Verifying calculation of the radioactive shielding of the cylindrical canister designed to convey SPRR-300 spent fuel assemblies

Аннотация

The paper presented the detailed calculation of the radioactive shielIn the cylindrical canister designed to convey SPRR-300 spent fuel assemblies on the basis of their actual measurements, with the dose rates are given at different intervals for shielded and unshielded spent fuel assemblies. The appropriateness of the thickness of the canister is shown by the calculation, along with the experimental operation is followed.

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