Home / Publications / Journals / Nuclear Technology / Volume 24 / Number 1
Nuclear Technology / Volume 24 / Number 1 / October 1974 / Pages 7-12
Technical Paper / Reactor / dx.doi.org/10.13182/NT74-A31456
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Calculations of super prompt critical excursions induced by ramp variation of absorption cross sections are performed in various geometries (r, xy, rz, xyz). The time behavior of neutron flux and fuel temperature is analyzed, especially with regard to their dependence on geometry and rod velocity. The evaluations establish the need for genuine three-dimensional calculations to correctly predict peak flux and temperature distributions for situations where space-dependent feedback effects essential.