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DOE OSTI · 3000743

Microreactor Assembly Transportation Cask Model Description for Criticality Safety Validation Basis Assessment

Abstract

Criticality safety analyses are completed on a transportation cask used for microreactor assembly shipment to provide an example of model and analysis to industry for reproducing this type of study on their microreactor fuel shipment. The fuel assembly considered is based on a gas-cooled microreactor (GC-MR), which utilizes HALEU fuel in the form of TRISO particles and utilizes various design options considered in industry designs. Various versions of this GC-MR assembly were studied, with and without YH2 moderator, providing similar conclusions. The shipment cask design is revised based on an existing design ES-3100, developed by Y-12 for the transport of highly enriched uranium (HEU), but is enlarged to hold the GC-MR fuel assembly. Criticality safety analysis for the cask/GC-MR fuel assembly package was performed using the CSAS6 sequence of SCALE6.3.2, utilizing the ENDF/B-VII.1 based continuous energy neutron library, and the analysis strictly follows the guideline from NRC reference reports. Different scenarios, e.g. normal operation, undamaged cask with water flooded, damaged cask with optimal water moderation, have been analyzed and it could be concluded the package would always have a large margin of subcriticality even packed in an infinite array. Sensitivity and similarity analyses are also performed using the TSUNAMI sequence of SCALE6.3.2, and the similarity analysis uses all the experiments from the ICSBEP Handbook with Intermediate and Mixed Enriched Uranium (IEU) and Low Enriched Uranium (LEU) systems together with additional ones that are sponsored by the DNCSH program. These similarity analyses indicate that dry cases have no similar benchmark experiments (ck values greater than 0.8), which may become problematic if more assemblies are shipped together (or a fully loaded core is shipped) and margin to criticality is reduced. However, the damaged cask models with flooded assemblies exhibited similarities to many experiments with ck values greater than 0.8.

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BibTeXRIS

Zhong, Zhaopeng [Argonne National Laboratory (ANL), Argonne, IL (United States)], Abdelhameed, Ahmed Amin E. [Argonne National Laboratory (ANL), Argonne, IL (United States)], Stauff, Nicolas E. [Argonne National Laboratory (ANL), Argonne, IL (United States)], Celik, Cihangir [Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)]. 2025-10-21. Microreactor Assembly Transportation Cask Model Description for Criticality Safety Validation Basis Assessment. https://doi.org/10.2172/3000743

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