Subchannel analysis of supercritical light water-cooled fast reactor assembly

Yoo, Juhyun; Oka, Yoshiaki; Ishiwatari, Yuki; Yang, Jianwei; Liu, Jie

doi:10.1016/j.nucengdes.2006.11.005

Cited by 16 publications

(9 citation statements)

References 6 publications

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“…Because there is no available experimental data at supercritical pressure in the bundle scale, some of the design parameters have been taken for the SWFR fuel assembly. Different parameters of SWFR fuel assembly are shown in Table . The area that the coolant flows between the fuel rods of the reactor vessel are called subchannels.…”

Section: Numerical Analysismentioning

confidence: 99%

“…Another good reason to use hexagonal fuel assemblies is that fast reactors can become more reactive when fuel is pushed closer together. There is no additional need of moderation like water rods . The core consists of hexagonal seed and blanket fuel assemblies (Cao et al., 2008).…”

Section: Introductionmentioning

confidence: 99%

“…They are cooled via upward or downward flow of coolant as shown in Fig. . Downward flow is adapted in the blanket assemblies and some of the seed assemblies to get high core outlet temperatures.…”

Section: Introductionmentioning

confidence: 99%

“…There is no additional need of moderation like water rods. [3][4][5] The core consists of hexagonal seed and blanket fuel assemblies (Cao et al, 2008). They are cooled via upward or downward flow of coolant as shown in Fig.…”

Section: Introductionmentioning

confidence: 99%

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CFD analysis of heat transfer in hexagonal subchannels of super fast reactor in upward flow

Sahoo

Roul³

et al. 2017

Heat Trans. Asian Res.

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A super fast reactor is a fast spectrum, supercritical, water‐cooled reactor. This paper represents CFD analysis of heat transfer in hexagonal subchannels of super fast reactor using FLUENT in ANSYS. The numerical simulation of grid stability was done by considering different mesh sizes and the turbulence model for heat transfer of supercritical water was also carried out and compared with the experimental data. RNG k‐ϵ turbulence model with enhanced wall treatment was considered for simulations. Heat transfer and heat generation rate analysis of the outer surface rod wall is carried out with different subchannels by changing various parameters like boundary conditions and pitch‐to‐diameter ratio. The analyses reveal that the outer surface of the rod wall temperature decreases with increase in pitch‐to‐diameter ratio. Maximum coolant temperature rises in edge subchannels more than corner subchannels. Further analysis is carried out with different mass fluxes. Increases in mass flux has minimal effect on the maximum rod wall surface temperature. Maximum cladding surface temperature for the corner subchannel is less compared to the edge subchannel. Heat generation rate also decreases with increase in pitch‐to‐diameter ratio. This paper also investigates the buoyancy effect on subchannels with varying heat flux as boundary conditions considering constant mass flux.

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Section: Numerical Analysismentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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CFD analysis of heat transfer in hexagonal subchannels of super fast reactor in upward flow

Sahoo

Roul³

et al. 2017

Heat Trans. Asian Res.

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“…A subchannel analysis code for supercritical pressure, which was developed by the University of Tokyo 12,13) and verified against the PRANDTL experiment, has been applied to the thermal-hydraulic fuel assembly design and used to evaluate the MCST of the superfast reactor. The code is based on a control volume approach.…”

Section: Subchannel Analysismentioning

confidence: 99%

Fuel, Core Design and Subchannel Analysis of a Superfast Reactor

CAO

Oka

Ishiwatari

et al. 2008

Journal of Nuclear Science and Technology

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A compact supercritical water-cooled fast reactor (superfast reactor) core with a power of 700 MWe is designed by using a three-dimensional neutronics thermal-hydraulic coupled method. The core consists of 126 seed assemblies and 73 blanket assemblies. In the seed assemblies, 251 fuel rods, consisting of MOX pellets, stainless steel (SUS304) cladding, and fission gas plenum are arranged into a tight triangle lattice along with 19 guide tubes for control rods and instrumentation. A zirconium hydride (ZrH) layer is employed in the blanket assemblies to reduce void reactivity. The results of the coupling three-dimensional neutronics and thermal hydraulic calculations show that this core has a high power density of 158.8 W/cm 3 with a maximum linear heat generation rate (MLHGR) less than 39 kW/m, that an average coolant outlet temperature of 500 C is achieved with a maximum cladding surface temperature (MCST) less than 650 C, and that void reactivity coefficients are negative throughout the cycle. Since the thermal-hydraulic part of the core design is based on single-channel analyses, subchannel analyses are also performed on all the seed assemblies to clarify the influence of cross-flow.

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