Quality control of metal-concrete flasks for spent nuclear fuel

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 in...

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Bibliographic Details
Published inTechnical physics Vol. 56; no. 8; pp. 1195 - 1201
Main Authors Shchigolev, N. D., Solovei, V. A., Kolkhidashvili, M. R., Pirogov, A. M.
Format Journal Article
LanguageEnglish
Published Dordrecht SP MAIK Nauka/Interperiodica 01.08.2011
Springer
Subjects
Classical and Continuum Physics
Experimental Instruments and Technique
Nuclear energy
Nuclear industry
Nuclear radiation
Physics
Physics and Astronomy
Quality control
Spent reactor fuels
Radioactive Source
Spend Nuclear Fuel
Petersburg Nuclear Physic Institute
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Summary: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.
ISSN:1063-7842
1090-6525
DOI:10.1134/S1063784211080226