It has been pointed out that high concentration dissolved hydrogen is one of the important factors of PWSCC (primary water stress corrosion cracking) in the primary systems of pressurized water reactors. Application of a substitution for hydrogen may be a fundamental countermeasure of PWSCC. The authors are developing a new water chemistry technology of a hydrogen alternative to suppress PWSCC. In the present paper, corrosion tests of Zircaloy-4 were performed in deaerated 5 mmol dm−3 methanol solution at 320 °C in the absence and presence of gamma-irradiation. The nominal absorbed dose of the test water was 100 kGy. After the immersion tests, the specimens were analyzed. Weight gain per unit surface area, thickness of oxide film and hydrogen storage were measured. In addition, Raman spectroscopy was carried out, to investigate possible deposition of organic compounds on surface of the specimens. The corrosion behavior of Zircaloy-4 without irradiation agreed with literature data. It was concluded that the presence of methanol did not affect the corrosion behavior of Zircaloy-4. The corrosion behavior of Zircaloy-4 hardly depended on 100 kGy gamma-irradiation. On the Raman spectra of the specimens after the immersion tests, the Raman peaks ascribed to polyethylene or graphite were not found. The deposit of decomposition products of methanol would be negligible if any. It seems that polymerization is not the major process in thermal decomposition and radiolysis of methanol, but methanol decomposes into CO2 or carboxylic acids.
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2013 21st International Conference on Nuclear Engineering
July 29–August 2, 2013
Chengdu, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5578-2
PROCEEDINGS PAPER
Corrosion Behavior of Zircaloy-4 in Methanol Solution at 320 °C Under Gamma-Irradiation
Masafumi Domae,
Masafumi Domae
Central Research Institute of Electric Power Industry, Yokosuka, Kanagawa, Japan
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Kosho Hojo,
Kosho Hojo
The Japan Atomic Power Company, Tokyo, Japan
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Wataru Sugino
Wataru Sugino
The Japan Atomic Power Company, Tsuruga, Fukui, Japan
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Masafumi Domae
Central Research Institute of Electric Power Industry, Yokosuka, Kanagawa, Japan
Kosho Hojo
The Japan Atomic Power Company, Tokyo, Japan
Wataru Sugino
The Japan Atomic Power Company, Tsuruga, Fukui, Japan
Paper No:
ICONE21-15309, V001T02A009; 7 pages
Published Online:
February 7, 2014
Citation
Domae, M, Hojo, K, & Sugino, W. "Corrosion Behavior of Zircaloy-4 in Methanol Solution at 320 °C Under Gamma-Irradiation." Proceedings of the 2013 21st International Conference on Nuclear Engineering. Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Radiation Protection and Nuclear Technology Applications. Chengdu, China. July 29–August 2, 2013. V001T02A009. ASME. https://doi.org/10.1115/ICONE21-15309
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