Unsteady heat exchange at the dry spent nuclear fuel storage

Alyokhina, Svitlana; Kostikov, А.

doi:10.1016/j.net.2017.07.029

Cited by 17 publications

(6 citation statements)

References 8 publications

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“…Other factors of influence onto the thermal state of SNF was investigated in [13] (influence of the daily temperature fluctuations) and [14] (influence of solar irradiation). It is found that both of them are not dangerous for spent nuclear fuel stored inside concrete containers.…”

Section: Fig 6 Classification Of the Factors Which Have Influence On The Thermal State Of Snfmentioning

confidence: 99%

Scientific Basis of Thermal Safety Analysis of Dry Storage of Spent Nuclear Fuel on Zaporizhska NPP

Alyokhina¹,

Kostikov²,

Koriahina³

2020

Problems of Atomic Science and Technology

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Now only one Dry Storage Facility of Spent Nuclear Fuel (DSFSNF) is operated in Ukraine. It is the facility on Zaporizhska NPP. Many different thermal investigations were done for ventilated containers of DSFSNF. In this study the generalization of scientific approaches to the thermal safety assessment are carried out. The multi-stage approach to the definition of thermal state of containers' group, single container, spent fuel assemblies and fuel rods was developed. Detailed thermal profiles of spent fuel assemblies inside storage container were calculated. With usage of multi-stage approach the thermal simulations of the influence of outer factors onto thermal state of containers was carried out. Results of thermal investigations were generalized and factors, which are influence on thermal state of containers, are detected. The method of spent nuclear fuel thermal state prediction and suggestion for improving the system of thermal monitoring were proposed.

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Section: Fig 6 Classification Of the Factors Which Have Influence On The Thermal State Of Snfmentioning

confidence: 99%

Scientific Basis of Thermal Safety Analysis of Dry Storage of Spent Nuclear Fuel on Zaporizhska NPP

Alyokhina¹,

Kostikov²,

Koriahina³

2020

Problems of Atomic Science and Technology

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“…A cask with a corrugated external surface will not exceed the limits for both the fuel cladding and outer surface temperatures. Unsteady thermal processes in storage containers with spent nuclear fuel were simulated [9]. The daily fluctuations of outer ambient temperatures were taken into account.…”

Section: Figure (1): Outline Of the Concrete Casksmentioning

confidence: 99%

Investigation of Thermal Hydraulic Behavior of Dry Spent Fuel Cask Under Forced Convection

helmy

Ahmed

Elnaggar

2019

Arab Journal of Nuclear Sciences and Applications

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The thermal-hydraulic behavior of the spent fuel in dry storage casks under forced convection mode is experimentally and numerically investigated. For this purpose, a test rig is designed and constructed to simulate the cooling loop cask. This test rig contains 21 spent fuel discharged from a pressurized water reactor (PWR). A numerical simulation is performed by ANSYS-CFX fluid dynamic code. The effect of decay heat generation and inlet air velocity are investigated. The results show that the increase in the inlet air velocity improves the coolability of the fuel, while the increase in decay heat leads to a decrease in the coolability of the fuel. Within the range (1.1< V < 2.8 m/s) for inlet air velocity and heaters power (630 < Q < 1260 watt), a new empirical correlation has been obtained for Nusselt number, Nu as a function in Reynolds number, Re. The comparisons between experimental and numerical results show a good agreement.

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“…The encoder is mounted on the shaft end of the reel and measures the lift distance directly with high accuracy. It is also equipped with a position display instrument to feed back the position information of the wire rope [3]. The intelligent multi-turn absolute encoder is used in this design.…”

Section: Position Measurementmentioning

confidence: 99%

Design of Control System about Spent Fuel Associated Assembly Handling Tool

Hu¹,

Pingliang²,

Cao³

2019

dtetr

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This paper expounds a kind of handling tool with accurate alarm, fault analysis, and accident avoidance. The tool contains position & tension measurement, server driving and PLC-300 software, it can insure safety of spent fuel assembly during transfer. PrefaceDuring outage of NPP, the spent fuel associated components need to be replaced in the spent water pool. The spent fuel associated assembly handling tools mainly include RCCA handling tool and burnable poison assembly handling tool, which are used for switching the RCCA, burnable poison assembly respectively.The handling tools imported by Daya Bay Nuclear Power in the 1990s solved the basic functions of crawling, lifting, and releasing. The mechanical alarm device was designed to visualize the current position of the relevant components which can meet the basic functional requirements. The equipment is expensive and now is now ageing. A domestic company has referenced the design of imported equipment, but its application units were limited and the failures occurred frequently [1].When the handling tools which is developed at home and abroad change the associated components, they are prone to arise the safety risk that the single rod bending leads to the leakage of radioactive gas or the associated components crash and damage the fuel assembly, and may be accompanied by the foreign matter, which threatens the safety of the fuel assembly.Therefore, this article proposes a handling control system based on position, tension measurement and servo drive which includes tension accurate alarm, fault analysis, double start and stop criterion of position and tension, and the design of error prevention ,which can ensure the safety of fuel assembly and associated components.

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Unsteady heat exchange at the dry spent nuclear fuel storage

Cited by 17 publications

References 8 publications

Scientific Basis of Thermal Safety Analysis of Dry Storage of Spent Nuclear Fuel on Zaporizhska NPP

Scientific Basis of Thermal Safety Analysis of Dry Storage of Spent Nuclear Fuel on Zaporizhska NPP

Investigation of Thermal Hydraulic Behavior of Dry Spent Fuel Cask Under Forced Convection

Design of Control System about Spent Fuel Associated Assembly Handling Tool

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