Analysis of the Three Mile Island submerged demineralizer system vessel burial data

Jasen, W.G.; Amir, S.J.

doi:10.2172/5745649

1989

DOI: 10.2172/5745649

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Analysis of the Three Mile Island submerged demineralizer system vessel burial data

W.G. Jasen¹,

S.J. Amir²

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Cited by 5 publications

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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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Characterization and storage of radioactive zeolite waste

Yamagishi

Nagaishi

Kato

et al. 2014

Journal of Nuclear Science and Technology

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Effect of Gamma-ray Irradiation on Corrosion of Stainless Steel Contacted with Zeolite Particle

Kato

Yamagishi

Sato

et al. 2021

ZAKAEP

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Localized Corrosion Behavior of Stainless Steel in the Diluted Artificial Sea-Water Contacted with Zeolite under Gamma-ray Irradiation

Kato

Sato

Nakano

et al. 2015

Transactions of the Atomic Energy Society of Japan

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Regarding the long-term storage of spent Cs adsorption vessels containing zeolites in the Fukushima Daiichi nuclear power station, corrosion of the material of the spent Cs adsorption vessels is one of the important issues. We performed electrochemical tests of stainless steel (SUS316L) in the zeolites containing artificial seawater under gamma-ray irradiation. The spontaneous potential (E SP ) and critical pitting potential (V C ) of SUS316L were measured to understand the corrosion resistance of the stainless steel in this study. The rest potential of the stainless steel increased with time after gamma-ray irradiation. E SP , defined as the steady rest potential, increased with increasing dose rate; this increase in E SP was suppressed by the contact of SUS316L with the zeolites. The concentration of H 2 O 2 in bulk water increased with increasing dose rate. This concentration increase was suppressed by the contact of SUS316L with the zeolites due to decomposition of H 2 O 2 . There was good relationship between E SP and the concentration of H 2 O 2 . The V C of SUS316L contacted with the zeolites decreased with increasing Cl -ion concentration and is slightly smaller than the V C in bulk water. The contact of SUS316L with the zeolites suppressed the increase in E SP under irradiation. The contact with the zeolites can reduce the probability of the localized corrosion of SUS316L.

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Analysis of the Three Mile Island submerged demineralizer system vessel burial data

Cited by 5 publications

References 1 publication

Characterization and storage of radioactive zeolite waste

Characterization and storage of radioactive zeolite waste

Effect of Gamma-ray Irradiation on Corrosion of Stainless Steel Contacted with Zeolite Particle

Localized Corrosion Behavior of Stainless Steel in the Diluted Artificial Sea-Water Contacted with Zeolite under Gamma-ray Irradiation

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