FENG Shaodong ZHANG Ming ZHU Kun XUE Guohong LI Yuan CHEN Huiliang. Evaluation of reactor structural function during core drop accident[J]. Nuclear techniques, 2013, 36(4): 040670
FENG Shaodong ZHANG Ming ZHU Kun XUE Guohong LI Yuan CHEN Huiliang. Evaluation of reactor structural function during core drop accident[J]. Nuclear techniques, 2013, 36(4): 040670 DOI: 10.11889/j.0253-3219.2013.hjs.36.040670.
Background: A core drop accident causes the core barrel and supporting structure to drop and impact on the bottom of the reactor vessel.Purpose: To ensure the scram functionality is maintained.Methods: The stress-strain curves applicable to the material are approximated by Ludwik’s expression.Considering the core deadweight
buoyancy force and heat expansion
material train ratios for both cold and hot conditions are calculated.Results: Vessel impact load(8294482N in cold condition & 6064537N in hot condition) is determined
which remains within the vessel design specification limits.The calculated drop length(47.44 mm in cold condition & 27.63 mm in hot condition) is less than the fuel pin full-diameter engagement length
so the fuel assembly top nozzle will remain engaged during a core drop.Finally the compressive assemblies are evaluated
which would not buckle due to the core drop accident loads.Conclusions: A core drop will not affect the scram function.