COBRA-IV PC: A personal computer version of COBRA-IV-I for thermal-hydraulic analysis of rod bundle nuclear fuel elements and cores

Webb, B.J.

doi:10.2172/5655065

Cited by 5 publications

(2 citation statements)

References 5 publications

(2 reference statements)

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“…Nuclear energy is a prominent source of base-load green energy. Sub-channel analysis [1][2][3] is used widely for fuel cluster computations and is an essential tool for licensing requirements of nuclear reactors. [4] Sub-channel analysis includes lateral interaction between sub-channels in onedimensional balance equations.…”

Section: Introductionmentioning

confidence: 99%

Estimation of turbulent energy mixing factor in PWR sub‐channel by DNS

Singh,

Mukhopadhyay,

Khakhar

et al. 2024

Can J Chem Eng

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Turbulent mixing within sub‐channels plays a crucial role in understanding the thermal hydraulics of reactor channels. It serves as an empirical parameter in sub‐channel analysis and has long been a challenge in the nuclear industry. Conducting experiments in this context is challenging due to the stringent requirement of maintaining pressure balance among sub‐channels to prevent convection effects. Fortunately, direct numerical simulation (DNS) is emerging as an invaluable tool for addressing this persistent issue. DNS enables the direct computation of turbulent mixing by analyzing fluctuating lateral velocities, offering a more profound understanding of the underlying phenomena. In this study, DNS was conducted at six Reynolds numbers ranging from 17,640 to 1.5 × 105 in pressurized water reactor (PWR) geometry to investigate the lateral mixing driven by turbulence. By studying intricate mechanisms governing the turbulent mixing, the valuable insights into reactor thermal performance and safety are provided. Furthermore, a correlation for turbulent mixing of energy based on the DNS data has been derived, enhancing our ability to model and predict this critical aspect of reactor behaviour. Additionally, this paper explores temperature fluctuations occurring at the fuel rod surface due to turbulence. A probabilistic distribution for temperature fluctuation under specific reactor conditions is presented.

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Section: Introductionmentioning

confidence: 99%

Estimation of turbulent energy mixing factor in PWR sub‐channel by DNS

Singh,

Mukhopadhyay,

Khakhar

et al. 2024

Can J Chem Eng

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“…The power distributions values obtained from the use of the MCNP code are used in the COBRA code. The COBRA code [21] was used to obtain the thermal analysis values. The COBRA code can determine the thermal values of the reactor coolant by performing the subchannel analysis.…”

Section: Introductionmentioning

confidence: 99%

Nükleer Reaktörlerde Nanoparçacık Olarak Kalsiyum Karbonat Kullanımının Araştırılması

Uzun

Genç

Acır

2023

Konya Journal of Engineering Sciences

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In this study, calcium carbonate (CaCO3) was considered as nanoparticle. In the first part of the study, half-value layer (HVL) and mean free path (MFP) values, which are radiation shielding parameters, were investigated in determined energy ranges by Phy-X open access software. At increasing energy levels, the HVL value reached approximately 10 cm, while the MFP value reached approximately 17 cm. In the second part of the study, the reactor core geometry was modeled with the MCNP code and then the relative power distribution values were determined. COBRA code input was prepared with the determined relative power distribution values and thermal analyzes were made. These analyzes were performed for three different nanoparticle ratios. As a result of the analysis, the temperature value at the end of the channel was 613 K when only water was used as a coolant, while the temperature value at the end of the channel was 611.19 K when 0.03% nanoparticles were used. Although the coolant temperature increased with the nanoparticle ratio, it was observed that the temperature decreased when only water was used.

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