Coupled system thermal Hydraulics/CFD models: General guidelines and applications to heavy liquid metals

Pucciarelli, Andrea; Toti, A; Castelliti, D.; Belloni, Francesco; Tichelen, Katrien Van; Moscardini, Marigrazia; Galleni, Francesco; Forgione, Nicola

doi:10.1016/j.anucene.2020.107990

Cited by 15 publications

(5 citation statements)

References 28 publications

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“…Основна ідея даної схеми полягає в тому, що результати, надані кожним кодом, повторно використовуються в якості оновленої граничної умови для іншого, з оцінкою узгодженість отриманих результатів за критерієм прийнятності, визначеним користувачем Якщо критерій прийнятності виконується, схема переходить до наступного часового кроку, а якщо ні -виконується ще одна внутрішня ітерація та обчислення для того самого часового кроку з оновленими граничними умовами. Такий підхід забезпечує надійне спряження та дає можливість застосування на швидких перехідних процесах та з використанням більшого часового кроку без виникнення нестабільності [8].…”

Section: матеріал і результати дослідженняunclassified

Simulation of Transient Process on Wwer-1000 Using Coupled Approach

Onyshchuk,

Klevtsov

2024

ENERHETYKA: ekonomika, tekhnolohiyi, ekolohiya

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Research and modeling of thermohydraulic processes in NPP equipment is necessary for a deep and improved justification of reliable and safe operation of nuclear installations. Taking into account the accumulated experience and the latest technologies, the study of thermohydraulic processes is developing in the direction of applying innovative approaches to conducting both experimental studies and expanding the calculation capabilities of thermohydraulic codes. The article presents an approach to the decomposition of the thermohydraulic model of the WWER-1000 reactor plant on submodels, which are calculated in coupling with separate instances of the system thermohydraulic code RELAP5/Mod 3.2. Coupling is implemented using a specially developed module. This approach allows you to "bypass" the internal limitations of RELAP5 in the number of components (hydrodynamic volumes, thermal structures, "trips" and control variables) that can be used for computational analysis. As a result, it becomes possible to achieve a higher degree of detail for the entire reactor installation. In addition, the article confirms the possibility of applying the previously developed coupling module to such a non-equilibrium model as a nuclear reactor model. At the same time, the use of the RELAP5 model as a reactor model makes it possible to avoid inaccuracies that arise when applying assumptions about the transverse profiles of the input variables of the CFX model, as well as to perform the validation of the RELAP5 model of the RU loops. Coupled calculation of stationary and transient mode of reactor installation WWER-1000 is performed. The reliability of calculation results obtained in conjugation is evaluated by comparing them with the results of autonomous calculations in RELAP5. The analysis of the results of computational modeling confirms the possibility of applying the developed coupling module to such a non-equilibrium model as a model of a nuclear reactor, and also confirms the correctness of the RELAP5 model of the loops of the reactor plant obtained on the basis of the modification of the full-fledged RELAP5 model.

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Section: матеріал і результати дослідженняunclassified

Simulation of Transient Process on Wwer-1000 Using Coupled Approach

Onyshchuk,

Klevtsov

2024

ENERHETYKA: ekonomika, tekhnolohiyi, ekolohiya

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“…Up to this date, the numerical code development activities focused on the implementation of the chemical models that simulate the interaction between water and PbLi inside the SIMMER-III code (Galleni et al, 2022;Pesetti et al, 2016) and on the development of code chains to study the hydraulic behaviour of the system in these scenarios (Galleni et al, 2020;Pesetti et al, 2016;Pucciarelli et al, 2021). However, all these codes and code chains focused on the goal of simulating the behaviour of the fluid part of the system, neglecting the response of the structures under these dynamical loadings.…”

Section: (Preliminary Development and Validation Activities Of An Int...mentioning

confidence: 99%

SIMMER-III/ANSYS coupling (Preliminary development and validation activities of an integral tool for the design and analysis of WCLL components)

BADODI,

EBOLI,

CAMMI

et al. 2024

Mechanical Engineering Journal

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In the framework of the development of fusion energy, one of the most prominent technologies arising to address the issues of tritium breeding and power conversion is the Water-Cooled Lithium-Lead (WCLL). This technology utilizes a molten eutectic alloy of Lithium and Lead which circulates inside the Breeding Blanket (BB) and is irradiated with neutrons to produce tritium. Water is then circulated inside the system to cool the components. The simultaneous presence inside critical areas of the reactor of molten metal alloy and water, at high temperature and pressure, poses significant safety concerns. For this reason, adequate design and analysis techniques are required to ensure the ability of the system to survive and mitigate any possible damage in case of the in-box Loss of Coolant Accident (LOCA), the most critical postulated accidental scenario. With this aim in mind, a novel approach was implemented with the aim of coupling the SIMMER-III code and the ANSYS Mechanical code for the modelling of both the chemical and thermodynamical interactions between water and the alloy, and the resulting effects on the structures. This work presents the status of the coupling technique development and the results of the preliminary validation activities performed against experimental data provided by the LIFUS5 facility operating at ENEA Brasimone Research Centre. The resulting comparison between these data and the codes' predictions allows a careful evaluation of the errors introduced in each step of the chain. Moreover, it provides confidence in the capacity of the methodology to correctly predict the ability of the structures to withstand incidental loads without suffering extensive damage. This work aims at providing engineers with a usable and powerful tool that allows for the safety analysis of WCLL-based components during the early stages of the design phase. This would help save time, and effort and reduce the economic cost that might arise from any undetected issue propagating downstream the design process.

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“…These R&D activities are pursued in the framework of EU projects [68-71] and national programs [72][73][74][75] to cope with gaps in the simulation performances. The development of STH/CFD (System Thermal Hydraulics/Computational Fluid Dynamics) is becoming increasingly interesting for the simulation of complex thermal hydraulics analysis in support of the design of the LFR nuclear system [79]. 1D STH numerical codes are considered one of the most relevant tools in the licensing process of nuclear power plants.…”

Section: Numerical Tools For Lfrmentioning

confidence: 99%

Overview on Lead-Cooled Fast Reactor Design and Related Technologies Development in ENEA

et al. 2021

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The next generation of nuclear energy systems, also known as Generation IV reactors, are being developed to meet the highest targets of safety and reliability, sustainability, economics, proliferation resistance, and physical protection, with improved performances compared with the currently licensed plants or those presently being built. Among the proposed technologies, lead-cooled fast reactors (LFRs) have been identified by nuclear industries in both Western and developing countries as being among the optimal Generation IV candidates. Since 2000, ENEA, the Italian National Agency for New Technologies, Energy, and Sustainable Economic Development is supporting the core design, safety assessment, and technological development of innovative nuclear systems cooled by heavy liquid metals (HLM) and, most recently, fully oriented on LFRs. ENEA is developing world-recognized skills in fast spectrum core design and is one of the largest European fleets of experimental facilities aiming at investigating HLM thermal-hydraulics, coolant chemistry control, corrosion behavior for structural materials, and material properties in the HLM environment, as well as at developing corrosion-protective coatings, components, instrumentation, and innovative systems, supported by experiments and numerical tools. Efforts are also dedicated to develop and validate numerical tools for specific application to HLM systems, ranging from neutronics codes, system and core thermal-hydraulic codes, computational fluid dynamics (CFD) and fuel pin performance codes, including their coupling. The present work aims at highlighting the capabilities and competencies developed by ENEA so far in the framework of liquid metal technologies for Generation IV LFRs. In particular, an overview on the ongoing R&D experimental program will be depicted considering the current fleet of facilities, namely: CIRCE, NACIE-UP, LIFUS5, LECOR, BID-1, HELENA, RACHEL, and Mechanical Labs. An overview on the numerical activities performed so far and those presently ongoing is also reported. Finally, an overview of the ENEA contribution to the ALFRED Project in the frame of the FALCON international consortium is reported, mainly addressing the ongoing activity in terms of core design, technology development, and auxiliary systems design.

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Coupled system thermal Hydraulics/CFD models: General guidelines and applications to heavy liquid metals

Cited by 15 publications

References 28 publications

Simulation of Transient Process on Wwer-1000 Using Coupled Approach

Simulation of Transient Process on Wwer-1000 Using Coupled Approach

SIMMER-III/ANSYS coupling (Preliminary development and validation activities of an integral tool for the design and analysis of WCLL components)

Overview on Lead-Cooled Fast Reactor Design and Related Technologies Development in ENEA

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