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Journal Articles

SFCOMPO-2.0; An OECD NEA database of spent nuclear fuel isotopic assays, reactor design specifications, and operating data

Michel-Sendis, F.*; Gauld, I.*; Martinez, J. S.*; Alejano, C.*; Bossant, M.*; Boulanger, D.*; Cabellos, O.*; Chrapciak, V.*; Conde, J.*; Fast, I.*; et al.

Annals of Nuclear Energy, 110, p.779 - 788, 2017/12

 Times Cited Count:58 Percentile:99.17(Nuclear Science & Technology)

Journal Articles

Issues in three-dimensional depletion analysis of measured data near the end of a fuel rod

DeHart, M. D.*; Gauld, I. C.*; Suyama, Kenya

Transactions of the American Nuclear Society, 99(1), p.663 - 666, 2008/11

It is becoming possible to use three dimension depletion calculation codes owing to the high speed computers in recent years and development of the sophisticated calculation method. In the past, evaluation of the depletion calculation codes has been carried out by the analysis of the isotopic composition data obtained by the Post Irradiation Examination from the positions which are suitable for one or two dimensional calculation method. For the analyses of isotopic composition data from the end region of fuel rods, we need other information of surrounding regions. This paper describes this problem based on the three dimensional depletion calculation.

Journal Articles

Three-dimensional depletion analysis of the axial end of a Takahama fuel rod

DeHart, M. D.*; Gauld, I. C.*; Suyama, Kenya

Proceedings of International Conference on the Physics of Reactors, Nuclear Power; A Sustainable Resource (PHYSOR 2008) (CD-ROM), 9 Pages, 2008/09

Recent developments in spent fuel characterization methods have involved the development of several three-dimensional depletion algorithms based on Monte Carlo methods for the transport solution. However, most validation done to-date has been based on radiochemical assay data for spent fuel samples selected from locations in fuel assemblies that can be easily analyzed using two-dimensional depletion methods. This paper reports on the results of three-dimensional depletion calculations performed using the T6-DEPL depletion sequence of the SCALE 5.1 code system, which couples the KENO-VI Monte Carlo transport solver with the ORIGEN-S depletion and decay code, for a spent fuel sample that was extracted from the end region of the fuel rod.

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