Fission yields and cross section uncertainty propagation in Boltzmann/Bateman coupled problems: Global and local parameters analysis with a focus on MTR

Frosio, Thomas; Bonaccorsi, Thomas; Blaise, Patrick

doi:10.1016/j.anucene.2016.07.025

Cited by 6 publications

(19 citation statements)

References 22 publications

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“…The method used to evaluate the uncertainties comes from complete work performed in [8,9]. The complete evaluation of propagated uncertainties on neutronics parameters requires a precise knowledge of both nuclear data and manufacturing uncertainties.…”

Section: Evaluation Of the Technological Uncertaintiesmentioning

confidence: 99%

“…The benchmark used is the present paper is a Material Testing Reactor based on 20% enriched 235 UU 3 Si 2 Al fuel plates [9]. A unique type of assembly has been modelled to build the whole core.…”

Section: Benchmark Descriptionmentioning

confidence: 99%

“…Another difficulty arises here through the coupled calculation and the associated uncertainty propagation coming from direct and transmutation terms. Transmutation and direct effects can be decorrelated by doubling the number of calculations, with the methods coming from [9]. In this paper, we will use the MC method described therein with the goal to get a global sensitivity analysis.…”

Section: Statistical Distributions Of Manufacturing Parametersmentioning

confidence: 99%

“…The equations from [9] for local isotopic concentrations uncertainties are still valid then, and we resume here the theory for the sake of completeness.…”

Section: Statistical Distributions Of Manufacturing Parametersmentioning

confidence: 99%

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Manufacturing Data Uncertainties Propagation Method in Burn-Up Problems

Frosio

Bonaccorsi

Blaise

2017

Science and Technology of Nuclear Installations

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A nuclear data-based uncertainty propagation methodology is extended to enable propagation of manufacturing/technological data (TD) uncertainties in a burn-up calculation problem, taking into account correlation terms between Boltzmann and Bateman terms. The methodology is applied to reactivity and power distributions in a Material Testing Reactor benchmark. Due to the inherent statistical behavior of manufacturing tolerances, Monte Carlo sampling method is used for determining output perturbations on integral quantities. A global sensitivity analysis (GSA) is performed for each manufacturing parameter and allows identifying and ranking the influential parameters whose tolerances need to be better controlled. We show that the overall impact of some TD uncertainties, such as uranium enrichment, or fuel plate thickness, on the reactivity is negligible because the different core areas induce compensating effects on the global quantity. However, local quantities, such as power distributions, are strongly impacted by TD uncertainty propagations. For isotopic concentrations, no clear trends appear on the results.

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Section: Evaluation Of the Technological Uncertaintiesmentioning

confidence: 99%

Section: Benchmark Descriptionmentioning

confidence: 99%

Section: Statistical Distributions Of Manufacturing Parametersmentioning

confidence: 99%

“…The equations from [9] for local isotopic concentrations uncertainties are still valid then, and we resume here the theory for the sake of completeness.…”

Section: Statistical Distributions Of Manufacturing Parametersmentioning

confidence: 99%

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Manufacturing Data Uncertainties Propagation Method in Burn-Up Problems

Frosio

Bonaccorsi

Blaise

2017

Science and Technology of Nuclear Installations

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“…The method can be extended to depletion calculations and to other local parameters. In this case, sensitivities can be computed with direct perturbation methods as it is done in [1]. Then, an important quantity of Pearson coefficients can be calculated for each local quantity of interest with the second equality of equation (4).…”

Section: Introductionmentioning

confidence: 99%

Impact of correlations between core configurations for the evaluation of nuclear data uncertainty propagation for reactivity

Frosio¹,

Blaise²,

Bonaccorsi³

2017

EPJ Nuclear Sci. Technol.

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Abstract. The precise estimation of Pearsons correlations, also called "representativity" coefficients, between core configurations is a fundamental quantity for properly assessing the nuclear data (ND) uncertainties propagation on integral parameters such as k-eff, power distributions, or reactivity coefficients. In this paper, a traditional adjoint method is used to propagate ND uncertainty on reactivity and reactivity coefficients and estimate correlations between different states of the core. We show that neglecting those correlations induces a loss of information in the final uncertainty. We also show that using approximate values of Pearson does not lead to an important error of the model. This calculation is made for reactivity at the beginning of life and can be extended to other parameters during depletion calculations.

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