Probabilistic approach for decay heat uncertainty estimation using URANIE platform and MENDEL depletion code

Tsilanizara, A.; Gilardi, Nicolas; Huynh, T.D.; Jouanne, C.; Lahaye, Sébastien; Martinez, Jean-Marc; Diop, Cheikh M’Backé

doi:10.1016/j.anucene.2015.11.027

Cited by 6 publications

(4 citation statements)

References 12 publications

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“…The mass and isotopic yields of the fission products have a direct influence on the amount of neutron poisons that limit the fuel burnup and on the evaluation of the residual power of the reactor after shutdown [1,2]. The fission yields of the plutonium nuclides are also mandatory for the studies on the fuel multi-recycling [3].…”

Section: Introductionmentioning

confidence: 99%

Measurements of Fission Products Yields with the LOHENGRIN mass spectrometer at ILL

Chebboubi¹,

Julien-Laferrière²,

Nicholson³

et al. 2020

EPJ Web Conf.

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The CEA in collaboration with ILL and LPSC has developed a measurement program on symmetric and heavy mass fission product distributions. The combination of measurements with ionisation chamber and Ge detectors is necessary to describe precisely the heavy fission product region in mass and charge. Recently, new measurements of fission yields and kinetic energy distributions, for different fissioning systems (233,235 U(nth, f),241 Am(2nth, f) and 239,241 Pu(nth, f), were performed with recoil spectrometer LOHENGRIN. The focus has been done on the self-normalization of the data to provide new absolute measurements, independently of any libraries along with the experimental covariance matrix. To reach precise measurements, a new experimental procedure was developed along with a new analysis method.

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Section: Introductionmentioning

confidence: 99%

Measurements of Fission Products Yields with the LOHENGRIN mass spectrometer at ILL

Chebboubi¹,

Julien-Laferrière²,

Nicholson³

et al. 2020

EPJ Web Conf.

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“…Uncertainty quantification in MENDEL is based on a propagation method using a Monte Carlo approach by correlated sampling [9], and sampling is done by the CEA uncertainty platform URANIE [10,11]. Nuclear data uncertainties are propagated to physical quantities of interest (such as decay heat or concentrations) [12].…”

Section: Introductionmentioning

confidence: 99%

Choice of positive distribution law for nuclear data

Lahaye

2018

EPJ Nuclear Sci. Technol.

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Nuclear data evaluation files in the ENDF6 format provide mean values and associated uncertainties for physical quantities relevant in nuclear physics. Uncertainties are denoted as D in the format description, and are commonly understood as standard deviations. Uncertainties can be completed by covariance matrices. The evaluations do not provide any indication on the probability density function to be used when sampling. Three constraints must be observed: the mean value, the standard deviation and the positivity of the physical quantity. MENDEL code generally uses positively truncated Gaussian distribution laws for small relative standard deviations and a lognormal law for larger uncertainty levels (>50%). Indeed, the use of truncated Gaussian laws can modify the mean and standard deviation value. In this paper, we will make explicit the error in the mean value and the standard deviation when using different types of distribution laws. We also employ the principle of maximum entropy as a criterion to choose among the truncated Gaussian, the fitted Gaussian and the lognormal distribution. Remarkably, the difference in terms of entropy between the candidate distribution laws is a function of the relative standard deviation only. The obtained results provide therefore general guidance for the choice among these distributions.*

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“…For example, the depletion solvers of MENDEL are currently used in the deterministic transport code APOLLO3 ® [18] and in the Monte Carlo transport code TRIPOLI-4 ® , in order to perform depletion calculations. Recently, a new capability has been added to handle the propagation of the nuclear data uncertainties by a probabilistic approach [8] based on URANIE [19], the CEA uncertainty and sensitivity platform.…”

Section: Mendelmentioning

confidence: 99%

“…In this context, CEA develops his own SDR scheme with its codes TRIPOLI-4 ® [7] and MENDEL [8]. This development is supported by a EUROfusion [9] task: Monte Carlo code development.…”

Section: Introductionmentioning

confidence: 99%

Rigorous-two-Steps scheme of TRIPOLI-4® Monte Carlo code validation for shutdown dose rate calculation

et al. 2017

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Abstract.After fission or fusion reactor shutdown the activated structure emits decay photons. For maintenance operations the radiation dose map must be established in the reactor building. Several calculation schemes have been developed to calculate the shutdown dose rate. These schemes are widely developed in fusion application and more precisely for the ITER tokamak. This paper presents the rigorous-two-steps scheme implemented at CEA. It is based on the TRIPOLI-4 ® Monte Carlo code and the inventory code MENDEL. The ITER shutdown dose rate benchmark has been carried out, results are in a good agreement with the other participant.

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Probabilistic approach for decay heat uncertainty estimation using URANIE platform and MENDEL depletion code

Cited by 6 publications

References 12 publications

Measurements of Fission Products Yields with the LOHENGRIN mass spectrometer at ILL

Measurements of Fission Products Yields with the LOHENGRIN mass spectrometer at ILL

Choice of positive distribution law for nuclear data

Rigorous-two-Steps scheme of TRIPOLI-4® Monte Carlo code validation for shutdown dose rate calculation

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