Thermal analysis of CASTOR RBMK-1500 casks during long-term storage of spent nuclear fuel

Poškas, Robertas; Šimonis, Vytautas; Poškas, Povilas; Sirvydas, A.

doi:10.1016/j.anucene.2016.09.031

Cited by 23 publications

(6 citation statements)

References 5 publications

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“…Modeling was performed for characteristic container storage periods: at 100, 200 and 300 years of storage but analysis include also the data [17] for just loaded casks with SNF pre-stored in water pools for 5 years and at 50 years storage. Validation of the numerical model was performed by comparing modelling results of cask surface temperatures with surface temperature measurements of a commercial cask for winter conditions (ambient temperature -6 o C taking into account real burnup of the loaded fuel bundles [26].…”

Section: Methodsmentioning

confidence: 99%

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Modeling of decay heat removal from CONSTOR RBMK-1500 casks during long-term storage of spent nuclear fuel

Poškas

Šimonis

Jouhara

et al. 2019

Energy

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Management of spent nuclear fuel is a very important part in the whole cycle of nuclear energy generation. Ignalina nuclear power plant operated two RBMK-1500 reactors that are now being decommissioned. After careful consideration "dry" storage technology in casks was selected for the interim storage of spent nuclear fuel (SNF) for up to 50 years. SNF after pre-storage time in water pools for not less than 5 years is loaded into cast-iron or metal-concrete casks. In this paper decay heat removal was modeled from specific GNB (Gesellschaft für Nuklear Behälter GmbH) metalconcrete (CONSTOR RBMK-1500) casks for the long-term storage period up to 300 years. The ALGOR code was used for the numerical modeling of the distribution of the heat fluxes and temperatures in a loaded cask placed in an open type storage facility in both summer and winter taking into account local environmental conditions. A local sensitivity analysis of the impact of fuel parameter uncertainties is also performed.

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Section: Methodsmentioning

confidence: 99%

“…R. Poškas et al [17] analyzed the long-term extended storage of SNF (up to 300 years) in the cast iron non-ventilated CASTOR casks at the Ignalina NPP from a thermal point of view. A cask was modeled assuming it is at an open type storage facility in summer and winter conditions.…”

Section: Introductionmentioning

confidence: 99%

Modeling of decay heat removal from CONSTOR RBMK-1500 casks during long-term storage of spent nuclear fuel

Poškas

Šimonis

Jouhara

et al. 2019

Energy

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“…The determination of the thermal state of containers with SNF is an important component in ensuring the safety of the SNF dry storage during the entire service life of the storage facility. Therefore, a number of thermal state studies have been carried out for storage containers with SNF from WWER-1000 [1,2] (the method will be transformed for storage modules with RBMK-1000 fuel) and RBMK-1500 [3,4] reactors.…”

Section: Introductionmentioning

confidence: 99%

Comparative Analysis of Numerical Methods Used for Thermal Modeling of Spent Nuclear Fuel Dry Storage Systems

Alyokhina¹,

Matsevity²,

Дудкин³

et al. 2019

Problems of Atomic Science and Technology

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Management of spent nuclear fuel is a very important part in the whole cycle of nuclear energy generation. Usually “dry” storage technology in casks is selected for the interim storage of spent nuclear fuel for up to 50 years after pre-storage time in water pools. In this paper, two case studies were carried out to highlight the differences and similarities between Ukraine and Lithuania in spent nuclear fuel storage.

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“…С. В. Альохіна1,2 , О. М. Дибач3 , А. О. Костіков 1 , Д. О. Дімітрієва 3 1 Інститут проблем машинобудування ім. А. М. Підгорного НАН України, м. Харків, Україна 2 Харківський національний університет імені В. Н. Визначення теплового стану контейнерів з відпрацьованим ядерним паливом є важливою складовою забезпечення безпеки його сухого зберігання протягом усього терміну експлуатації сховища.…”

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Prediction of the maximum temperature inside container with spent nuclear fuel

Alyokhina

Dybach

Kostikov

et al. 2018

Nucl. and Rad. Safe.

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The definition of the thermal state of containers with spent nuclear fuel is important part of the ensuring of its safe storage during all period of storage facility operation. The this work all investigations are carried out for the storage containers of spent nuclear fuel of WWER-1000 reactors, which are operated in the Dry Spent Nuclear Fuel Storage Facility in Zaporizhska NPP. The analysis of existing investigations in the world nuclear engineering science concerning to the prediction of maximum temperatures in spent nuclear fuel storage container is carried out. The absence of studies in this field is detected and the necessity of the dependence for the maximum temperature in the storage container and temperature of cooling air on the exit of ventilation duct from variated temperatures of atmospheric air and decay heat formulation is pointed out. With usage of numerical simulation by solving of the conjugate heat transfer problems, the dependence of maximum temperatures in storage container with spent nuclear fuel from atmospheric temperature and decay heat is detected. The verification of used calculation method by comparison of measured air temperature on exit of ventilation channels and calculated temperature of cooling air was carried out. By regression analysis of numerical results of studies the dependence of ventilation air temperature from the temperature of atmospheric air and the decay heat of spent nuclear fuel was formulated. For the obtained dependence the statistical analysis was carried out and confidence interval with 95% of confidence is calculated. The obtained dependences are expediently to use under maximum temperature level estimation at specified operation conditions of spent nuclear fuel storage containers and for the control of correctness of thermal monitoring system work.

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Thermal analysis of CASTOR RBMK-1500 casks during long-term storage of spent nuclear fuel

Cited by 23 publications

References 5 publications

Modeling of decay heat removal from CONSTOR RBMK-1500 casks during long-term storage of spent nuclear fuel

Modeling of decay heat removal from CONSTOR RBMK-1500 casks during long-term storage of spent nuclear fuel

Comparative Analysis of Numerical Methods Used for Thermal Modeling of Spent Nuclear Fuel Dry Storage Systems

Prediction of the maximum temperature inside container with spent nuclear fuel

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