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

Thermal Evaluation of a Dual Purpose Cask for Bushehr Nuclear Reactor Spent Fuels Under Normal Conditions

Document Type : Research Paper

Authors

M Rezaeian
J Kamali
S.J Ahmadi
https://doi.org/10.24200/nst.2019.745
Abstract
Dual purpose cask system is one of the most important developing systems of dry interim storage of nuclear spent fuels. Thermal evaluation of a dual purpose cask designed for transport and interim storage of spent fuels of Bushehr Nuclear Power Plant is carried out as appears in this paper. SolidWorks and ANSYS Workbench 15 are utilized for the modeling and thermal simulation of the cask under normal condition of transport, as well as, normal condition of interim storage, respectively. According to the results, the maximum temperature of the fuel cladding will not exceed the allowed limits and the fuel integrity will be maintainel. Furthermore, the temperatures of the other components are predicted in the range of allowed limits, demonstrating the safety of the cask under the normal conditions based on the IAEA safety standards.

Highlights

[1] International Atomic Energy Agency, Operation and Maintenance of Spent Fuel Storage and Transportation Casks/Containers, IAEA-TECDOC 1532, (2007).

 

[2] M. Bunn, J.P. Holdren, A. Macfarlane, S.E. Pickett, A. Suzuki, T. Suzuki, J. Weeks, Interim Storage of Spent Nuclear Fuel, A Safe, Flexible, and Cost-Effective Near-Term Approach to Spent Fuel Management, A Joint Report from the Harvard University Project on Managing the Atom and the University of Tokyo Project on Sociotechnics of Nuclear Energy, (2001).

 

[3] Massachusetts Institute of Technology, The Future of Nuclear Fuel Cycle, An Interdisciplinary MIT Study, (2011).

 

[4] A. Carnesale, Recommendations by the Blue Ribbon Commission on America's Nuclear Future, A Plan for Managing Spent Nuclear Fuel and High-Level Nuclear Waste, The Bridge, National Academy of Engineering, (2012).

 

[5] International Atomic Energy Agency, Storage of spent nuclear fuel, IAEA Specific Safety Guide (No. SSG-15), (2012).

 

[6] International Atomic Energy Agency, Regulations for the Safe Transport of Radioactive Material, IAEA Safety Standards, Specific Safety Requirements (No. SSR-6), (2012).

 

[7] M. Chiguer, A. Froment, F. Lelievre, Rethinking Used Fuel Management, A Post-Fukushima Perspective, European Nuclear Society Conference, United Kingdom, Manchester, September, (2012).

 

[8] D. Metaly, B.J. Garrick, N. Mote, Management of Radioactive Waste, A Socio-Technical Challenge, The Bridge, National Academy of Engineering, (2012).

 

[9] M. Rezaeian, Criticality, Shielding, Thermal, and Mechanical Design of a Dual-purpose Cask for Spent (Used) Fuels of Bushehr Nuclear Power Plant, Ph.D. Thesis, Nuclear Science and Technology Research Institue, (2016).

 

[10] M. Rezaeian, J. Kamali, Basket criticality design of a dual purpose cask for VVER 1000 spent fuel assemblies, Kerntechnik., 81 (2016). 

 

[11] M. Rezaeian, J. Kamali, Effect of a dual-purpose cask payload increment of spent fuel assemblies from VVER 1000 Bushehr Nuclear Power Plant on basket criticality, Applied Radiation and Isotopes, 119 (2017).

 

[12] BNPP FSAR: Safety Analysis Report for the Bushehr Nuclear Power Plant, State Research, Design and Engineering Survey Institute, Atomenergo-ergoproekt, Moscow, (2003).

 

[13] M. Rezaeian, J. Kamali, Radioactive Source Specification of Bushehr's VVER-1000 Spent Fuels, Science and Technology of Nuclear Installations, (2016).

 

[14] ANSYS Inc., ANSYS Workbench V15 Manual, (2014).

 

[15] Y. Xu, J. Yang, C. Xu, W. Wang, Z. Ma, Thermal analysis on NAC-STC spent fuel transport cask under different transport conditions, Nucl. Eng. Des., 265 (2013) 682– 690

 

[16] International Atomic Energy Agency, Advisory Material for the IAEA Regulations for the Safe Transport of Radioactive Material (2012 Edition), IAEA Specific Safety Guide (No. SSG-26), (2014).

 

[17] F. P. Incropera, D. P. DeWitt, Introduction to Heat Transfer, 3rd Edition, Wiley, (2000).

Keywords

Dual Purpose Cask
Thermal Evaluation
Nuclear Spent Fuel
Bushehr Nuclear Reactor
[1] International Atomic Energy Agency, Operation and Maintenance of Spent Fuel Storage and Transportation Casks/Containers, IAEA-TECDOC 1532, (2007).
 
[2] M. Bunn, J.P. Holdren, A. Macfarlane, S.E. Pickett, A. Suzuki, T. Suzuki, J. Weeks, Interim Storage of Spent Nuclear Fuel, A Safe, Flexible, and Cost-Effective Near-Term Approach to Spent Fuel Management, A Joint Report from the Harvard University Project on Managing the Atom and the University of Tokyo Project on Sociotechnics of Nuclear Energy, (2001).
 
[3] Massachusetts Institute of Technology, The Future of Nuclear Fuel Cycle, An Interdisciplinary MIT Study, (2011).
 
[4] A. Carnesale, Recommendations by the Blue Ribbon Commission on America's Nuclear Future, A Plan for Managing Spent Nuclear Fuel and High-Level Nuclear Waste, The Bridge, National Academy of Engineering, (2012).
 
[5] International Atomic Energy Agency, Storage of spent nuclear fuel, IAEA Specific Safety Guide (No. SSG-15), (2012).
 
[6] International Atomic Energy Agency, Regulations for the Safe Transport of Radioactive Material, IAEA Safety Standards, Specific Safety Requirements (No. SSR-6), (2012).
 
[7] M. Chiguer, A. Froment, F. Lelievre, Rethinking Used Fuel Management, A Post-Fukushima Perspective, European Nuclear Society Conference, United Kingdom, Manchester, September, (2012).
 
[8] D. Metaly, B.J. Garrick, N. Mote, Management of Radioactive Waste, A Socio-Technical Challenge, The Bridge, National Academy of Engineering, (2012).
 
[9] M. Rezaeian, Criticality, Shielding, Thermal, and Mechanical Design of a Dual-purpose Cask for Spent (Used) Fuels of Bushehr Nuclear Power Plant, Ph.D. Thesis, Nuclear Science and Technology Research Institue, (2016).
 
[10] M. Rezaeian, J. Kamali, Basket criticality design of a dual purpose cask for VVER 1000 spent fuel assemblies, Kerntechnik., 81 (2016). 
 
[11] M. Rezaeian, J. Kamali, Effect of a dual-purpose cask payload increment of spent fuel assemblies from VVER 1000 Bushehr Nuclear Power Plant on basket criticality, Applied Radiation and Isotopes, 119 (2017).
 
[12] BNPP FSAR: Safety Analysis Report for the Bushehr Nuclear Power Plant, State Research, Design and Engineering Survey Institute, Atomenergo-ergoproekt, Moscow, (2003).
 
[13] M. Rezaeian, J. Kamali, Radioactive Source Specification of Bushehr's VVER-1000 Spent Fuels, Science and Technology of Nuclear Installations, (2016).
 
[14] ANSYS Inc., ANSYS Workbench V15 Manual, (2014).
 
[15] Y. Xu, J. Yang, C. Xu, W. Wang, Z. Ma, Thermal analysis on NAC-STC spent fuel transport cask under different transport conditions, Nucl. Eng. Des., 265 (2013) 682– 690
 
[16] International Atomic Energy Agency, Advisory Material for the IAEA Regulations for the Safe Transport of Radioactive Material (2012 Edition), IAEA Specific Safety Guide (No. SSG-26), (2014).
 
[17] F. P. Incropera, D. P. DeWitt, Introduction to Heat Transfer, 3rd Edition, Wiley, (2000).

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