Experimental validation of VESTA 2.1

Haeck, Wim; Cochet, B.; Bernard, Franck; Tymen, A.

doi:10.1051/snamc/201403603

Cited by 6 publications

(2 citation statements)

References 6 publications

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“…UPM performed calculations with KENO-VI which is coupled with ORIGEN depletion solver within the SCALE code system [7]. CIEMAT and IRSN used the EVOLCODE 2.0 [8] and VESTA 2.2.0 [9] codes which couple MCNP with the depletion solvers ACAB [10] and PHOENIX, respectively. The deterministic results were produced by NNL and Cambridge University using WIMS [11].…”

Section: Modeling Assumptionsmentioning

confidence: 99%

Neutronic Analysis of the European Sodium Fast Reactor: Part II—Burnup Results

Fridman

Velarde

Otero

et al. 2021

Journal of Nuclear Engineering and Radiation Science

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In the framework of the Horizon 2020 project ESFR-SMART (2017-2021), the European Sodium Fast Reactor (ESFR) core was updated through a safety-related modification and optimization of the core design from the earlier FP7 CP-ESFR project (2009-2013). This study is dedicated to neutronic analyses of the improved ESFR core design. The conducted work is reported in two parts. Part I deals with the evaluation of the safety-related neutronic parameters of the fresh Beginning-of-Life (BOL) core carried out by 8 organizations using both continuous energy Monte Carlo and deterministic computer codes. In addition to the neutronics characterization of the core, a special emphasis was put on the calibration and verification of the computational tools involved in the analyses. Part II is devoted to once-through and realistic batch-wise burnup calculations aiming at the establishing of the equilibrium core state, which will later serve as a basis for detailed safety analyses.

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Section: Modeling Assumptionsmentioning

confidence: 99%

Neutronic Analysis of the European Sodium Fast Reactor: Part II—Burnup Results

Fridman

Velarde

Otero

et al. 2021

Journal of Nuclear Engineering and Radiation Science

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“…First, the DARWIN2.3 validation could be extended with the analysis of two sets of integral decay heat measurements which have been found in the literature: the GE-Morris and HEDL measurements. They are used for the validation of other international codes dedicated to decay heat computation such as SCALE/ORIGEN [39] or VESTA2.1 [40]. The GE-Morris and HEDL measurements enable us to cover lower cooling time ranges than the CLAB experiments.…”

Section: Perspectives For the Determination Of An Enhanced Extended Umentioning

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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