The fuel pellet-cladding interaction (PCI) of liquid-metal fast breeder reactor (LMFBR) fuel elements or fuel rods at unsteady state is analyzed and discussed based on experimental results. In the analyses, the heat generation, fuel restructuring, temperature distribution, gap conductance, irradiation swelling, irradiation creep, fuel burnup, fission gas release, fuel pellet cracking, crack healing, cladding cracking, yield failure and fracture failure of the fuel elements are taken into consideration. To improve the sintered (U,Pu)O2 fuel performance and reactor core safety at high temperature and fuel burnup, it is desirable to (a) increase and maintain the ductility of cladding material, (b) provide sufficient gap thickness and plenum space for accommodating fission gas release, (c) keep ramps-power increase rate slow and gentle, and (d) reduce the intensity and frequency of transient PCI in order to avoid intense stress fatigue cracking (SFC) and stress corrosion cracking (SCC) due to fission product compounds CsI, CdI2, Cs2Te, etc. at the inner cladding surface of the fuel elements during PCI.
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October 1981
This article was originally published in
Journal of Engineering for Power
Research Papers
Pellet-Cladding Interaction of LMFBR Fuel Elements at Unsteady State: An Introduction to Computer Code ISUNE-5
B. M. Ma
B. M. Ma
Dept. of Nuclear Engineering and Engineering Research Institute, Iowa State University, Ames, Iowa
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B. M. Ma
Dept. of Nuclear Engineering and Engineering Research Institute, Iowa State University, Ames, Iowa
J. Eng. Power. Oct 1981, 103(4): 627-636 (10 pages)
Published Online: October 1, 1981
Article history
Received:
April 4, 1980
Online:
September 28, 2009
Citation
Ma, B. M. (October 1, 1981). "Pellet-Cladding Interaction of LMFBR Fuel Elements at Unsteady State: An Introduction to Computer Code ISUNE-5." ASME. J. Eng. Power. October 1981; 103(4): 627–636. https://doi.org/10.1115/1.3230785
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