Innovative model of annular fuel design for lead-cooled fast reactors

Rowinski, Marcin Karol; White, Timothy John; Zhao, Jiyun

doi:10.1016/j.pnucene.2015.04.002

Cited by 5 publications

(2 citation statements)

References 34 publications

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“…The United States (Kazimi et al, 2006;El-Sahlamy et al, 2020), South Korea (Shin et al, 2012), Iran (Zaidabadi et al, 2017), and other countries have used annular fuel assembly for active pressurized water reactors, proving many advantages of the annular fuel assembly. Rowinski et al (2015)described the innovative model of annular fuel design for lead-cooled fast reactors. Due to the introduction of the inner flow field, the research on the mechanical properties of annular fuel assembly is of great significance.…”

Section: Introductionmentioning

confidence: 99%

Thermal-hydraulic characteristics in inner and outer wire-wrapped for a fast reactor annular fuel assembly

et al. 2022

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The annular fuel has dual-cooled surfaces internally and externally. Compared with traditional cylindrical fuel, the inner flow field is introduced on the annular fuel assembly, and wire-wrapped can influence the inner flow field. In order to research and compare the effect of wire-wrapped on the sub-channels and inner flow field of the fast reactor annular fuel assembly, thermal-hydraulic properties of the fast reactor annular fuel assembly with the inner and outer wire-wrapped are investigated in this research. The flow, heat transfer, and mechanical properties are analyzed, including temperature, transverse velocity, pressure drop, and thermal stress. The temperature of three sub-channels is the key that influences the temperature characteristics. The wire-wrapped reduces the coolant temperature gradient, flattens the coolant outlet temperature, and makes the coolant outlet temperature more uniform. The transverse velocity of coolant in the sub-channels is about three times that of in the inner flow field. From the perspective of the inner flow field, the increase in the number of wire-wrapped leads to an increase in transverse velocity. The number of wire-wrapped is not as good as possible from the perspective of sub-channels. The pressure drop of the sub-channels is larger than the pressure drop of the inner flow field. No matter the sub-channels or the inner flow field, the increase in the number of wire-wrapped will cause an increase in the pressure drop. The thermal-hydraulic properties of one inner and outer wire-wrapped are better than other models. The stress in the cladding is about 1.75 times the stress in the annular fuel rod, and the stress in the inner cladding is higher than that in the outer cladding. The research provides a reference for the optimization design of the fuel assembly.

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Section: Introductionmentioning

confidence: 99%

Thermal-hydraulic characteristics in inner and outer wire-wrapped for a fast reactor annular fuel assembly

et al. 2022

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“…Annular fuel has advantages of shorter heat transfer path and larger heat transfer area than traditional solid rod fuel. It has been considered as a novel fuel design for different types of nuclear reactor concepts, such as liquid cooled fast reactor (Rowinski and White, 2015), CANDU (Nava Dominguez and Rao, 2020), gas cooled reactor (Han et al, 2006) and water cooled reactor (Shin and Chun, 2012;Kwon and Kim, 2019).…”

Section: Introductionmentioning

confidence: 99%

Researches on Special Thermal Hydraulic Phenomena of Annular Fuel Assembly by Sub-Channel Analysis Code-NACAF

Zhang

Shan

et al. 2021

Front. Energy Res.

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Dual cooled annular fuel is a novel fuel design, which has the potential to improve the reactor power density while maintaining or improving its safety margin. The effects of tight-lattice geometry, fuel burnup, fuel expansion, coolant channel blockage on the thermal hydraulic performance of annular fuel is studied to illustrate its special features in this paper. A sub-channel analysis code named NACAF, which includes empirical constitutive models in consideration of tight-lattice effects on prediction of pressure drop, critical heat flux and turbulent mixing, channel blockage model, heat conduction model for dual surface cooling condition, coolant flowrate distribution between inner and outer channel, is developed for annular fuel assembly or core analysis based on homogenous fluid model. Validation work is carried out with comparing NACAF results with analytical solutions, as well as numerical results of existing sub-channel code for annular fuel, such as VIPRE-01 and TAFIX. Comparison results demonstrates NACAF’s prediction error is acceptable and it has the ability to simulate thermal hydraulic performance of annular fuels or annular fuel bundles. Based on the developed and verified NACAF, the special thermal hydraulic phenomena of annular fuel are studied to clarify the features of annular fuel.

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Numerical study on the thermal hydraulic characteristics in mixed pattern of wire-wrapped bundle for fast reactor annular fuel assembly

Yuan

Guo²,

Zhou³

et al. 2023

Annals of Nuclear Energy

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Innovative model of annular fuel design for lead-cooled fast reactors

Cited by 5 publications

References 34 publications

Thermal-hydraulic characteristics in inner and outer wire-wrapped for a fast reactor annular fuel assembly

Thermal-hydraulic characteristics in inner and outer wire-wrapped for a fast reactor annular fuel assembly

Researches on Special Thermal Hydraulic Phenomena of Annular Fuel Assembly by Sub-Channel Analysis Code-NACAF

Numerical study on the thermal hydraulic characteristics in mixed pattern of wire-wrapped bundle for fast reactor annular fuel assembly

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