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Packaging, Transport, Storage & Security of Radioactive Material Volume 21, 2010 - Issue 3
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Articles

Thermal analysis of proposed transport cask for three advanced burner reactor used fuel assemblies

T. BullardDepartment of Mechanical Engineering University of Nevada, Reno, NV89557, USA;, Email: [email protected]
,
M. GreinerDepartment of Mechanical Engineering University of Nevada, Reno, NV89557, USA
,
M. DennisSandia National Laboratories PO Box 5800, MS 0719, Albuquerque, NM 87185, USA
,
S. BaysIdaho National Laboratory, PO Box 1625, MS 3870, Idaho Falls, ID 83403, USA
&
R. WeinerSandia National Laboratories PO Box 5800, MS 0719, Albuquerque, NM 87185, USA
Pages 158-164 | Published online: 19 Apr 2013

References

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  • Y. Chikazawa and C. Grandy: Nucl. Technol, 2009, 165, 321–332.
  • ‘Packaging and transportation of radioactive material’, 10 CFR 71, Code of Federal Regulations, US Nuclear Regulatory Commission, Washington, DC, USA, 2010.
  • E. A. Hoffman, R. N. Hill and W. S. Yang: ‘Preliminary core design studies for the advanced burner reactor over a wide range of conversion ratios’, Argonne National Laboratories Report no. ANL-AFC-177, 2006, 22, 26.
  • ‘Safety analysis report for the universal transport cask’, Revision 1, Volume 1 of 2, NAC International, Norcross, GA, USA, 2002.
  • ‘Multi-purpose canister (MPC) implementation program conceptual design phase report’, MPC Conceptual Design Report, Volume II.A, contract no. DE-AC01–91RW00134, US Department of Energy, Office of Civilian Radioactive Waste Management, Washington, DC, USA, 1993.
  • N. R. Chalasani, P. Araya and M. Greiner: ‘Benchmark of computational fluid dynamics simulations using temperatures measured within enclosed vertical and horizontal arrays of heated rods’, Nucl. Technol., 2009, 167, (3), 371–383.
  • J. C. Anderson and M. R. Feldman: ‘Thermal modeling of packages for normal conditions of transport with insolation’, Proc. ASME Heat Transf. Division, ASME HTD, 1995, 317, (2, 215223).
  • S. W. Churchill and H. H. S. Chu: Int. J. Heat Mass Transf., 1975, 18, 1049–1055.
  • ‘Consolidated safety analysis report for IF 300 shipping cask’, General Electric Uranium Management Corporation, Sunnyvale, CA, USA, 1984.

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