Heat transfer enhancement in dry cask storage for nuclear spent fuel using additive high density inert gas

Yoo, Hee Sang; Yoo, Seung Hun; Kim, Eung Soo

doi:10.1016/j.anucene.2019.04.018

Cited by 18 publications

(11 citation statements)

References 16 publications

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“…Safety issues regarding loss of coolant condition and maintaining water chemistry of wet storage facility have been considered after Fukushima Daiichi accident. 4,5 The spent fuel stored during certain period at wet storage facility is managed by interim storage facility. Therefore, spent fuel dry storage cask becomes one of key facility in spent fuel management process.…”

Section: Introductionmentioning

confidence: 99%

“…Saturation issue will be continued until the determination and construction of repossessing or disposal facility. Safety issues regarding loss of coolant condition and maintaining water chemistry of wet storage facility have been considered after Fukushima Daiichi accident 4,5 . The spent fuel stored during certain period at wet storage facility is managed by interim storage facility.…”

Section: Introductionmentioning

confidence: 99%

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Effective energy management design of spent fuel dry storage based on hybrid control rod‐heat pipe

Kim

Bang

2020

Int J Energy Res

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Spent fuel dry storage cask, which stores the spent fuel from wet storage facility to final processing, has been developed and managed. Even though thermal management mechanisms of dry storage casks secure the thermal integrity of the cask, improvement of thermal management capacity of dry storage cask would enhance thermal margin against unforeseen off-normal conditions with increasing specific storage capacity. Ulsan National Institute of Science and Technology (UNIST) CANister (UCAN) utilizing the new-type thermosyphon heat pipe, is under development as an advanced design of spent fuel dry storage cask. Hybrid control rod-heat pipe, which is an annular thermosyphon by containing neutron absorber, is a key component of UCAN. Heat removal performance of the hybrid control rod-heat pipe was analyzed bya series of experiment withtest facility simulating single fuel assembly with full height. The UCAN fuel assembly showed the reduced structural and fuel temperatures compared to bare fuel assembly of conventional cask designs, exhibitingimproved thermal margin. According to experimentally observed heat removal rate of the hybrid control rod-heat pipe, UCAN design could extend manageable thermal capacity from 13.3% to 33.8%. The removeddecay heat through hybrid control rod-heat pipe could be reused in electricity generation with stirling engine and thermoelectric devices improving energy management efficiency. Intermittent boiling accompanying geyser phenomena was frequently occurred inside the test section, and the boiling behaviors according to fill ratios (FRs) and operating pressures dominated the heat removal performances. The hydrostatic pressure owing to large aspect ratio affected differentiated thermal-hydraulic behaviors compared to conventional thermosyphons. To develop heat transfer and hydraulic models of the hybrid control rod-heat pipe, geyser phenomenon inside the test section wasdiscussed physically. This workexhibited the feasibility of UCAN design and provides fundamental physics on intermittent boiling of thermosyphon operating at sub-atmospheric pressures.

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Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Effective energy management design of spent fuel dry storage based on hybrid control rod‐heat pipe

Kim

Bang

2020

Int J Energy Res

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“…This error was reported to the code creators, whom confirmed that the error was happening when the upper plenum model was used. The results (thermally speaking) were fairly accurate, but this is mostly due to the fact that the TN-24P is a low pressure cask (1 atmosphere when it is loaded), therefore convection plays a relatively small role in dissipating the heat, the error would be compounded as the pressure (and therefore the convection), is increased (Yoo et al, 2019). This error was estimated severe enough to stop using the code for this thesis.…”

Section: Cobra Sfsmentioning

confidence: 94%

“…If CFD tools could only be used to perform validation of existing experimental results, they would not be very useful (whether in the nuclear industry or others). In this sense other works have proposed new ways in which a dry cask could be improved, as previously explain this could be using a gas mixture (Yoo et al, 2019), or introducing heat pipes in the fuel elements of a dry cask to lower its temperature (Jeong and Bang, 2016). This study showed that heat pipes (are passive heat transfer devices that use both conduction and phase change to extract heat from a source), are capable of lowering up to 95 K the PCT when five heat pipes were used for each assembly.…”

Section: Figure 13 Channel Description Cobra Sfsmentioning

confidence: 95%

“…Once the model has been validated it can be used for further work, for example using the model to try to obtain a smaller scale model and then validate that against a dummy model (Yoo et al, 2010b). In (Yoo et al, 2019), the author tries to improve the thermal behavior of the cask by mixing the helium with high density inert gases (such as Xenon, CO2, Krypton or Argon) at different pressures and mixing ratios. The idea was that by increasing the density of the gases, the increase buoyancy of the mixed gas would improve the thermal response.…”

Section: Figure 13 Channel Description Cobra Sfsmentioning

confidence: 99%

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Methodology for spent fuel dry cask thermal-hydraulics analysis for long term storage

Rodríguez¹

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One of the largest challenges facing the nuclear industry is with the management of nuclear spent fuel. As the available space in the nuclear spent pools is shrinking, nuclear power plants have needed a temporal solution to storage the nuclear spent fuel before a more definitive or a country centralized solution is coming. This necessity has been met by using nuclear dry casks. This technology has been used for a long time but with the increase in burnout in the fuel and in the casks lifetime due to lack of progress in constructing central storage facilities has meant that more knowledge is needed regarding the behavior of the fuel during this part of its cycle.In this sense, one of the key parameters is the Peak Cladding Temperature (PCT), which should not surpass 400 °C (USNRC, 2003). At that temperature, the hydrides dissolved in the clad can change their orientation and could cause embrittlement in the clads that could lead to rod failure. In order to ensure that this temperature limit is not surpass, simulations are needed to verify it. These simulations can be done with Finite Elements (FE) codes such as Ansys Mechanical and with sub-channel codes such as COBRA SFS, but the most common way to simulate the dry cask thermal behavior is through Computational Fluid Dynamics (CFD) codes like Ansys Fluent, STAR-CCM+, CFX or OpenFoam, among others.V

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Numerical simulation of coupling heat transfer and thermal stress for spent fuel dry storage cask with different power distribution and tilt angles

Cheng

Tao

et al. 2023

NUCL SCI TECH

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Heat transfer enhancement in dry cask storage for nuclear spent fuel using additive high density inert gas

Cited by 18 publications

References 16 publications

Effective energy management design of spent fuel dry storage based on hybrid control rod‐heat pipe

Effective energy management design of spent fuel dry storage based on hybrid control rod‐heat pipe

Methodology for spent fuel dry cask thermal-hydraulics analysis for long term storage

Numerical simulation of coupling heat transfer and thermal stress for spent fuel dry storage cask with different power distribution and tilt angles

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