Journal of Nuclear Science, Engineering and Technology (JONSAT)
In cooperation with the Iranian Nuclear Society

Heat Transfer Study of High Level Nuclear Waste Stored in Deep Underground Tunnel and Its Effect on Ground Surface Temperature

Document Type : Research Paper

Authors

H Aminfar
J Ghasemi
Abstract
Storage of high-level waste and spent fuels from nuclear reactors is a main concern in the field of nuclear engineering. Generally, deep geological repository is suggested for this purpose. Heat transfer by high-level waste and spent fuels and their impacts on environment in a deep geological repository is an important subject for study. In this paper a three dimentional model for heat transfer in canisters and a deep tunnel was developed. FLUENT 6.0 with K-ε turbulence model was used to simulate the turbulent flow with and without radiation. The influence of parameters such as heat flux, air velocity, and depth of tunnel and the ground and canisters surface temperature were studied for two cases of forced and natural convection. For the air velocity of 0.6m/s with 67 canisters in the tunnel and 360kW/m2 the initial heat flux for each canister, it is shown that the surface temperature reaches its allowed maximum limit of 93oC for concrete.

Highlights

  1. 1.    S. Moujaes and A. Bhargava, “Simulation of heat transfer around a canister placed horizontally in a drift,” Proc, Int. Conf. High Level Radioactive Waste Management, Las Vegas, Nevada, May 22-26 (1994).

 

  1. 2.     G. Danko, T.A. Buscheck, J.J. Nitao, S. Saterlie, “Analysis of near-field and psychometric waste package enviroment using ventilation,” Proc. Int. Conf. High Level Radioactive Waste Management, Las Vegas, Nevada (1995).

 

  1. 3.    A. Roald, W.P. Darrell, C. Yitung “Modeling convective heat transfer around a waste cask stored in the Yucca mountain repository,” The 6th ASME-JSME thermal engineering joint conference, U.S.A (2003).

 

  1. 4.    C. David, Wilcox, “Turbulence modeling for CFD,” DCW industries, Inc. California (1993).

 

  1. 5.    S.R. Kukatla, “Thermal transport evalutions related to waste package design,” Nevada Center for Advanced Computational Methods, University of Nevada, Las Vegas (2003).

 

  1. 6.    A. Bejan, “Convection heat transfer,” John Wiley & Sons (1984).

 

  1. 7.    W. Ahmeda, M. Arshada, Kh. Ghulam Qasimb, “Dry storage of spent KANUPP fuel and booster rod assemblies,” Institute for Nuclear Power, Islamabad & Karachi Nuclear Power Complex, Pakistan (2003).

 

  1. 8.    U.S. Nuclear Regulatory Commission “Regulatory guid 3.54- spent fuel heat generation in an Ind spent fuel storage installation,” January (1999).

 

  1. 9.     Charles W. Forsberg, “Depleted uranium dioxide as a spent-nuclear-fule waste-package particulate fill:fill behavior,” Oak Ridge National Laborator, managed by UT-Bttelle, LLC, for the U.S. Department of energy (2001).

 

10.J. William, Quapp, “An advanced solution for the storage, transportation and disposal of spent fuel and vitrified high level waste,” Teton Technologies Inc. paper presented at global99, September 2 (1999).

 

11.American Concrete Institute Standard 349, App A4, Last version (1985).

 

Keywords

Canisters
Radiation Heat Transfer
Repository of Nuclear Waste Package
Spent Nuclear Fuel (SNF)
  1. 1.    S. Moujaes and A. Bhargava, “Simulation of heat transfer around a canister placed horizontally in a drift,” Proc, Int. Conf. High Level Radioactive Waste Management, Las Vegas, Nevada, May 22-26 (1994).

 

  1. 2.     G. Danko, T.A. Buscheck, J.J. Nitao, S. Saterlie, “Analysis of near-field and psychometric waste package enviroment using ventilation,” Proc. Int. Conf. High Level Radioactive Waste Management, Las Vegas, Nevada (1995).

 

  1. 3.    A. Roald, W.P. Darrell, C. Yitung “Modeling convective heat transfer around a waste cask stored in the Yucca mountain repository,” The 6th ASME-JSME thermal engineering joint conference, U.S.A (2003).

 

  1. 4.    C. David, Wilcox, “Turbulence modeling for CFD,” DCW industries, Inc. California (1993).

 

  1. 5.    S.R. Kukatla, “Thermal transport evalutions related to waste package design,” Nevada Center for Advanced Computational Methods, University of Nevada, Las Vegas (2003).

 

  1. 6.    A. Bejan, “Convection heat transfer,” John Wiley & Sons (1984).

 

  1. 7.    W. Ahmeda, M. Arshada, Kh. Ghulam Qasimb, “Dry storage of spent KANUPP fuel and booster rod assemblies,” Institute for Nuclear Power, Islamabad & Karachi Nuclear Power Complex, Pakistan (2003).

 

  1. 8.    U.S. Nuclear Regulatory Commission “Regulatory guid 3.54- spent fuel heat generation in an Ind spent fuel storage installation,” January (1999).

 

  1. 9.     Charles W. Forsberg, “Depleted uranium dioxide as a spent-nuclear-fule waste-package particulate fill:fill behavior,” Oak Ridge National Laborator, managed by UT-Bttelle, LLC, for the U.S. Department of energy (2001).

 

10.J. William, Quapp, “An advanced solution for the storage, transportation and disposal of spent fuel and vitrified high level waste,” Teton Technologies Inc. paper presented at global99, September 2 (1999).

 

11.American Concrete Institute Standard 349, App A4, Last version (1985).

 

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