Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Spent fuel simulation during dry storage via enhancement of FRAPCON-4.0: Comparison between PWR and SMR and discharge burnup effect

  • Dahyeon Woo (Department of Nuclear Eng., Seoul National Univ.) ;
  • Youho Lee (Department of Nuclear Eng., Seoul National Univ.)
  • Received : 2022.04.28
  • Accepted : 2022.08.08
  • Published : 2022.12.25
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Abstract

Spent fuel behavior of dry storage was simulated in a continuous state from steady-state operation by modifying FRAPCON-4.0 to incorporate spent fuel-specific fuel behavior models. Spent fuel behavior of a typical PWR was compared with that of NuScale Power Module (NPMTM). Current PWR discharge burnup (60 MWd/kgU) gives a sufficient margin to the hoop stress limit of 90 MPa. Most hydrogen precipitation occurs in the first 50 years of dry storage, thereby no extra phenomenological safety factor is identified for extended dry storage up to 100 years. Regulation for spent fuel management can be significantly alleviated for LWR-based SMRs. Hydride embrittlement safety criterion is irrelevant to NuScale spent fuels; they have sufficiently lower plenum pressure and hydrogen contents compared to those of PWRs. Cladding creep out during dry storage reduces the subchannel area with burnup. The most deformed cladding outer diameter after 100 years of dry storage is found to be 9.64 mm for discharge burnup of 70 MWd/kgU. It may deteriorate heat transfer of dry storage by increasing flow resistance and decreasing the view factor of radiative heat transfer. Self-regulated by decreasing rod internal pressure with opening gap, cladding creep out closely reaches the saturated point after ~50 years of dry storage.

Keywords

Acknowledgement

This work was supported by the Nuclear Safety Research Program through the Korea Foundation Of Nuclear Safety (KoFONS) using the financial resource granted by the Nuclear Safety and Security Commis-sion (NSSC) of the Republic of Korea [No.2003018] (50%). This work was supported by the Nuclear Safety Research Program through the Ministry of Trade, Industry and Energy (MOTIE) using the financial resource granted by the institute for Korea Spent Nuclear Fuel (iKSNF) of the Republic of Korea [No.2021040101002A] (50%).

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