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Reprocessing problems associated with the increasing burn-up of future fuels
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Fuel burn-up in nuclear reactors
The Soviet Journal of Atomic Energy, 1956The paper describes the method of calculating fuel burn-up in nuclear reactors, taking into account the capture and multiplication of neutrons while slowing down. In the calculations, account is taken of the burn-up of U235 and the build-up and burn-up of Np239, Pu239, Pu240, Pu241 and of the fission fragments.
B. L. Ioffe, L. B. Okun
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Change of fuel-to-cladding gap width with the burn-up in FBR MOX fuel irradiated to high burn-up
Journal of Nuclear Materials, 2004In order to study the dependence of the gap width change on the burn-up, the fuel-to-cladding gap widths were investigated by ceramography in a large number of FBR MOX fuel pins irradiated to high burn-up. The dependence of gap widths on the burn-up was closely connected with the formations of JOG (joint oxyde-gaine) and rim structure.
Koji Maeda, Takeo Asaga
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Journal of Nuclear Materials, 2011
Abstract The TRANSURANUS burn-up model (TUBRNP) calculates the local concentration of the actinides, the main fission products, and 4He as a function of the radial position across a fuel rod. In this paper, the improvements in the helium production model as well as the extensions in the simulation of 238–242Pu, 241Am, 243Am and 242–245Cm isotopes are
P. Botazzoli +7 more
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Abstract The TRANSURANUS burn-up model (TUBRNP) calculates the local concentration of the actinides, the main fission products, and 4He as a function of the radial position across a fuel rod. In this paper, the improvements in the helium production model as well as the extensions in the simulation of 238–242Pu, 241Am, 243Am and 242–245Cm isotopes are
P. Botazzoli +7 more
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Radiochemistry, 2012
A sample of WWER-1000 spent nuclear fuel (SNF) with the burn-up of approximately 50 GW day (t U)−1 was studied by methods of destructive analysis. Data on the content of isotopes of U, Pu, Am, Cm, Nd, and Cs are given. The methods used are briefly described.
E. R. Petrov +6 more
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A sample of WWER-1000 spent nuclear fuel (SNF) with the burn-up of approximately 50 GW day (t U)−1 was studied by methods of destructive analysis. Data on the content of isotopes of U, Pu, Am, Cm, Nd, and Cs are given. The methods used are briefly described.
E. R. Petrov +6 more
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TRIGA fuel burn-up calculations and its confirmation
Nuclear Engineering and Design, 2010Abstract The Cesium (Cs-137) isotopic concentration due to irradiation of TRIGA Fuel Elements FE(s) is calculated and measured at the Atominstitute (ATI) of Vienna University of Technology (VUT). The Cs-137 isotope, as proved burn-up indicator, was applied to determine the burn-up of the TRIGA Mark II research reactor FE.
R. Khan, S. Karimzadeh, H. Böck
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A study on the burn-up characteristics of inert matrix fuels
Progress in Nuclear Energy, 2015Abstract Proper disposal of minor actinides (MA), long-lived fission products (LLFPs), and transuranium element (TRU) plays a key role in the sustainable development of fission nuclear power. Adoption of inert matrix fuels (IMFs) can effectively reduce the amount of 237 Np and Np element in the spent fuel of present-day commercial power reactors. In
Tao Yu +6 more
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Phase characterisation of simulated high burn-up UO2 fuel
Journal of Alloys and Compounds, 1998Abstract To determine the lattice constant variation with burn-up and the oxidation behaviour at high temperatures, simulated UO2-spent fuels with burn-ups up to 200 GWd tM−1 were prepared by cold pressing and sintering and characterised by X-ray diffraction analysis and thermogravimetry.
J Cobos +3 more
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Fuel burn-up fraction in RBMK-1000 reactor
Soviet Atomic Energy, 1986The authors calculate fuel burnup fractions for the four RBMK reactors of the Leningrad plant for both unloaded and loaded fuel and graph the predicted dependence of average burnup for both scenarios on reactor operation time, the distribution function for a steady-state mode of continuous fuel recharging, and a histogram of fuel element distribution ...
A. P. Eperin +6 more
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Rapid Determination of Burn-Up of Nuclear Fuel—a Possible Approach
Separation Science and Technology, 1988Abstract High performance liquid chromatography (HPLC) has been used for the separation and estimation of light rare earths by making use of an anion exchanger or a dynamically modified reverse phase column as a cation exchanger. Both these methods were studied and relative performance was assessed from the point of view of their suitability for the ...
D. Karunasagar +3 more
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