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An Inline Burn-up Algorithm: Proposal and Preliminary Analysis
International Conference on Physics of Reactors 2022 (PHYSOR 2022), 2022A new burn-up algorithm is proposed for coupling neutronics and isotopic depletion. The algorithm is analogous to those proposed for enforcing xenon equilibrium and converging neutronics and thermal-hydraulics. During the corrector step of standard predictor-corrector methods, the corrector nuclide density is updated as neutronics converges.
Cosgrove, Paul +2 more
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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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Extension of the TRANSURANUS burn-up model
Journal of Nuclear Materials, 2008The validation range of the model in the TRANSURANUS fuel performance code for calculating the radial power density and burnup in UO2 fuel has been extended from 64 MWd/kgHM up to 102 MWd/kgHM, thereby improving also its precision. In addition, the first verification of calculations with post-irradiation examination data is reported for LWR-MOX fuel ...
A. Schubert +4 more
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2016
Taking the reader on an ethnographic tour of the melon harvesting fields during a historic heat wave in Fresno County, this chapter provides a close-up examination of how the organization of labor crews forces migrant farmworkers to privilege their work about their health. It shows that subcontracting intensifies the labor demands placed on field hands
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Taking the reader on an ethnographic tour of the melon harvesting fields during a historic heat wave in Fresno County, this chapter provides a close-up examination of how the organization of labor crews forces migrant farmworkers to privilege their work about their health. It shows that subcontracting intensifies the labor demands placed on field hands
openaire +1 more source
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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The REBUS Experimental Programme for Burn-Up Credit
12th International Conference on Nuclear Engineering, Volume 3, 2004An international programme called REBUS for the investigation of the burn-up credit has been initiated by the Belgian Nuclear Research Centre SCK-CEN and Belgonucle´aire with the support of EdF and IRSN from France and VGB, representing German nuclear utilities and NUPEC, representing the Japanese industry. Recently also ORNL from the U.S.
Pierre D’hondt +6 more
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