Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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FRAPCON analysis of cladding performance during dry storage operations

  • Richmond, David J. (PNNL) ;
  • Geelhood, Kenneth J. (PNNL)
  • Received : 2017.11.21
  • Accepted : 2018.01.17
  • Published : 2018.03.25
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Abstract

There is an increasing need in the United States and around the world to move used nuclear fuel from wet storage in fuel pools to dry storage in casks stored at independent spent fuel storage installations or interim storage sites. Under normal conditions, the Nuclear Regulatory Commission limits cladding temperature to $400^{\circ}C$ for high-burnup (>45 GWd/mtU) fuel, with higher temperatures allowed for low-burnup fuel. An analysis was conducted with FRAPCON-4.0 on three modern fuel designs with three representative used nuclear fuel storage temperature profiles that peaked at $400^{\circ}C$. Results were representative of the majority of US light water reactor fuel. They conservatively showed that hoop stress remains below 90 MPa at the licensing temperature limit. Results also show that the limiting case for hoop stress may not be at the highest rod internal pressure in all cases but will be related to the axial temperature and oxidation profiles of the rods at the end of life and in storage.

Keywords

References

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Cited by

  1. Improvement of delayed hydride cracking assessment of PWR spent fuel during dry storage vol.52, pp.3, 2018, https://doi.org/10.1016/j.net.2019.07.036