Submerged demineralizer system vessel shipment report

Quinn, G.J.; Henrie, J.O.; Greenborg, J.

doi:10.2172/6854167

Cited by 10 publications

(3 citation statements)

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“…The zeolite particles are not as fine as the core debris expected in the filter canisters, but they are less dense and more porous. The resulting calculated gas generation rate was later confirmed by measurement (Quinn et al 1984).…”

Section: )mentioning

confidence: 65%

Evaluation of special safety issues associated with handling the Three Mile Island Unit 2 core debris

Henrie¹,

Appel²

1985

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Section: )mentioning

confidence: 65%

Evaluation of special safety issues associated with handling the Three Mile Island Unit 2 core debris

Henrie¹,

Appel²

1985

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“…Furthermore, the contaminated water in 1F includes a considerable quantity of salts from seawater. The presence of salts makes the situation different from that experienced in the reactor water treatment 5,6) after the accident at Three Mile Island Unit 2.…”

Section: Introductionmentioning

confidence: 90%

Measurement and Evaluation of Hydrogen Production from Mixtures of Seawater and Zeolite in Decontamination of Radioactive Water

Kumagai

NAGAISHI

Kimura

et al. 2021

Insights Concerning the Fukushima Daiichi Nuclear Accident Vol. 4

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Zeolite is used for the decontamination of radioactive water, which contains salts from seawater, accumulated in the Fukushima Daiichi Nuclear Power Plant. The evaluation of hydrogen production by water radiolysis during the decontamination process is important for safe operation. Thus, hydrogen production from a mixture of zeolite and seawater was studied by a γ-radiolysis experiment, and the hydrogen production during the process was evaluated. The measured yield of hydrogen from seawater was comparable to the primary yield in the γ-radiolysis of water. This result indicates that the oxidation of hydrogen by the radical products of water radiolysis is not effective in seawater. The measured yield from the mixture decreased at a high weight fraction of zeolite. However, the measured yield was higher than that expected from the direct radiolysis of water in the mixture, which would decrease proportionally to the weight fraction of water. This result suggests that the radiation energy deposited on the zeolite is involved in hydrogen production. From the measured yields, the hydrogen production rate was evaluated to be 3.6 mL/h per t of radioactive water before the process and 1.5 L/h per t of waste adsorbent after the process.

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“…The spent zeolite vessels were highly radioactive. Prior to underground storage, they were dehydrated and inserted with a hydrogen recombination catalyst to reduce their hydrogen concentration [4][5][6]. Consequent to the accident at Fukushima Daiichi Nuclear Power Station owned by the Tokyo Electric Power Co. (TEPCO), a large amount of radioactive water has been generated to cool the damaged reactor cores.…”

Section: Introductionmentioning

confidence: 99%

Characterization and storage of radioactive zeolite waste

Yamagishi

Nagaishi

Kato

et al. 2014

Journal of Nuclear Science and Technology

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For the safe storage of zeolite wastes generated by the treatment of radioactive saline water at the Fukushima Daiichi Nuclear Power Station, this study investigated the fundamental properties of herschelite adsorbent and evaluated its adsorption vessel for hydrogen production and corrosion. The hydrogen produced by the herschelite sample is oxidized by radicals as it diffuses to the water surface and thus depends on the sample's water level and dissolved species. The hydrogen production rate of herschelite submerged in seawater or pure water may be evaluated by accounting for the water depth. From the obtained fundamental properties, the hydrogen concentration of a reference vessel (decay heat = 504 W) with or without residual pure water was evaluated by thermal-hydraulic analysis. The maximum hydrogen concentration was below the lower explosive limit (4%). The steady-state corrosion potential of a stainless steel 316L increased with the absorbed dose rate, but the increase was repressed in the presence of herschelite. The temperature and absorbed dose at the bottom of the 504 W vessel were determined as 60• C and 750 Gy/h, respectively. Under these conditions, localized corrosion of a herschelite-contacted 316L vessel would not immediately occur at Cl − concentrations of 20,000 ppm.

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Submerged demineralizer system vessel shipment report

Cited by 10 publications

References 0 publications

Evaluation of special safety issues associated with handling the Three Mile Island Unit 2 core debris

Evaluation of special safety issues associated with handling the Three Mile Island Unit 2 core debris

Measurement and Evaluation of Hydrogen Production from Mixtures of Seawater and Zeolite in Decontamination of Radioactive Water

Characterization and storage of radioactive zeolite waste

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