Results 131 to 140 of about 1,923 (185)
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Cladding for high performance fuel
Progress in Nuclear Energy, 2012Abstract Contemporary cladding for commercial Generation III (light water reactor) fuel is made from zirconium-based alloys. This family of materials has evolved dramatically over their ∼50 years of existence, leading to an order of magnitude improvement in corrosion resistance.
Lars Hallstadius +2 more
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Fuel/cladding compatibility in U-19Pu-10Zr/HT9-clad fuel at elevated temperatures
Journal of Nuclear Materials, 1993Abstract Twenty-five elevated-temperature tests were conducted on irradiated U-19wt%Pu-10wt%Zr fuel clad with HT9 at the Alpha-Gamma Hot Cell Facility at Argonne National Laboratory, Illinois. Samples with burnups as high as 11 at% were tested, and the cladding penetration rates all fall within the data band previously defined. Highlights of the test
A.B. Cohen, H. Tsai, L.A. Neimark
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Cladding Thickness of Fuel Elements by X-rays
Advances in X-ray Analysis, 1958AbstractThe paper is based on a feasibility study to determine the suitability of various techniques for the non-destructive measurement of cladding thickness on uranium fuel elements. The techniques studied were: 1—the attentuation of the characteristic X-ray fluorescence from the uranium base metal by the cladding material, and 2—Compton scattering ...
Beverley James Lowe +2 more
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Fuel Cladding Material and Basic Properties
2023Since the cladding is the second physical barrier to the fission product release, it is important to avoid any cladding failure; some desired characteristics of cladding in order to avoid failures and to enhance the fuel element performance are discussed in section 5.2.
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Development of Zirconium—Barrier Fuel Cladding
2010This paper was prepared for the 1991 Kroll Award. A review is presented of the development of barrier fuel. It includes the recognition of the pellet-cladding interaction (PCI) fuel failure mode and of a coordinated program to develop understanding, mitigation strategies, and a fuel that is resistant to this failure mode.
Joseph Sam Armijo +2 more
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Solution to a fuel-and-cladding rewetting model
International Communications in Heat and Mass Transfer, 1989Abstract A solution by the Wiener-Hopf technique is derived for a model for the rewetting of a nuclear fuel rod. The gap between the fuel and the cladding is modelled by an imperfect contact between the two. A constant heat transfer coefficient is assumed on the wet side, whereas the dry side is assumed to be adiabatic. The solution for the rewetting
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Fracture Predictions in Zircaloy Fuel Cladding
1985Predictions of the maximum initial allowable temperature required to achieve a 40-year life in dry storage are made for Zircaloy clad spent fuel. Maximum initial temperatures of 360 to 405°C for irradiated spent fuel cladding (wet pool storage) are predicted.
Mansoor A. Khan +2 more
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Model for Fuel/Cladding Chemical Interaction
Nuclear Technology, 1986A kinetic model of fuel/cladding chemical interaction (FCCI) has been developed. By fitting the model to in-pile experimental data, a wastage correlation has been derived that predicts corrosion depth due to FCCI. The model can explain the temperature dependency of the corrosion depth observed in the in-pile experimental data.
Kenji Konashi +2 more
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Development of Zirconium-Barrier Fuel Cladding
1994This paper was prepared for the 1991 Kroll Award. A review is presented of the development of barrier fuel. It includes the recognition of the pellet-cladding interaction (PCI) fuel failure mode and of a coordinated program to develop understanding, mitigating strategies, and a fuel that is resistant to this failure mode.
JS Armijo, LF Coffin, HS Rosenbaum
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