Oxidation Kinetics of Zircaloy-2 in The Saturated Steam Medium at A Temperature Range of 250 - 300 0C and pH From 5 to 9
Creators
- 1. Nuclear Fuel Element Development Centre, National Atomic Energy Agency, Serpong, Indonesia (Indonesia)
Description
The oxidation of zircaloy-2 in saturated steam medium has been studied to deal with the understanding of the oxidation kinetics and mechanism of cladding material of the BWR (boiling Water Reactor) fuel element. The experiments has been performed at temperature (T) range of 250 - 300 0C, for a time range (t) of 1-16 hours, and pH from 5 to 9 utilizing non continuous gravimetric method. The results show that at pH of 5 and temperatures between 250 - 300 0C the zircaloy-2 oxidation kinetic increases quantitatively during 1 hour to 2 hours exposure and then it decreases according to a hyperbolic function In the pH=7 at T=2500C the zircaloy-2 oxidation kinetic increases linearly and at T=275-300 0C it increases following a logarithmic function. At pH=9 and T=250-3000C zircaloy-2 oxidation kinetic increases following a logarithmic function. The initial oxidation mechanism of zircaloy-2 at pH from 5 to 9 obeys the Pilling Bedworth theory
Files
32062184.pdf
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Additional details
Additional titles
- Original title (Indonesian)
- Kinetika Oksidasi Zircaloy-2 dalam Media Uap Air Jenuh pada Temperatur 250- 300
Publishing Information
- Publisher
- Nuclear Fuel Element Development Centre, National Atomic Energy Agency
- Imprint Place
- Jakarta (Indonesia)
- Imprint Title
- Proceedings of the second Scientific Presentation on Nuclear Fuel Cycle
- Imprint Pagination
- 400 p.
- Journal Page Range
- p. 147-153
- ISSN
- 1410-1998
- Report number
- INIS-ID--010
Conference
- Title
- 2. Scientific Presentation on Nuclear Fuel Cycle
- Original Conference Title
- Presentasi Ilmiah Daur Bahan Bakar Nuklir II
- Dates
- 19-20 Nov 1996
- Place
- Jakarta (Indonesia)
INIS
- Country of Publication
- Indonesia
- Country of Input or Organization
- Indonesia
- INIS RN
- 32062184
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; CLADDING; FUEL ELEMENTS; GRAVIMETRY; OXIDATION; STEAM; URANIUM DIOXIDE; ZIRCALOY 2
- Descriptors DEC
- ACTINIDE COMPOUNDS; ALLOY-ZR98SN-2; ALLOYS; CHALCOGENIDES; CHEMICAL REACTIONS; CHROMIUM ADDITIONS; CHROMIUM ALLOYS; CORROSION RESISTANT ALLOYS; DEPOSITION; ENRICHED URANIUM REACTORS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; IRON ADDITIONS; IRON ALLOYS; MATERIALS; NICKEL ADDITIONS; NICKEL ALLOYS; OXIDES; OXYGEN COMPOUNDS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; SURFACE COATING; THERMAL REACTORS; TIN ALLOYS; TRANSITION ELEMENT ALLOYS; URANIUM COMPOUNDS; URANIUM OXIDES; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCALOY; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS
Optional Information
- Notes
- author; 9 refs; 3 figs Imprint:Prosiding: Presentasi ilmiah daur bahan bakar nuklir 2