Radiation Physics and Engineering
A peer-reviewed journal published by K. N. Toosi University of Technology

Investigation of required modifications of the manufactured TRR DPC for transport and storage of two-year cooled spent fuel assemblies

Articles in Press

Document Type : Research Article

Authors

Behrooz Rokrok
Zohreh Gholamzadeh
Atiyeh Jozvaziri
Ebrahim Abedi

Reactor and Nuclear Safety School‎, ‎Nuclear Science and Technology Research Institute‎, ‎Tehran‎, ‎Iran

https://doi.org/10.22034/rpe.2026.558815.1320
Abstract
Dual-purpose cask (DPC) is used for transporting and interim storage of spent fuel assemblies, since such casks are an attractive option due to their flexibility and economy efficiency. In point of economical view, construction of high-capacity DPC is more suitable. The cask could be used to transport the spent fuel assemblies of long cooling time with its full capacity. At emergency situations the same cask potentially could be used to transport the spent fuels with short cooling time using some modifications inside the canister. The present study would investigate the highest capacity of Tehran Research Reactor (TRR) DPC for transport and storage of 2-year cooled spent fuel assemblies. MCNPX2.7.0 computational code was used to calculate the DPC body maximum gamma and neutron dose rates. The obtained results showed that maximum six 2-year cooled SFAs of TRR could be transported by the present DPC. Moreover, filling the empty places of canister with carbon-steel shield blocks, some modifications on the cask door and floor is needed to pass the determined gamma dose rate limit (2 mSv.h-1). By adding 6 cm thick carbon-steel on the DPC door and its bottom the goal is obtained while the modifications increase the cask weight about 1 ton.

Highlights

  • Dual-purpose cask (DPC) is used for transporting and interim storage of spent fuel assemblies.
  • Computational methods help to estimate gamma dose rates before high cost design and constructions.
  • Gamma dose rates should be calculated to optimum the cask shield material thickness.
  • Measurements help to benchmark the carried out simulations.

Keywords

Dry storage
Nuclear spent fuel
Short cooling time
DPC cask
MCNP simulation
Subjects

Copyright
RPE is licensed under a Creative Commons Attribution-NonCommercial 4.0 International License (CC BY-NC 4.0).

Conflict of Interest
The authors declare no potential conflict of interest regarding the publication of this work‎.

Funding
‎The authors declare that no funds‎, ‎grants‎, ‎or other financial support were received during the preparation of this manuscript‎.

Radiation Physics and Engineering

Articles in Press, Accepted Manuscript
Available Online from 10 May 2026

  • Receive Date 10 November 2025
  • Revise Date 07 January 2026
  • Accept Date 06 May 2026

Home

Submit Manuscript

Reviewers

Contact Us