Experimental Validation of the DARWIN2.3 Package for Fuel Cycle Applications

San-Felice, L.; Eschbach, R.; Bourdot, P.

doi:10.13182/nt12-121

Cited by 34 publications

(32 citation statements)

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“…This is why CESAR is validated against DARWIN TM [1,7,8], CEA reference computer package for isotopic inventory evolution. DARWIN TM computes all 3800 isotopes from JEFF3.1.1.…”

Section: Validation Processmentioning

confidence: 99%

CESAR5.3: Isotopic depletion for Research and Testing Reactor decommissioning

Ritter

Eschbach

Girieud

et al. 2018

EPJ Nuclear Sci. Technol.

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CESAR stands in French for “simplified depletion applied to reprocessing”. The current version is now number 5.3 as it started 30 years ago from a long lasting cooperation with ORANO, co-owner of the code with CEA. This computer code can characterize several types of nuclear fuel assemblies, from the most regular PWR power plants to the most unexpected gas cooled and graphite moderated old timer research facility. Each type of fuel can also include numerous ranges of compositions like UOX, MOX, LEU or HEU. Such versatility comes from a broad catalog of cross section libraries, each corresponding to a specific reactor and fuel matrix design. CESAR goes beyond fuel characterization and can also provide an evaluation of structural materials activation. The cross-sections libraries are generated using the most refined assembly or core level transport code calculation schemes (CEA APOLLO2 or ERANOS), based on the European JEFF3.1.1 nuclear data base. Each new CESAR self shielded cross section library benefits all most recent CEA recommendations as for deterministic physics options. Resulting cross sections are organized as a function of burn up and initial fuel enrichment which allows to condensate this costly process into a series of Legendre polynomials. The final outcome is a fast, accurate and compact CESAR cross section library. Each library is fully validated, against a stochastic transport code (CEA TRIPOLI 4) if needed and against a reference depletion code (CEA DARWIN). Using CESAR does not require any of the neutron physics expertise implemented into cross section libraries generation. It is based on top quality nuclear data (JEFF3.1.1 for ∼400 isotopes) and includes up to date Bateman equation solving algorithms. However, defining a CESAR computation case can be very straightforward. Most results are only 3 steps away from any beginner's ambition: Initial composition, in core depletion and pool decay scenario. On top of a simple utilization architecture, CESAR includes a portable Graphical User Interface which can be broadly deployed in R&D or industrial facilities. Aging facilities currently face decommissioning and dismantling issues. This way to the end of the nuclear fuel cycle requires a careful assessment of source terms in the fuel, core structures and all parts of a facility that must be disposed of with “industrial nuclear” constraints. In that perspective, several CESAR cross section libraries were constructed for early CEA Research and Testing Reactors (RTR’s). The aim of this paper is to describe how CESAR operates and how it can be used to help these facilities care for waste disposal, nuclear materials transport or basic safety cases. The test case will be based on the PHEBUS Facility located at CEA − Cadarache.

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“…This is why CESAR is validated against DARWIN TM [1,7,8], CEA reference computer package for isotopic inventory evolution. DARWIN TM computes all 3800 isotopes from JEFF3.1.1.…”

Section: Validation Processmentioning

confidence: 99%

CESAR5.3: Isotopic depletion for Research and Testing Reactor decommissioning

Ritter

Eschbach

Girieud

et al. 2018

EPJ Nuclear Sci. Technol.

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“…For instance, 137 Cs is systematically underestimated in PWR UOX fuel depletion calculations with DRAINW2.3 [1]. Assimilating this tendency could overcome this underestimation by reducing nuclear data uncertainties.…”

Section: Work Planmentioning

confidence: 99%

“…DARWIN2.3 [1] is the French reference package used for fuel cycle applications. It solves the Boltzmann and Bateman equations in a coupling way to compute fuel cycle parameters, at any irradiation and cooling time.…”

Section: Introductionmentioning

confidence: 99%

“…The DARWIN2.3 package has been experimentally validated for light water reactors for the material balance and decay heat calculation [1]. It has also been experimentally validated for sodium fast reactors for the material balance of the main actinides and fission products involved in burn up-credit calculations [8].…”

Section: Introductionmentioning

confidence: 99%

“…As regards decay heat calculation for PWR UOX fuel assemblies, the experimental validation of the package covers both short cooling time (40 minutes -40 days) for lowburnup fuels [9] and long cooling time (10-30 years) for intermediate to high burnup (20-50 GWd/t) ranges [1]. The DARWIN2.3 experimental validation work points out some isotopes for which the depleted concentration calculation can be improved; all the more some of them play an important role in the fuel cycle management (fuel inventory, decay heat, radiotoxicity.…”

Section: Introductionmentioning

confidence: 99%

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

et al. 2017

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Abstract. DARWIN2.3 is the reference package used for fuel cycle applications in France. It solves the Boltzmann and Bateman equations in a coupling way, with the European JEFF-3.1.1 nuclear data library, to compute the fuel cycle values of interest. It includes both deterministic transport codes APOLLO2 (for light water reactors) and ERANOS2 (for fast reactors), and the DARWIN/PEPIN2 depletion code, each of them being developed by CEA/DEN with the support of its industrial partners.The DARWIN2.3 package has been experimentally validated for pressurized and boiling water reactors, as well as for sodium fast reactors; this experimental validation relies on the analysis of post-irradiation experiments (PIE).The DARWIN2.3 experimental validation work points out some isotopes for which the depleted concentration calculation can be improved. Some other nuclides have no available experimental validation, and their concentration calculation uncertainty is provided by the propagation of a priori nuclear data uncertainties.This paper describes the work plan of studies initiated this year to improve the accuracy of the DARWIN2.3 depleted material balance calculation concerning some nuclides of interest for the fuel cycle.

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Direct determination of the 237Np/238U ratio in nuclear fuel samples by multicollection inductively coupled plasma mass spectrometry (MC-ICP-MS)

Mialle,

Nonell,

Cruchet

et al. 2024

J Radioanal Nucl Chem

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A new method for the direct measurement of 237Np/238U ratio in irradiated UO2 pellets by multicollection inductively coupled plasma mass spectrometry (MC-ICP-MS) is proposed. It allows the determination of ratios down to 10 × 10–6 mol·mol−1 using ion counter and Faraday cup. This approach was validated by intercomparison with the usual two-step-method (Quadrupole ICP-MS for 237Np determination and isotope dilution mass spectrometry (IDMS) for 238U). For ratios between 10 × 10–6 and 100 × 10–6 mol·mol−1, expanded uncertainties (k = 2) varied from 2.75% to 0.81%, twice lower than the uncertainties determined by the usual method.

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Experimental Validation of the DARWIN2.3 Package for Fuel Cycle Applications

Cited by 34 publications

References 1 publication

CESAR5.3: Isotopic depletion for Research and Testing Reactor decommissioning

CESAR5.3: Isotopic depletion for Research and Testing Reactor decommissioning

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

Direct determination of the 237Np/238U ratio in nuclear fuel samples by multicollection inductively coupled plasma mass spectrometry (MC-ICP-MS)

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