Evaluation of radioactive material leakage through the fuel cladding as result of diffusion processes during the long-term storage of spent nuclear fuel

Alyokhina, Svitlana; Maksymov, Maksym; Romashov, Yurii Volodymyrovych

doi:10.1016/j.jksues.2021.08.006

Cited by 3 publications

(3 citation statements)

References 16 publications

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“…There are several studies on the handling and storage of spent fuel [1][2][3][4][5][6][7][8][9][10]. After remaining in interim wet storage for more than 4 years, spent fuel can be moved to dry cask storage.…”

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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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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“…In general, inspectors are looking for a specific nuclear material and radioactive material generated and leaked from nuclear power plants, nuclear fuel-related facilities, reprocessing facilities, and/or enrichment plants. Nuclear materials and radioactive materials spread far due to natural phenomena or may be leaked while transported to other facilities, and thus there is a possibility that these materials will be distributed in a wide area around the facility or along the movement route [7]. To obtain sufficient data for a short period of time, it is essential to perform sampling in an area where nuclear materials and radioactive materials are expected to exist.…”

Section: Introductionmentioning

confidence: 99%

“…The radioactive materials found around reprocessing facilities are 89 Sr, 90 Sr, 131 I, 137 Cs, and 140 Ba. In addition to the substances described above, other detected substances in the Chernobyl and Fukushima nuclear accident areas are 110 mAg, 129 mTe, and 134 Cs [7][8][9][10]. Among various radioactive materials, 137 Cs is a target material for verification because it can be measured from a long distance, has a long half-life of 30 years, is released in large amounts from nuclear activity, and has a very slow movement speed in soil [10].…”

Section: Introductionmentioning

confidence: 99%

Development of a CsI(Tl) scintillator based gamma probe for the identification of nuclear materials in unknown areas

Kim¹,

Lee²,

Jeong³

et al. 2022

J. Inst.

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In case of nuclear accident or an act of terrorism, such as planting a dirty bomb, the nuclear and radioactive materials could be spread over a large area. The environmental radioactivity information has to be obtained rather fast in order to secure the safety of any activity in these potentially high-level radiation contaminated areas. In addition, a lack of both social infrastructure and environmental radiation information may be expected in this area. Therefore, the sampling process must be carried out in a timely and efficient manner. In this study, a probe operated via a distribution method was developed to improve the efficiency of the sampling process by identifying the location and nuclides of leaked materials. For distribution type operation, CsI(Tl) and SiPM were applied to the sensor part of the probe to operate at low voltage operation and for durability. In addition, the power consumption of the data acquisition module and the weight of the probe were optimized for distribution through drones, battery operation, and wireless communication. The energy resolution of this probe was 10.84% at 662 keV and it showed adequate characteristics in the spectrum of nuclear materials. In addition, the practical operability of this probe was verified through determination of the minimum detectable dose rate condition and the difference in the measured values based on the landing orientation.

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Shielding and corrosion properties of the Alloy 709 as canister material for spent nuclear fuel dry casks

Alsmadi

Bourham²

2023

Defence Technology

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Evaluation of radioactive material leakage through the fuel cladding as result of diffusion processes during the long-term storage of spent nuclear fuel

Cited by 3 publications

References 16 publications

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

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

Development of a CsI(Tl) scintillator based gamma probe for the identification of nuclear materials in unknown areas

Shielding and corrosion properties of the Alloy 709 as canister material for spent nuclear fuel dry casks

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