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This research aims to improve nuclear safety analysis by assessing the activation and radiation levels of spent fuel assemblies.

Activation analysis and shielding design of spent fuel assemblies

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This research aims to improve nuclear safety analysis by assessing the activation and radiation levels of spent fuel assemblies.
Utilized a coupling method of Monte Carlo code and fuel depletion code for calculation.
Analyzed historical nuclide depletion and radioactivity of detectors in spent fuel assemblies.
Evaluated dose rate distribution after three years of cooling without shielding.
The calculated dose rate at 30 cm from the assembly surface drops below 1 mSvh-1 after 3 years of cooling.
Results align closely with actual measurements, with an acceptable error margin.
Proposed a shielding design scheme based on findings to enhance radiation protection.

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Randomized trial evaluates dose rates in spent fuel assemblies, suggesting improved shielding design.

Yan et al. (2026) studied this question.

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