Quality control of metal-concrete flasks for spent nuclear fuel

摘要

The safety operation of a serial metal-concrete flask intended for spent nuclear fuel (SNF) storage requires flaw inspection of its concrete filler and testing of the radiation protection parameters of the casing for compliance to design specifications. A test bench for γ flaw detection of flasks intended for storage and transportation of SNF in an amount of (5-7) × 10~3 kg with an activity of ~10~6 Ci is described (including its new version). The kinematics of the bench, as well as its electronics, software, and hardware solutions that improve the survivability and reliability of the instrumentation and raise the validity of measurement results, are presented.