Corrosion behavior of Zircaloy-4 in aqueous solution of methanol at 320degC under gamma-irradiation
Creators
- 1. Central Research Institute of Electric Power Industry, Materials Science Research Laboratory, Yokosuka, Kanagawa (Japan)
- 2. Japan Atomic Power Company, Plant Management Department, Tokyo (Japan)
- 3. Japan Atomic Power Company, Tsuruga, Fukui (Japan)
Description
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 5x10-3 mol dm-3 methanol solution at 320degC 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. (author)
Availability note (English)
Available from http://dx.doi.org/10.1299/mej.2014tep0023Additional details
Identifiers
Publishing Information
- Journal Title
- Mechanical Engineering Journal (Online)
- Journal Volume
- 1
- Journal Issue
- 4
- Journal Page Range
- p. 1400011.1-1400011.9
- ISSN
- 2187-9745
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 48079998
- Subject category
- S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ABSORBED RADIATION DOSES; CLADDING; CRACKING; DISSOCIATING GASES; HYDROGEN; HYDROGEN STORAGE; METHANOL; PWR TYPE REACTORS; RADIOLYSIS; RAMAN SPECTROSCOPY; STRESS CORROSION; TRANSMISSION ELECTRON MICROSCOPY; ZIRCALOY 4
- Descriptors DEC
- ALCOHOLS; ALLOYS; ALLOY-ZR98SN-4; CHEMICAL RADIATION EFFECTS; CHEMICAL REACTIONS; CHROMIUM ADDITIONS; CHROMIUM ALLOYS; CORROSION; CORROSION RESISTANT ALLOYS; DECOMPOSITION; DEPOSITION; DOSES; ELECTRON MICROSCOPY; ELEMENTS; ENRICHED URANIUM REACTORS; FLUIDS; GASES; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HYDROXY COMPOUNDS; IRON ADDITIONS; IRON ALLOYS; LASER SPECTROSCOPY; MATERIALS; MICROSCOPY; NONMETALS; ORGANIC COMPOUNDS; POWER REACTORS; PYROLYSIS; RADIATION DOSES; RADIATION EFFECTS; REACTORS; SPECTROSCOPY; STORAGE; SURFACE COATING; THERMAL REACTORS; THERMOCHEMICAL PROCESSES; TIN ALLOYS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCALOY; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS
Optional Information
- Notes
- 8 refs., 6 figs., 3 tabs.