A study on the flow characteristics in an annular type fuel pellet of PWR

Kwon, Yuri; Yang, Yuesuo; Kim, J. S.; Kwon, Soon Bum

doi:10.1007/s12206-012-1205-x

Cited by 7 publications

(4 citation statements)

References 2 publications

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“…The physical properties applied to this analysis are adopted from 6.5500 × 10 −9 1.0412 × 10 −8 [1]. Material properties of the pellet and cladding at operating temperature are given in Tables 2 and 3, and the heat transfer coefficients can be found in [4][5][6][7]. In the thermoelasticplastic-creep analysis, we used the mathematical formula as a function of temperature obtained from experiments in an actual nuclear reactor.…”

Section: Thermal and Mechanical Materials Propertiesmentioning

confidence: 99%

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Comparison of the Characteristics of Solid Type and Annular Type Nuclear Fuels Using Thermoelastic-Plastic-Creep FEM

Kwon

Lee

Yun

2016

Mathematical Problems in Engineering

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The purpose of this study is to compare the characteristics of two types of nuclear fuel using the finite element program of thermoelastic-plastic-creep analysis. The analyzed fuel rods are of two types, solid and annular ones, and their thermomechanical characteristics are compared. Thermoelastic-plastic-creep analyses were made using an in-house finite element analysis program that adopts the “effective-stress-function” algorithm. The temperature-dependent material properties, which were obtained from the experiments for actual nuclear reactors, are adopted. The effects of type of fuel systems are revealed in both stresses and temperature distributions. The maximum tensile and compressive hoop stress of pellet and cladding are monitored to evaluate the mechanical behavior, and the maximum temperature is used to evaluate the thermal behavior. Although the annular type of fuel has certain disadvantage, it would be used very effectively or safely in future nuclear power plants.

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Section: Thermal and Mechanical Materials Propertiesmentioning

confidence: 99%

“…The recent nuclear fuels are of solid type [1,2] and are generally utilized in the pressurized water nuclear reactors. Annular types of fuel [3][4][5][6][7] have been introduced to improve the performance of nuclear power plant. Annular fuels have wider surfaces, which promote the transfer of generated heat into the cooling water.…”

Section: Introductionmentioning

confidence: 99%

Comparison of the Characteristics of Solid Type and Annular Type Nuclear Fuels Using Thermoelastic-Plastic-Creep FEM

Kwon

Lee

Yun

2016

Mathematical Problems in Engineering

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“…Finite element analysis procedures of nuclear fuels have been developed by many researchers [5][6][7] and mostly applied to basic designs of them. The nominal operation of the nuclear power plant is known to exhibit the highest pellet temperature between 1100∼1400 ∘ C and the clad temperature 400∼600 ∘ C [8].…”

Section: Finite Element Analysis Of Nuclear Fuelsmentioning

confidence: 99%

A Critical Heat Generation for Safe Nuclear Fuels after a LOCA

Kim

Kim²,

Cho

et al. 2014

Science and Technology of Nuclear Installations

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This study applies a thermo-elasto-plastic-creep finite element procedure to the analysis of an accidental behavior of nuclear fuel as well as normal behavior. The result will be used as basic data for the robust design of nuclear power plant and fuels. We extended the range of mechanical strain from small or medium to large adopting the Hencky logarithmic strain measure in addition to the Green-Lagrange strain and Almansi strain measures, for the possible large strain situation in accidental environments. We found that there is a critical heat generation after LOCA without ECCS (event category 5), under which the cladding of fuel sustains the internal pressure and temperature for the time being for the rescue of the power plant. With the heat generation above the critical value caused by malfunctioning of the control rods, the stiffness of cladding becomes zero due to the softening by high temperature. The weak position of cladding along the length continuously bulges radially to burst and to discharge radioactive substances. This kind of cases should be avoid by any means.

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“…Due to the introduction of the inner flow field, the research on the mechanical properties of annular fuel assembly is of great significance. Zhao et al (2004), Kwon et al (2013),and Xu et al (2020 analyzed the mechanical properties, such as thermal stress and displacement of PWR with annular fuel assembly. The abovementioned studies on the annular fuel assembly are focused on the PWR without the effect of the wire-wrapped.…”

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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A study on the flow characteristics in an annular type fuel pellet of PWR

Cited by 7 publications

References 2 publications

Comparison of the Characteristics of Solid Type and Annular Type Nuclear Fuels Using Thermoelastic-Plastic-Creep FEM

Comparison of the Characteristics of Solid Type and Annular Type Nuclear Fuels Using Thermoelastic-Plastic-Creep FEM

A Critical Heat Generation for Safe Nuclear Fuels after a LOCA

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

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