Fission product release from nuclear fuel I. Physical modelling in the ASTEC code

Brillant, G.; Marchetto, C.; Plumecocq, W.

doi:10.1016/j.anucene.2013.03.022

Cited by 20 publications

(8 citation statements)

References 21 publications

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“…These plateaus and ramps could be associated to the creation and destruction of chemical phases which control the release of FP under specific conditions. Nevertheless, scenario codes for source-term estimation such as the ASTEC Code [24], [25] normally assume that volatile FP such as iodine and caesium behave as gases and that their release is purely diffusive. As for Ba and Mo, some reactions are considered but the intermediary compounds have never been observed experimentally.…”

Section: Scientific Contextmentioning

confidence: 99%

Insights on fission products behaviour in nuclear severe accident conditions by X-ray absorption spectroscopy

Geiger

Bès

Martin

et al. 2016

Journal of Nuclear Materials

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Many research programs have been carried out aiming to understand the fission products behaviour during a Nuclear Severe Accident. Most of these programs used highly radioactive irradiated nuclear fuel, which requires complex instrumentation. Moreover, the radioactive character of samples hinders an accurate chemical characterisation. In order to overcome these difficulties, SIMFUEL stand out as an alternative to perform complementary tests. A sample made of UO 2 doped with 11 fission products was submitted to an annealing test up to 1700 °C in reducing atmosphere. The sample was characterized before and after the annealing test using SEM-EDS and XAS at the MARS beam-line, SOLEIL Synchrotron. It was found that, despite the absence of volatile FP in SIMFUEL samples, the overall behaviour of several fission products like Mo, Ba, Pd and Ru was similar to that observed experimentally in irradiated fuels and also consistent with thermodynamic estimations.

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Section: Scientific Contextmentioning

confidence: 99%

Insights on fission products behaviour in nuclear severe accident conditions by X-ray absorption spectroscopy

Geiger

Bès

Martin

et al. 2016

Journal of Nuclear Materials

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“…Note that the effective diffusion coefficient does not depend on the fuel Oxygen/Metal (O/M) ratio, as it is the case in some severe accident codes [18]. This dependency stems from the decoupling of FP thermochemistry and fuel oxidation/reduction modeling in these codes.…”

Section: Extension To Severe Accident Modelingmentioning

confidence: 98%

“…The second aspect that is generally lacking in SA codes compared to fuel performance codes is the precise description of the irradiated fuel state before the SA scenario. SA codes generally consider the fuel pellet as a single entity characterized by an average burnup and FP content [12] [18]. While this hypothesis is convenient to reduce the computational time, it is far from the fuel state after irradiation in a commercial Pressurized Water Reactor (PWR).…”

Section: Introductionmentioning

confidence: 99%

Modeling of fission product release during severe accidents with the fuel performance code ALCYONE

Germain

Sercombe

Riglet-Martial

et al. 2022

Nuclear Engineering and Design

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“…ASTEC contains several modules aimed at modelling various aspects of SA progression. The ELSA module within ASTEC simulates fission product release from defective fuel, which is informed by thermodynamic calculations including 42 chemical elements [80]. The handling of fission products are partitioned in three categories: volatiles, semi-volatiles, and low-volatiles [17].…”

Section: Astec Astec (Accident Source Term Evaluation Codementioning

confidence: 99%

“…Unlike the work of Cubicciotti [73] and MELCOR, a Gibbs energy minimizer is not directly coupled to ASTEC, but rather a series of equilibrium constants are used instead. An empirical correlation relating temperature and oxygen partial pressure is used to model fuel stoichiometry, x in UO 2±x [80]. A number of correlations are used to capture specific chemical reactions (e.g., CeO 2(s) = Ce g + O 2(g) ), which are temperature dependent and sometimes include activity coefficients to account for non-ideal behaviour [81].…”

Section: Astec Astec (Accident Source Term Evaluation Codementioning

confidence: 99%

Thermodynamically Informed Nuclear Fuel Codes—A Review and Perspectives

Piro

2021

Thermo

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A number of codes are used to predict various aspects of nuclear fuel performance and safety, ranging from conventional fuel performance codes to simulate normal operating conditions to integral engineering codes to simulate severe accident behaviour. There has been a number of reportings in the open literature of nuclear fuel codes being informed by thermodynamic calculations, ranging from the use of simple thermodynamic correlations to direct coupling of equilibrium thermodynamic software. Progress in expanding predictive capabilities have been reported, which also includes advances in thermodynamic database development to better capture irradiated fuel. However, this progress has been accompanied by several challenges, including effective coupling of different types of physical phenomena in a practical manner and doing so with a reasonable increase in computational expense. This review paper will summarize previous experiences reported in the open literature in coupling thermodynamic calculations with nuclear fuel codes and applications, identify current challenges and limitations, and offer some perspectives for the community to consider moving forward.

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Fission product release from nuclear fuel I. Physical modelling in the ASTEC code

Cited by 20 publications

References 21 publications

Insights on fission products behaviour in nuclear severe accident conditions by X-ray absorption spectroscopy

Insights on fission products behaviour in nuclear severe accident conditions by X-ray absorption spectroscopy

Modeling of fission product release during severe accidents with the fuel performance code ALCYONE

Thermodynamically Informed Nuclear Fuel Codes—A Review and Perspectives

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