Validation of Serpent-SUBCHANFLOW-TRANSURANUS pin-by-pin burnup calculations using experimental data from a Pre-Konvoi PWR reactor

García, Manuel; Bilodid, Y.; Perello, Joaquín Basualdo; Tuominen, Riku; Gommlich, André; Leppänen, Jaakko; Valtavirta, Ville; Imke, Uwe; Ferraro, Diego; Uffelen, P. Van; Seidl, Marcus; Sánchez-Espinoza, Víctor Hugo

doi:10.1016/j.nucengdes.2021.111173

Cited by 11 publications

(5 citation statements)

References 10 publications

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“…This second verification exercise was deemed successful as the magnitude of the biases between deterministic and Monte Carlo solutions were within the range of typical biases encountered in the literature when performing such analysis. For fullcore type of calculations, the results of the CHUP methodology could be compared to fullcore high-fidelity solutions, which are computationally costly but doable as demonstrated in (García et al, 2021).…”

Section: Discussionmentioning

confidence: 99%

“…Such approach has been attempted in the past (Ranta-aho, 2011), but only for a subset of a fullcore model and a reduced set of isotopes. More recently fullcore coupled cycle calculations for pressurized water systems were carried out using Monte Carlo codes (Lee et al, 2020;García et al, 2021;García et al, 2021). However such simulations required either specific feature of the code (domain decomposition in Serpent) available only for depletion problems or codes which are not openly available (Lee et al, 2020).…”

Section: Introductionmentioning

confidence: 99%

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Monte Carlo Analysis of Bwr Geometries Using a Cycle Check-Up Methodology

Hursin¹,

Vasiliev²,

Rochman³

et al. 2023

Preprint

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Section: Discussionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Monte Carlo Analysis of Bwr Geometries Using a Cycle Check-Up Methodology

Hursin¹,

Vasiliev²,

Rochman³

et al. 2023

Preprint

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“…Owing to the more detailed description of HBU fuel behaviour in the TRANSURANUS code, in combination with higher computational power, high fidelity simulations for the reactor safety analysis have been initiated within the McSAFE project. These include pin-by-pin simulations of PWRs or WWERs by means of the coupled Serpent-Subchanflow-TRANSURANUS code system [51,52]. This work is being extended to simulate fuel rods with accident tolerant materials such as FeCrAl cladding and U3Si2 fuel in various water cooled SMRs such as the Nuscale reactor within the McSAFER project [53].…”

Section: Utility Experience Withmentioning

confidence: 99%

Safety and Performance Aspects in the Development and Qualification of High Burnup Nuclear Fuels for Water Cooled Reactors

2024

IAEA TECDOC Series

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This TECDOC aims at illustrating the status in addressing safety and technological challenges encountered in the development, qualification and licensing of HBU nuclear fuels for Water Cooled Reactors (WCRs), summarizing the discussions held at a Technical Meeting organized by the IAEA in November 2022. This publication will provide useful insights for a future revision of IAEA Safety Standards Series No. SSG-52, Design of the Reactor Core for Nuclear Power Plants, as industry trends strongly signal a need to broaden the scope of this safety guide to include high burnup nuclear fuels. This publication is intended for Technical and Scientific Support Organizations (TSOs), regulatory organizations, operators, and research organizations.

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“…In these codes, the adoption of a priori calculations of the CBC has gained increasing attention in the last decade, facilitated by the increase in the availability of computing power and advanced reactor analysis codes. For example, code validations have been carried out with the typical benchmark problems, that is, VERA 7 and BEAVRS, 8 and with the experimental data of other facilities 9 …”

Section: Introductionmentioning

confidence: 99%

“…For example, code validations have been carried out with the typical benchmark problems, that is, VERA 7 and BEAVRS, 8 and with the experimental data of other facilities. 9 The boron concentration dictates the rate of thermal neutron captures in the boron, which hardens the spectrum. The spectrum hardening (or softening) affects the 1-group cross sections and the reaction rates used to solve the Bateman equations.…”

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confidence: 99%

Study of radionuclide inventory in nuclear fuel under uncertainties in boron concentration using high‐fidelity models

Castagna

Gilad

2022

Intl J of Energy Research

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Summary Uncertainties in the critical boron concentration during reactor burnup calculations strongly affect the spectrum, thus propagating to the 1‐group cross sections and reaction rates used in the Bateman equations and eventually affecting the resulting nuclide densities. These, in turn, alter the calculated critical boron concentration and so on. Usually, the uncertainty due to this nonlinear feedback is overlooked since only final (ie, at the end of the cycle) radionuclide densities are considered for fuel and waste management. However, for source term analysis, an accurate estimation of the core's radionuclide inventory is required at any time during the irradiation cycle. This paper presents an in‐depth uncertainty analysis on the nuclide inventory calculations by considering the nonlinear feedback due to deviation from the critical boron concentration during calculation. In particular, the physical characterization of the interrelated effects among spectrum, cross‐sections, reaction rates, and boron concentration are highlighted. The results indicate that deviation from the critical boron concentration during calculation may lead to significant discrepancies in nuclide densities during the irradiation cycle, which tends to decrease towards the end of the cycle. The physical processes underlying this behaviour are studied in depth using a high‐fidelity model and the Monte Carlo transport calculations. The methodology presented in this study may be used for systematic uncertainty and sensitivity analysis.

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Validation of Serpent-SUBCHANFLOW-TRANSURANUS pin-by-pin burnup calculations using experimental data from a Pre-Konvoi PWR reactor

Cited by 11 publications

References 10 publications

Monte Carlo Analysis of Bwr Geometries Using a Cycle Check-Up Methodology

Monte Carlo Analysis of Bwr Geometries Using a Cycle Check-Up Methodology

Safety and Performance Aspects in the Development and Qualification of High Burnup Nuclear Fuels for Water Cooled Reactors

Study of radionuclide inventory in nuclear fuel under uncertainties in boron concentration using high‐fidelity models

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