Modeling of low-temperature reduction of metal oxide in hydrogen treatment system for severe accidents in nuclear power plants

Kotaro Nakamura, Masashi Tanabe, Satoru Abe, Takashi Mawatari, Takao Nakagaki

研究成果: Conference contribution

抄録

At the Fukushima Daiichi nuclear power plant, zirconium in the fuel rod cladding reacted with water vapor at elevated temperatures due to a loss of cooling water, resulting in the production of a large amount of hydrogen. This hydrogen leaked from the reactor vessel and accumulated in the top of reactor building, eventually leading to an explosion. A hydrogen treatment system that re-oxidizes hydrogen to water vapor is one of the effective methods to prevent such an explosion. A prominent re-oxidation method is via a fixed bed reactor packed with metal oxide pellets. The advantages of this method are its relatively fast oxidation rate without external oxygen/air injection. In this study, experiments and complementary numerical calculations were performed on the hydrogen reoxidation reaction by metal oxides. The oxidation of hydrogen by copper oxide is modeled by 5 interacting, elementary reactions consisting of 6 chemical species. Experiments were performed using two packed bed set-ups, with measurement of inlet/outlet gas composition and pre/post-analysis of solid composition used to determine constants of the individual reaction rates for numerical calculations. From these reaction constants, the temporal behavior of the outlet gas was predicted.

本文言語English
ホスト出版物のタイトルStudent Paper Competition; Thermal-Hydraulics; Verification and Validation
出版社American Society of Mechanical Engineers (ASME)
ISBN(印刷版)9784888982566
出版ステータスPublished - 2020
イベント2020 International Conference on Nuclear Engineering, ICONE 2020, collocated with the ASME 2020 Power Conference - Virtual, Online
継続期間: 2020 4 42020 4 5

出版物シリーズ

名前International Conference on Nuclear Engineering, Proceedings, ICONE
3

Conference

Conference2020 International Conference on Nuclear Engineering, ICONE 2020, collocated with the ASME 2020 Power Conference
CityVirtual, Online
Period20/4/420/4/5

ASJC Scopus subject areas

  • 原子力エネルギーおよび原子力工学

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