 to manufacture so-called mixed oxide fuel (MOX), as well as some amount of reprocessed Uranium (RepU) which may be used as carrier material or blended with regular UO2.
Advanced Thermal-Hydraulic, Neutronic Codes Vol 2 (csni-r2001-2-vol2)