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

Poškas, Robertas; Šimonis, Vytautas; Jouhara, Hussam; Poškas, Povilas

doi:10.1016/j.energy.2018.12.217

Cited by 16 publications

(3 citation statements)

References 18 publications

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“…Five other cases have been run to address the temperature of the air cooling the system, as it acts as the heat sink. The choice of decay power and external air temperature as the main parameters for the sensitivity analysis (SA) is additionally supported by the results obtained in [46], in which both parameters seem to play a role when analyzing the PCT (and the cask external wall) in a CONSTOR RBMK-1500 cask.…”

Section: Sensitivity Casesmentioning

confidence: 80%

Uncertainty and Sensitivity Analysis of a Dry Cask for Spent Nuclear Fuel

et al. 2022

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Nuclear safety relies to a good extent on thoroughly validated codes. However, code predictions are affected by uncertainties that need to be quantified for a more accurate evaluation of safety margins. In this regard, the present paper proposes a preliminary uncertainty and sensitivity analysis of the thermal behavior of a concrete-based dry cask for spent nuclear fuel storage, employing the MELCOR code and a series of MATLAB scripts. As thermal behavior is of utmost importance for the fulfillment of United States Nuclear Regulatory Commission (USNRC) safety requirements, the Peak Cladding Temperature (PCT) has been addressed as the key Figure of Merit (FOM). Variables related to the main heat transfer mechanisms have been selected as input parameters for the uncertainty quantification, whereas heat source and heat sink, namely decay power and external air temperature, have been dealt with in a separate sensitivity analysis. The results show that the selected parameters have a weak influence on the PCT, whereas it is strongly related to the decay power and external air temperature values. In any case, PCT stays below the regulatory threshold even under the considered off-normal conditions.

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Section: Sensitivity Casesmentioning

confidence: 80%

Uncertainty and Sensitivity Analysis of a Dry Cask for Spent Nuclear Fuel

et al. 2022

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“…Poškas, Šimonis, Jouhara, and Poškas (2019) developed a decay heat removal modeling kinetics during long‐term storage time. The model included up to 300 years of CONSTOR RBMK‐1500 casks having a metal concrete composition, together with the addition of sensitivity analysis of multiple parameters.…”

Section: Spent Nuclear Fuel Managementmentioning

confidence: 99%

Radioactive waste: A review

Deng

Zhang

Dong

et al. 2020

Water Environment Research

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The reviewed papers presented here provide a general overview of worldwide radioactive waste-related studies conducted in 2019. The current review includes studies related to safety assessments, decommission and decontamination of nuclear facilities, fusion facilities, and transportation. Further, the review highlights radioactive wastewater decontamination, management solutions for the final disposal of low-and highlevel radioactive wastes (LLRW and HLRW), interim storage and final disposal options for spent fuel (SF), and tritiated wastes, with a focus on environmental impacts due to the mobility of radionuclides in the ecosystem, water and soil along with other research progress made in the management of radioactive waste. © 2020 Water Environment Federation • Practitioner points • The release of radionuclides and their subsequent fate and transport in the environment poses public health concern and has stimulated recent research on the waste management techniques. • Seeking a safe and environmental-friendly solution is the current trend for existing and projected inventories of radioactive waste. • Significant progress in the field of geological disposal of radioactive waste has been made in the last two decades.

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“…One method of increasing the heat removal from concrete dry storage is adding an air gap as a ventilation channel in the dry storage There are many studies on spent fuel heat removal from non-ventilated dry storage and ventilated dry storage. Several studies on heat removal from non-ventilated dry storage, among others, have discussed decay heat removal after a long-term storage period using the ALGOR code [11,12], heat transfer enhancement in non-ventilated dry storage using inert gas [13], and minimizing the deviation of the thermal load in a non-ventilated dry cask [14].…”

Section: Introductionmentioning

confidence: 99%

Theoretical and Experimental Analysis on Influence of Natural Airflow on Spent Fuel Heat Removal in Dry Cask Storage

et al. 2022

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A key issue contributing to the success of NPP technology is the safe handling of radioactive waste, particularly spent nuclear fuel. According to the IAEA safety standard, the spent fuel must be stored in interim wet storage for several years so the radiation and the decay heat of the spent fuel will decrease to the safe limit values, after which the spent fuel can be moved to dry storage. In this study, we performed a theoretical analysis of heat removal by natural convection airflow in spent nuclear fuel dry storage. The temperature difference between the air inside and outside dry storage produces an air density difference. The air density difference causes a pressure difference, which then generates natural airflow. The result of the theoretical analysis was validated with simulation software and experimental investigation using a reduced-scale dry storage prototype. The dry storage prototype consisted of a dry cask body and two canisters stacked to store materials testing reactor (MTR) spent fuel, which generates decay heat. The cask body had four air inlet vents on the bottom and four air outlet vents at the top. To simulate the decay heat from the spent fuel in the two canisters, the canisters were wrapped with an electric wire heater that was connected to a voltage regulator to adjust the heat power. The theoretical analysis results of this study are relatively consistent with the experimental results, with the mean relative deviation (MRD) values for the prediction of air velocity, the heat rate using natural airflow, and the heat rate using the thermal resistance network equation are +0.76, −23.69, and −29.54%, respectively.

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

Cited by 16 publications

References 18 publications

Uncertainty and Sensitivity Analysis of a Dry Cask for Spent Nuclear Fuel

Uncertainty and Sensitivity Analysis of a Dry Cask for Spent Nuclear Fuel

Radioactive waste: A review

Theoretical and Experimental Analysis on Influence of Natural Airflow on Spent Fuel Heat Removal in Dry Cask Storage

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