Extension of the TRANSURANUS burn-up model

Arndt, Sebastian; Uffelen, P. Van; Laar, J. van de; Walker, C.T.; Haeck, Wim

doi:10.1016/j.jnucmat.2008.01.006

Cited by 40 publications

(30 citation statements)

References 21 publications

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“…To confirm their correctness, the SIMS profiles for the actinide isotopes were compared with the isotope distributions calculated with the new version of the TUBRNP burn-up model of the TRAN-SURANUS code [27] and the Monte-Carlo burn-up code ALEPH [28]. The current versions of the TUBRNP model and the ALEPH code have the capability to calculate the shape of the radial isotope profile, but they cannot compute the concentration level of the isotope.…”

Section: Behaviour Of Plutonium and The Minor Actinidesmentioning

confidence: 99%

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SIMS analysis of an UO2 fuel irradiated at low temperature to 65MWd/kgHM

Walker

Stephan

Portier

et al. 2009

Journal of Nuclear Materials

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Section: Behaviour Of Plutonium and The Minor Actinidesmentioning

confidence: 99%

“…18. Comparison of the radial profiles for 237 Np, 240 Pu and 242 Cm measured by SIMS with the radial isotope distributions calculated by the TUBRNP model [27] and the ALEPH burn-up code [28].…”

Section: Behaviour Of the Fission Gases Xe And Kr In The High Burn-upmentioning

confidence: 99%

SIMS analysis of an UO2 fuel irradiated at low temperature to 65MWd/kgHM

Walker

Stephan

Portier

et al. 2009

Journal of Nuclear Materials

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“…For the present problem, various models can be used to calculate the local burn up and the isotope distributions along the radial direction. The TRANSURANUS model is very successful in the description of the local burnup and related properties in various reactors including light and heavy water reactors [8][9][10]. In TRANSURANUS model, a fixed neutron flux is assumed except for the absorption reaction of 238 U and 240 Pu [10], while the RAPID model considers detailed properties of the neutron flux at each burnup [11].…”

Section: Introductionmentioning

confidence: 99%

A Simple Formula for Local Burnup and Isotope Distributions Based on Approximately Constant Relative Reaction Rate

Yuan

Wang

Chen

2016

Science and Technology of Nuclear Installations

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A simple and analytical formula is suggested to solve the problems of the local burnup and the isotope distributions. The present method considers two extreme conditions of neutrons penetrating the fuel rod. Based on these considerations, the formula is obtained to calculate the reaction rates of 235 U, 238 U, and 239 Pu and straightforward the local burnup and the isotope distributions. Starting from an initial burnup level, the parameters of the formula are fitted to the reaction rates given by a Monte Carlo (MC) calculation. Then the present formula independently gives very similar results as the MC calculation from the starting to high burnup level, but takes just a few minutes. The relative reaction rates are found to be almost independent on the radius (except (n, γ) of 238 U) and the burnup, providing a solid background for the present formula. A more realistic examination is also performed when the fuel rods locate in an assembly. A combination of the present formula and the MC calculation is expected to have a nice balance on the accuracy and the cost on time. *

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“…The fractional fission gas release at the end of life, the variation in the fuel center temperature during the irradiation and the radial temperature gradient during the last irradiation cycle were calculated with the current version of TRANSURANUS fuel performance code (see e.g., ref. [13,14]). The calculated variation in the fuel center temperature at the axial location in 12G2 of the samples on which EPMA, SEM and LA-ICP-MS were performed is shown in Fig.…”

Section: Fuel Temperature and Fission Gas Releasementioning

confidence: 99%