Results 251 to 260 of about 203,114 (300)

Hyperspectral imaging suggests potential for rapid quantification of fission products in spent nuclear fuel. [PDF]

Sci Rep
Dunphy RD, Parker AJ, Bandala M, Bennet S, Boxall C, Chard P, Cockbain N, Eaves D, Goddard D, Ma X, Taylor CJ, Wilbraham R, Zabalza J, Murray P, Joyce MJ.   +14 more
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Can fire exclusion zones enhance postfire tree regeneration? A simulation study in subalpine conifer forests. [PDF]

Ecol Appl
Keller TT, Abendroth DC, Braziunas KH, Dollinger C, Hood PR, Knowlton GJ, Seidl R, Turner MG.   +7 more
europepmc   +1 more source

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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, LUZZI, LELIO, S. Brémier, A. Schubert, P. Van Uffelen, C. T. Walker, W. Haeck, W. Goll   +7 more
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TRIGA fuel burn-up calculations and its confirmation

Nuclear 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
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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
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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, 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
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Fabrication of DUPIC fuel pellets using high burn-up spent PWR fuel

Journal of Nuclear Science and Technology, 2012
Technology for the direct usage of a spent PWR fuel in CANDU reactors (DUPIC) was developed in KAERI to reduce the amount of spent fuel. DUPIC fuel pellets were fabricated using a dry processing method to re-fabricate CANDU fuel from spent PWR fuel without any intentional separation of fissile materials or fission products.
Jung-Won Lee, Geun-Il Park, Yong Choi
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Fuel burn-up fraction in RBMK-1000 reactor

Soviet Atomic Energy, 1986
The 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, V. S. Romanenko, A. V. Zav'yalov, A. V. Krayushkin, Yu. V. Garusov, G. F. Yaroslavtsev, M. V. Shavlov   +6 more
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