Deposition behavior of TiO2 on fuel cladding surface in boiling water under simulated BWR operating conditions
- 1. Toshiba Corp., Kawasaki, Kanagawa (Japan)
- 2. Toshiba Corp., Yokohama, Kanagawa (Japan)
Description
The susceptibility of stainless steel structural materials in boiling water reactors (BWRs) to intergranular stress corrosion cracking (IGSCC) can be reduced by lowering the electrochemical corrosion potential (ECP). A technique for reducing the ECP by injecting TiO2 solution into BWRs under operating conditions ("On-Line TiO2 Injection") has been developed by the authors. One of the key considerations in the development and implementation of the On-Line TiO2 injection is a possible impact on fuel performance. From results of in-core corrosion tests, the integrity of the fuel is ensured when the amount of TiO2 deposited on a Zircaloy-2 cladding surface was less than 1000 μg/cm2. In order to investigate the TiO2 deposition behavior in boiling water, TiO2 deposition tests on a heated Zircaloy-2 cladding surface in boiling water were conducted in a laboratory loop under simulated BWR operating conditions. The effects of quality and heat flux on the deposition rate were evaluated. At a constant heat flux, the deposition rate was proportional to the quality within a certain distance from the inlet of an autoclave. At a constant quality, the deposition rate was proportional to the heat flux within the experimental range of heat fluxes used, namely, 150 to 250 kW/m2. The morphologies of the deposited TiO2 were characterized by scanning electron microscope (SEM) observation. Moreover, the profile of the deposition rate vs. axial length of fuel in an actual BWR was calculated from the experimental data. As a result, the maximum deposition rate was calculated to be 23.0 cm/h when the axial distance from the inlet core was 2.3 m, the quality was 8.1%, and the heat flux was 598.5 kW/m2. (author)
Additional details
Publishing Information
- Imprint Title
- Proceedings of nuclear plant chemistry conference 2014 Sapporo (NPC 2014)
- Imprint Pagination
- 2471 p.
- Journal Page Range
- 11 p.
Conference
- Title
- Nuclear plant chemistry conference 2014
- Acronym
- NPC 2014
- Dates
- 26-31 Oct 2014
- Place
- Sapporo, Hokkaido (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 47089585
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BWR TYPE REACTORS; CLADDING; ELECTROCHEMICAL CORROSION; HEAT FLUX; INTERGRANULAR CORROSION; SCANNING ELECTRON MICROSCOPY; STAINLESS STEELS; STRESS CORROSION; TITANIUM OXIDES; ZIRCALOY 2
- Descriptors DEC
- ALLOYS; ALLOY-ZR98SN-2; CARBON ADDITIONS; CHALCOGENIDES; CHEMICAL REACTIONS; CHROMIUM ADDITIONS; CHROMIUM ALLOYS; CORROSION; CORROSION RESISTANT ALLOYS; DEPOSITION; ELECTRON MICROSCOPY; ENRICHED URANIUM REACTORS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; IRON ADDITIONS; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS; MICROSCOPY; NICKEL ADDITIONS; NICKEL ALLOYS; OXIDES; OXYGEN COMPOUNDS; POWER REACTORS; REACTORS; STEELS; SURFACE COATING; THERMAL REACTORS; TIN ALLOYS; TITANIUM COMPOUNDS; TRANSITION ELEMENT ALLOYS; TRANSITION ELEMENT COMPOUNDS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCALOY; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS
Optional Information
- Notes
- Available as USB Flash Memory Data in PDF format, Folder Name: Session10-Future Trend and New Development#centre dot#Scientific Basis, Paper ID: 10154NPC2014proceedings.pdf; 9 refs., 16 figs., 1 tab.