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Technical Paper

Surface Dose Rate Calculations of a Spent-Fuel Storage Cask by Using MAVRIC and Its Comparison with SAS4 and MCNP

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Pages 343-350 | Published online: 10 Apr 2017

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Articles from other publishers (6)

Davor Grgić, Mario Matijević, Paulina Dučkić & Radomir Ječmenica. (2022) Analysis of the HI-TRAC VW Transfer Cask Dose Rates for Spent Fuel Assemblies Loaded in Nuclear Power Plant Krsko Storage Campaign One. Journal of Nuclear Engineering and Radiation Science 8:4.
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Davor Grgic, Mario Matijevic, Paulina Duckic & Radomir Jecmenica. (2022) Radiation shielding analysis of the HI-STORM FW storage cask. Nuclear Engineering and Design 396, pages 111878.
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Y.S. Tseng, W.Y. Wang, C.H. Lin, Y.M. Ferng & M.H. Wan. (2022) Development of 3-D numerical methodology to investigate transient characteristics of fuel temperature and hydrated residual water during drying process of dry storage system. Annals of Nuclear Energy 172, pages 109083.
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Nicholas J. Quartemont, Abigail A. Bickley & James E. Bevins. (2020) Nuclear Data Covariance Analysis in Radiation-Transport Simulations Utilizing SCALE Sampler and the IRDFF Nuclear Data Library. IEEE Transactions on Nuclear Science 67:3, pages 482-491.
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Yuan Gao, Christopher R. Hughes, Christopher R. Greulich, James E. Tulenko, Andreas Enqvist & James E. Baciak. (2018) Radiation dose rate distributions of spent fuel dry casks estimated with MAVRIC based on detailed geometry and continuous-energy models. Annals of Nuclear Energy 117, pages 84-97.
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Davor Grgic, Mario Matijevic, Paulina Duckic & Radomir Jecmenica. (2022) Radiation Shielding Analysis of the Hi-Storm Fw Storage Cask. SSRN Electronic Journal.
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