Investigation of the Thermal Performance of a Vertical Two-Phase Closed Thermosyphon as a Passive Cooling System for a Nuclear Reactor Spent Fuel Storage Pool

Kusuma, Mukhsinun Hadi; Putra, Nandy; Antariksawan, Anhar Riza; Susyadi,; Imawan, Ficky Augusta

doi:10.1016/j.net.2016.10.008

Cited by 57 publications

(21 citation statements)

References 21 publications

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“…The heat pipe used is made of copper using demineralized water as the working fluid. Our results show that a straight wickless-heat pipe has excellent thermal performance and can be used as an alternative passive cooling technology to remove residual decay heat generated in the spent fuel storage pool when the blackout station occurs [7][8][9].…”

Section: Introductionmentioning

confidence: 91%

Effect of graphenenano-fluid on heat pipe thermal performance for passive heat removal in nuclear spent fuel storage pool

Rosidi

Putra

Kusuma

2018

IOP Conf. Ser.: Earth Environ. Sci.

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Abstract. After Fukushima Dai-ichi nuclear power reactor accident, spent fuel in spent fuel storage pool (SFSP) became an important thing to pay attention to, due to its decay heat release. If station blackout occurred, the active system for SFSP cooling system will experience malfunction to remove the product of decay heat. To keep spent fuel safe, heat pipe as passive cooling system device can be used to remove spent fuel decay heat even if the active cooling system failed. Heat pipe with 6 m on length will be proposed as apassive cooling system in SFSP. For that, it is necessary to analyze the effect of Graphene nano-fluid as heat pipe working fluid. The objective of this research is to know the effect on Graphene nano-fluid to enhance the heat pipe thermal performance and to know the heat transfer phenomena inside the heat pipe based on Graphene nano-fluid. Graphene nano-fluid with 1% weight concentration was used as working fluid with filling ratio of 80%. The experimental investigation is conducted with varying the evaporator heat load of 1000, 1500, 2000, and 2500 W. Water as coolant flows in thecondenser with aconstant volumetric flow rate of 8 L/min. The experiment results show that there was anovershoot, zigzag and stable phenomena inside the heat pipe. The thermal resistance of heat pipe is obtained at 0.015 o C/W. The use of Graphene nano-fluid as working fluid can enhance the heat pipe thermal performance significantly and can be used as an alternative working fluid in heat pipe for thepassive cooling system in SFSP of nuclear power plant.

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Section: Introductionmentioning

confidence: 91%

Effect of graphenenano-fluid on heat pipe thermal performance for passive heat removal in nuclear spent fuel storage pool

Rosidi

Putra

Kusuma

2018

IOP Conf. Ser.: Earth Environ. Sci.

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“…The RELAP5 has been validated for a wide range of reactor types and accident conditions using a variety of experiments and plant data, including TMI-2 (Allison & Hohorst, 2010). RELAP5 has also been used for experimental analyses other than in nuclear reactor facilities (Kusuma et al, 2017). As in the other field of technology, the use of a computer code is increasing in the safety analysis.…”

Section: Introductionmentioning

confidence: 99%

TRIGA-2000 Research Reactor Thermal-hydraulic Analysis using RELAP/SCDAPSIM/MOD3.4

Antariksawan¹,

Umar²,

Widodo³

et al. 2017

IJTech

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Any events presumed to risk the safety of a nuclear reactor should be analyzed. In a research reactor, the applicability of best estimate thermal-hydraulic codes has been assessed for safety analysis purposes. In this paper, the applicability of the RELAP/SCDAPSIM/MOD3.4 thermalhydraulic code to one Indonesian research reactor, which is named TRIGA-2000, is performed. The aim is to validate the model and use the model to analyze the thermal-hydraulic characteristics of TRIGA-2000 for main transient events considered in the Safety Analysis Report. The validation was done by comparing the calculation results with experimental data mainly in steady state conditions. The comparison of calculation results with the measurement data showed good agreement with little discrepancies. Based on these results, simulations for thermal-hydraulic analyses were performed for loss of coolant transients. The calculation results also properly depicted the physic of the thermal-hydraulic phenomena following the loss of coolant transients. These results showed the adequacy of the model. It could be shown that the engineered safety features of TRIGA-2000 play an important role in keeping the reactor safe from the risk of postulated loss of a coolant accident.

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“…However, the passive devices could not meet future challenging cooling demand because of the inherent limitation of the capillary pumping in terms of heat flux, transport distance and multiple heat source capabilities [10][11][12]. Meanwhile, high heat flux in advanced defense devices is found in radars, directed-energy laser and microwave weapon systems, and avionics.…”

Section: Intoroductionmentioning

confidence: 99%

Experimental study on a hybrid loop heat pipe

2017

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Abstract.A conventional loop heat pipe two-phase heat transfer device of passive system often can no longer meet the challenging cooling needs due to the inherent limitations of the capillary pumping which can lead to dry out. This study aims to create a loop heat pipe uses capillary wick copper sintered with centrifugal casting method. The stressing effort to overcome the dry-out by adding a diaphragm pump to accelerate the fluid transportation from the condenser to the evaporator (hybrid loop heat pipe, HLHP), where the pump is equipped with a reservoir and both installed on the liquid line. In testing the performance of HLHP also varying the filling ratio, FR: 50%, 60%, and 80%. The pump will be activated when the dry-out took place, by the piezo electric diaphragm pump with temperature controller installed in the evaporator that was set to activate the pump to work. From the results of the experimental, the pump successfully prevented the occurrence of dry out, and reduced the temperature of the evaporator from 130 o C to 80 o C, owing the pump distributed the working fluid from the condenser to the evaporator efficiently. The result indicated the best performance of HLHP was filling ratio, FR of 60%.

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Investigation of the Thermal Performance of a Vertical Two-Phase Closed Thermosyphon as a Passive Cooling System for a Nuclear Reactor Spent Fuel Storage Pool

Cited by 57 publications

References 21 publications

Effect of graphenenano-fluid on heat pipe thermal performance for passive heat removal in nuclear spent fuel storage pool

Effect of graphenenano-fluid on heat pipe thermal performance for passive heat removal in nuclear spent fuel storage pool

TRIGA-2000 Research Reactor Thermal-hydraulic Analysis using RELAP/SCDAPSIM/MOD3.4

Experimental study on a hybrid loop heat pipe

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