Work plan for improving the DARWIN2.3 depleted material balance calculation of nuclides of interest for the fuel cycle

Rizzo, Axel; Vaglio–Gaudard, C.; Martin, Julie-Fiona; Noguère, G.; Eschbach, R.

doi:10.1051/epjconf/201714609030

Cited by 4 publications

(4 citation statements)

References 7 publications

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“…DARWIN2.3 accuracy can be improved by identifying sources of biases and uncertainties [8]. In this framework, this paper presents an integral data assimilation method to improve nuclear data involved in the buildup of nuclides of interest for the fuel cycle.…”

Section: Introductionmentioning

confidence: 99%

Nuclear data adjustment based on the interpretation of post-irradiation experiments with the DARWIN2.3 package

Rizzo

Vaglio–Gaudard

Noguère

et al. 2018

EPJ Nuclear Sci. Technol.

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DARWIN2.3 is the French reference package dedicated to fuel cycle applications, computing fuel inventory as well as decay heat, neutron emissions, α, β and γ spectra. The DARWIN2.3 package fuel inventory calculation was experimentally validated with Post-Irradiation Experiments (PIEs), mainly consisting in irradiated fuel pellets analysis. This paper presents a method to assimilate these integral trends for improving nuclear data. In this study, the method is applied to 137Cs/238U concentration ratio. Results suggest an increase of the JEFF-3.1.1 235U cumulated thermal fission yield in 137Cs by (+3.8 ± 2.1)%, from 6.221E-02 to 6.460E-02 ± 2.1%.

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Section: Introductionmentioning

confidence: 99%

Nuclear data adjustment based on the interpretation of post-irradiation experiments with the DARWIN2.3 package

Rizzo

Vaglio–Gaudard

Noguère

et al. 2018

EPJ Nuclear Sci. Technol.

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“…The recent coupling of the TRIPOLI4 ® stochastic transport code with the MENDEL [15] deterministic depletion solver allows depletion calculations to be performed. Even though this process is not considered as a reference procedure for depletion calculation, the benchmarking between TRIPOLI4 ® and DARWIN2.3 has been investigated to provide first elements of modeling biases quantification [16] for fuel cycle calculations (material balance); this work tends to show that the modeling biases are limited in comparison with the biases coming from nuclear data; experimental Validation: it consists in comparing the calculation results of the set "nuclear data library + calculation scheme + codes" to the values measured with experiments, for the decay heat and the material balance of the main actinides and the fission products involved in fuel cycle calculations and burnup credit criticality calculations; -Uncertainty and bias Quantification: it consists in associating with each parameter calculated by the DARWIN2.3 package, a controlled uncertainty over a range of applications. Generally speaking, there are two ways to achieve this goal: the first one relies on the analysis of the experimental validation results when there is enough experimental data to cover the DARWIN2.3 application domain; in this case, the transposition method is then applied in order to transpose the Calculation-over-Experiment (C/E) discrepancies.…”

Section: Vvuq Process Applied To Darwin23 For the Bias And Uncertainmentioning

confidence: 99%

How to obtain an enhanced extended uncertainty associated with decay heat calculations of industrial PWRs using the DARWIN2.3 package

Huyghe

Vallet

Lecarpentier³

et al. 2019

EPJ Nuclear Sci. Technol.

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Decay heat is a crucial issue for in-core safety after reactor shutdown and the back-end cycle. An accurate computation of its value has been carried out at the CEA within the framework of the DARWIN2.3 package. The DARWIN2.3 package benefits from a Verification, Validation and Uncertainty Quantification (VVUQ) process. The VVUQ ensures that the parameters of interest computed with the DARWIN2.3 package have been validated over measurements and that biases and uncertainties have been quantified for a particular domain. For the parameter "decay heat", there are few integral experiments available to ensure the experimental validation over the whole range of parameters needed to cover the French reactor infrastructure (fissile content, burnup, fuel, cooling time). The experimental validation currently covers PWR UOX fuels for cooling times only between 45 minutes and 42 days, and between 13 and 23 years. Therefore, the uncertainty quantification step is of paramount importance in order to increase the reliability and accuracy of decay heat calculations. This paper focuses on the strategy that could be used to resolve this issue with the complement and the exploitation of the DARWIN2.3 experimental validation.

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“…In collaboration with AREVA NC, CEA has launched a study to identify potential opportunities to improve the precision of depletion calculation and association postprocessing, potentially via an evolution of the associated nuclear data, and focusing first on the radionuclides of the short-list [6].…”

Section: Top-list Of Radionuclides Of Interest and Perspectivesmentioning

confidence: 99%

The use of nuclear data in the field of nuclear fuel recycling

Martin

Launay²,

Grassi

et al. 2017

EPJ Web Conf.

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Abstract. AREVA NC La Hague facility is the first step of the nuclear fuel recycling process implemented in France. The processing of the used fuel is governed by high standards of criticality-safety, and strong expectations on the quality of end-products. From the received used fuel assemblies, the plutonium and the uranium are extracted for further energy production purposes within the years following the reprocessing. Furthermore, the ultimate waste -fission products and minor actinides on the one hand, and hulls and endpieces on the other hand -is adequately packaged for long term disposal. The used fuel is therefore separated into very different materials, and time scales which come into account may be longer than in some other nuclear fields of activity. Given the variety of the handled nuclear materials, as well as the time scales at stake, the importance given to some radionuclides, and hence to the associated nuclear data, can also be specific to the AREVA NC La Hague plant. A study has thus been led to identify a list of the most important radionuclides for the AREVA NC La Hague plant applications, relying on the running constraints of the facility, and the endproducts expectations. The activities at the AREVA NC La Hague plant are presented, and the methodology to extract the most important radionuclides for the reprocessing process is detailed.

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Work plan for improving the DARWIN2.3 depleted material balance calculation of nuclides of interest for the fuel cycle

Cited by 4 publications

References 7 publications

Nuclear data adjustment based on the interpretation of post-irradiation experiments with the DARWIN2.3 package

Nuclear data adjustment based on the interpretation of post-irradiation experiments with the DARWIN2.3 package

How to obtain an enhanced extended uncertainty associated with decay heat calculations of industrial PWRs using the DARWIN2.3 package

The use of nuclear data in the field of nuclear fuel recycling

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