Nuclear Physics and Atomic Energy

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Nuclear Physics and Atomic Energy

  ISSN: 1818-331X (Print), 2074-0565 (Online)
  Publisher: Institute for Nuclear Research of the National Academy of Sciences of Ukraine
  Languages: Ukrainian, English
  Periodicity: 4 times per year

  Open access peer reviewed journal


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Nucl. Phys. At. Energy 2007, volume 8, issue 1, pages 89-94.
Section: Atomic Energy.
Received: 21.06.2006; Published online: 30.03.2007.
PDF Full text (en)
https://doi.org/10.15407/jnpae2007.01.089

Cask size and weight reduction through the use of depleted uranium dioxide-concrete material

S. Y. Lobach1, J. M. Haire2

1Oregon State University, USA
2Oak Ridge National Laboratory, USA

Abstract: Newly developed depleted uranium (DU) composite materials enable fabrication of spent nuclear fuel (SNF) transport and storage casks that are smaller and lighter in weight than casks made with conventional materials. One such material is DU dioxide (DUO2)-concrete, so-called DUCRETETM. This paper examines the radiation shielding efficiency of DUCRETE as compared with that of a conventional concrete cask that holds 32 pressurized-water-reactor SNF assemblies. In this analysis, conventional concrete shielding material is replaced with DUCRETE. The thickness of the DUCRETE shielding is adjusted to give the same radiation surface dose, 200 mrem/h (2 mSv/hr), as the conventional concrete cask. It was found that the concrete shielding thickness decreased from 71 to 20 cm and that the cask radial cross-section shielding area was reduced ∼50%. The weight was reduced ∼21%, from 154 to ∼127 tons. Should one choose to add an extra outer ring of SNF assemblies, the number of such assemblies would increase from 32 to 52. In this case, the outside cask diameter would still decrease, from 169 to 137 cm. However, the weight would increase somewhat from 156 to 177 tons. Neutron cask surface dose is only ∼10% of the gamma dose. These reduced sizes and weights will significantly influence the design of next-generation SNF casks.

References:

1. Haire M. J., Swaney P. M. Cask Size and Weight Reduction Through the Use of Depleted uranium Dioxide (DUO2)-Steel Cermet Material. Waste Management 2005 Symposium, Tucson, Arizona, February 27 - March 3, 2005 (Waste Management Symposia, Inc., 2005).

2. Alekseev O. G., Matveev V. Z., Morenko A. I. et al. Estimation of Terrorist Attack Resistibility of Dual-Purpose Cask TP-117 with DU (Depleted Uranium) Gamma Shield. 14th Int. Symp. on the Packaging and Transportation of Radioactive Materials, Berlin, Germany, Sept. 20 - 24, 2004 (PATRAM 2004 Conference Agency, 2005).

3. SCALE: A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluations, NUREG/CR-0200, Rev. 6 (ORNL/NUREG/CSD-2/R6), Vols. I, II, and III (May 2000). Available from Radiation Safety Information Computational Center at Oak Ridge National Laboratory as CCC-545.