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boron dilution scenario

This paper compares CFD simulation results of a boron dilution scenario with experimental results.

Modelling of complex boron dilution transients in PWRs—Validation of CFD simulation with ANSYS CFX against the ROCOM E2.3 experiment

boron dilution scenario

In this paper, a new approach dealing with such heterogeneous boron dilution scenarios is presented.

A realistic approach for the assessment of the consequences of heterogeneous boron dilution events in pressurized water reactors

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Boron Dilution sentence examples within boron dilution transient

boron dilution transient

43 is selected as the benchmark and the rapid boron dilution transient in the nuclear reactor is studied with the coupling code.

CFD/RELAP5 coupling analysis of the ISP No. 43 boron dilution experiment

boron dilution transient

The main goal in this work was to investigate how well mixing during boron dilution transients in the pressurizer of a Rojas Mazaira et al.

Computational simulation of a test facility in reduced scale for analysis of boron dispersion in a pressurizer of an integral compact and modular reactor

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10.1016/j.net.2021.07.047

43 is selected as the benchmark and the rapid boron dilution transient in the nuclear reactor is studied with the coupling code.

CFD/RELAP5 coupling analysis of the ISP No. 43 boron dilution experiment

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10.1016/j.nucengdes.2020.110938

This paper compares CFD simulation results of a boron dilution scenario with experimental results.

Modelling of complex boron dilution transients in PWRs—Validation of CFD simulation with ANSYS CFX against the ROCOM E2.3 experiment

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10.15392/bjrs.v8i3a.1535

The main goal in this work was to investigate how well mixing during boron dilution transients in the pressurizer of a Rojas Mazaira et al.

Computational simulation of a test facility in reduced scale for analysis of boron dispersion in a pressurizer of an integral compact and modular reactor

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10.1051/EPJCONF/202124707005

In this paper we will give two examples of accidental transients that can be simulated with ANTARES: a REA (Rod Ejection Accident) and an inadvertent boron dilution event.

ANTARES: COUPLING PARCS WITH CATHARE-3

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10.1016/j.pnucene.2020.103592

The results show that static diffusion and sampling have a slight impact on boron dilution, but in different ways.

Numerical study of boron diffusion in CMT and related thermal fatigue near cold legs of an AP1000 nuclear power unit

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10.1007/s42452-019-1574-1

This work consists of a Computational Fluid Dynamics (CFD) modeling of a reference experiment on boron dilution in the Rossendorf coolant mixing Model (ROCOM) as part of a coordinated research project of the International Atomic Energy Agency, namely, “Application of numerical codes of fluid dynamics to the design of nuclear power plants”.

The capability of Ansys CFX to predict the mixing phenomena in ROCOM test facility

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10.1016/J.NUCENGDES.2019.04.038

In this paper, a new approach dealing with such heterogeneous boron dilution scenarios is presented.

A realistic approach for the assessment of the consequences of heterogeneous boron dilution events in pressurized water reactors

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10.1016/B978-0-08-102337-2.00004-3

The work is aimed at describing the mixing phenomena relevant for both safety analysis, particularly in steam line break and boron dilution scenarios, and mixing phenomena of interest for economical operation and the structural integrity.

Evaluation of safety of light-water-cooled reactors using CFD

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10.1016/J.NUCENGDES.2018.11.005

The Rossendorf Coolant Mixing Model (ROCOM) boron dilution benchmark experiment was assessed using the CUPID code in the framework of a Coordinated Research Project by the International Atomic Energy Agency, namely, “Application of Computational Fluid Dynamics Codes for Nuclear Power Plant Design.

Numerical analysis of the ROCOM boron dilution benchmark experiment using the CUPID code

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10.1016/J.PNUCENE.2019.103046

The boron dilution transient may cause re-criticality during an emergency shutdown, and the mixing between de-borated slug and boric acid inside the annular down-comer and the lower plenum is the inherent mechanism against such accident.

Experimental study on mixing phenomenon inside reactor down-comer under single-loop injection using laser induced fluorescence

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10.1016/J.ANUCENE.2019.04.017

The optimized core is operated without boron in the moderator and is characterized by enhanced safety features as a result of (1) avoiding concerns related to boric acid induced corrosion of a reactor pressure vessels internals; and (2) eliminating the probability of boron dilution accidents.

Core neutronics and safety characteristics of a boron-free core for Small Modular Reactors

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Boron Dilution - 43 is selected as the benchmark and the rapid boron dilution transient in the nuclear reactor is studied with the coupling code. [1] This paper compares CFD simulation results of a boron dilution scenario with experimental results. [2] The main goal in this work was to investigate how well mixing during boron dilution transients in the pressurizer of a Rojas Mazaira et al. [3] In this paper we will give two examples of accidental transients that can be simulated with ANTARES: a REA (Rod Ejection Accident) and an inadvertent boron dilution event. [4] The results show that static diffusion and sampling have a slight impact on boron dilution, but in different ways. [5] This work consists of a Computational Fluid Dynamics (CFD) modeling of a reference experiment on boron dilution in the Rossendorf coolant mixing Model (ROCOM) as part of a coordinated research project of the International Atomic Energy Agency, namely, “Application of numerical codes of fluid dynamics to the design of nuclear power plants”. [6] In this paper, a new approach dealing with such heterogeneous boron dilution scenarios is presented. [7] The work is aimed at describing the mixing phenomena relevant for both safety analysis, particularly in steam line break and boron dilution scenarios, and mixing phenomena of interest for economical operation and the structural integrity. [8] The Rossendorf Coolant Mixing Model (ROCOM) boron dilution benchmark experiment was assessed using the CUPID code in the framework of a Coordinated Research Project by the International Atomic Energy Agency, namely, “Application of Computational Fluid Dynamics Codes for Nuclear Power Plant Design. [9] The boron dilution transient may cause re-criticality during an emergency shutdown, and the mixing between de-borated slug and boric acid inside the annular down-comer and the lower plenum is the inherent mechanism against such accident. [10] The optimized core is operated without boron in the moderator and is characterized by enhanced safety features as a result of (1) avoiding concerns related to boric acid induced corrosion of a reactor pressure vessels internals; and (2) eliminating the probability of boron dilution accidents. [11]

boron dilution scenario

This paper compares CFD simulation results of a boron dilution scenario with experimental results. [1] In this paper, a new approach dealing with such heterogeneous boron dilution scenarios is presented. [2] The work is aimed at describing the mixing phenomena relevant for both safety analysis, particularly in steam line break and boron dilution scenarios, and mixing phenomena of interest for economical operation and the structural integrity. [3]

boron dilution transient

43 is selected as the benchmark and the rapid boron dilution transient in the nuclear reactor is studied with the coupling code. [1] The main goal in this work was to investigate how well mixing during boron dilution transients in the pressurizer of a Rojas Mazaira et al. [2] The boron dilution transient may cause re-criticality during an emergency shutdown, and the mixing between de-borated slug and boric acid inside the annular down-comer and the lower plenum is the inherent mechanism against such accident. [3]