Results 231 to 240 of about 8,761,998 (286)

High-fidelity CNN-based surrogate modeling for wildfire spread forecasting. [PDF]

open access: yesSci Rep
Nematshahi S   +4 more
europepmc   +1 more source

TRIGA fuel burn-up calculations and its confirmation

open access: yesNuclear Engineering and Design, 2010
Abstract 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
openaire   +2 more sources

Fuel burn-up in nuclear reactors

The Soviet Journal of Atomic Energy, 1956
The 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
openaire   +1 more source

Change of fuel-to-cladding gap width with the burn-up in FBR MOX fuel irradiated to high burn-up

Journal of Nuclear Materials, 2004
In 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
openaire   +1 more source

Extension and validation of the TRANSURANUS burn-up model for helium production in high burn-up LWR fuels

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
openaire   +1 more source

Experimental burn-up analysis of ITU Triga Mark II reactor fuel elements

open access: yesNuclear Engineering and Design
In this study, burn-up values ​​of spent fuels were determined using Non-Destructive Analysis (NDA) with the help of 137Cs burn-up indicator. Four spent fuel elements (F30, D18, B5 and E14) that burned in the core of the Istanbul Technical University ...
Tayfun Akyürek   +2 more
exaly   +2 more sources

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