ASTEC V2 severe accident integral code: Fission product modelling and validation

Cantrel, Laurent; Cousin, F.; Bosland, L.; Chevalier-Jabet, Karine; Marchetto, C.

doi:10.1016/j.nucengdes.2014.01.011

Cited by 25 publications

(14 citation statements)

References 40 publications

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“…) is an integral code co-developed by IRSN and the German Gesellschaft für Anlagen und Reaktorsicherheit mbH [17]. The primary objective of ASTEC is to simulate SA progression of LWRs, ranging from various initiating events to fission product release from containment [17].…”

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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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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“…The Ru-N-O-H system in the gas phase reaction was also incorporated to the ECUME. The CRK can be applied to the mechanistic codes such as SOPHAEROS module in ASTEC code (Cantrel, 2014), which can evaluate the FP chemistry with the reaction kinetics.…”

Section: Dataset For Chemical Reaction Kinetics (Crk)mentioning

confidence: 99%

Development of fission product chemistry database ECUME for the LWR severe accident

Miwa

Nakajima

Miyahara

et al. 2020

Mechanical Engineering Journal

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The SA analysis codes can estimate the release of fission products (FPs) into environment and distribution of FPs in a reactor based on the models of thermal-hydraulics and FP behaviors at each region in a reactor, from reactor pressure vessel (RPV) to containment vessel (CV) and reactor building (RB) through reactor cooling system (RCS). Thus, the improvement of FP models is one of the key issues for the improved source term (IAEA, 2008). The FP models have been improved based on results of the researches on various FP behaviors (Soffer, 1995; Clément, 2007; Allelein, 2009). The main issues for the improvement are FP chemistry (Haste, 2009; Miwa 2015) and treatment of fine space resolution in a reactor. As for the latter issue of fine space resolution, it is especially important for the decommissioning of 1F since a detailed and fine FP distribution is required (Nuclear Damage Compensation and Decommissioning Facilitation

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“…In order to take precautionary measures and to increase PWR security, computer simulations of crisis situations are regularly performed. A typical representative of modelling calculations is the Accident Source Term Evaluation Code (ASTEC) [11,12], which simulates all the possible phenomena associated with the PWR crisis situations, starting with different types of accidents, up to the release of fission products to the outside environment. Key point in the reliable predictions of Published as part of the topical collection of articles from the 17th edition of the Central European Symposium on Theoretical Chemistry (CESTC 2019) in Austria.…”

Section: Introductionmentioning

confidence: 99%

Spectroscopic properties of diatomic molecules CdI and CsCd: ab initio calculations

Kozakova

Černušák

2020

Theor Chem Acc

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Ab initio methods, CASPT2 and CCSD(T), with the large contraction of the ANO-RCC basis set, were used for the calculations of potential energy curves (PECs) of CsI and CsCd. Spin-free PECs for the ground and low-lying excited states of both diatomics were investigated for doublet and quartet Λ-∑ states (22 for CdI and 13 for CsCd). Spin-orbit interaction was calculated using the CASPT2/RASSI method, leading to 6 Ω states of CdI and 8 Ω states of CsCd. Spectroscopic properties for the bound states were calculated from these data-equilibrium distance R e , harmonic frequency ω e , the first anharmonicity ω e x e , rotational constant B e , excitation energy T e and dissociation energy D e .

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ASTEC V2 severe accident integral code: Fission product modelling and validation

Cited by 25 publications

References 40 publications

Thermodynamically Informed Nuclear Fuel Codes—A Review and Perspectives

Thermodynamically Informed Nuclear Fuel Codes—A Review and Perspectives

Development of fission product chemistry database ECUME for the LWR severe accident

Spectroscopic properties of diatomic molecules CdI and CsCd: ab initio calculations

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