English (United Kingdom)

https://curated-unify.zendy.io/wp-json/zendy-region/v1/featured_content/oa?rat=en

https://curated-unify.zendy.io/wp-json/zendy-region/v1/highlighted_journal/

Global: Zendy Plus annual

Presents the access of premium content as premium feature

Premium Content

Presents the keyphrase highlighting as premium feature

Keyphrase Highlighting

Presents the summarisation as premium feature

Summarisation

Insights

Presents the pdf analysis as premium feature

PDF Analysis

Presents the zaia usage as premium feature

ZAIA

Global: Zendy Plus monthly

Global: Zendy Tools annual

Global: Zendy Tools monthly

Global: Zendy Free Plan

Nuclear power is a significant source of electricity in the United States,but the average U.S. nuclear power plant is around 40 years old. Safemanagement of spent nuclear fuel (SNF) is a crucial aspect of the back end ofthe nuclear fuel cycle. SNF dry storage systems are increasingly popular asthey represent an effective solution in this area, given the absence of a finaldisposal system. In particular, the spent fuel cask system (dry cask method)provides a feasible solution for maintaining SNF ($\sim$60 years) prior to thefinal disposal. The HI-STORM overpack and MPC-32 canister are the primarycomponents of the HI-STORM 100 dry cask storage system. They remove heat fromthe system via natural circulation with no human intervention required. Thischaracteristic provides passive heat removal while requiring little maintenancein dry cask storage systems. This project aims to validate and compare thecapabilities of a thermal model of HI-STORM overpack developed using theMultiphysics Object-Oriented Simulation Environment (MOOSE) based on theauthor's previous study. MOOSE is an open-source framework developed by IdahoNational Laboratory for multiscale, multiphysics simulations. This study willimprove the capabilities of the thermal-hydraulic model of the HI-STORM drycask storage system by producing high-fidelity results for the air circulationin the overpack. Large Eddy Simulations (LES) are performed using theopen-source spectral element code NekRS, developed by Argonne NationalLaboratory (ANL), for simulating transitional and turbulent flows in complexgeometries. NekRS will produce high-fidelity results for the HI-STORM overpackto assess the validity of the current thermal-hydraulic model.

Validation and Comparison of HI-STORM Overpack Thermal-Hydraulic Model with MOOSE and NekRS