Combined Raman imaging and 18O tracer analysis for the study of zircaloy-4 high-temperature oxidation in spent fuel pool accident - 2016-0037
Creators
- 1. Univ. Grenoble Alpes and CNRS, LEPMI, F-38000 Grenoble (France)
- 2. IRSN/PSN-RES/SEREX/LE2M Cadarache 13115 Saint-Paul-lez-Durance (France)
Description
Oxidation at high temperature (HT) of cladding materials is expected to be the primary cause of the fuel assemblies degradation in spent fuel storage pool loss of cooling accidents. Unlike a loss-of-coolant accident (LOCA) in a reactor vessel, the presence of air in the atmosphere is expected in a spent fuel pool accident and is known to be an aggravating factor because of the 'catalytic' role of nitrogen on the oxidation. In steam LOCA conditions, a low-temperature (LT) oxidation scale simulating the corrosion oxide formed during in-service use of the assemblies has been observed to have a protective effect regarding subsequent HT oxidation. In the presence of nitrogen, HT oxidation kinetic experiments show that the protective effect of an LT corrosion scale also exists but is lost much earlier than in pure steam. Oxygen transport through LT oxide layers has been studied using the 18O tracer technique. We performed experiments in 18O2 alone as well as in mixed 18O2+N2 atmospheres, at 850 deg. C. Micro-Raman imaging, both at the specimen surfaces and on cross sections gave clear evidence for different characteristic distributions of 18O in the scales. Some of these distributions have been correlated with the presence of cracks and porosity in the LT oxide, which allows oxygen to locally penetrate in the scales. In cases in which no radial crack is present, apparent oxygen diffusion coefficients in the oxide were derived from fitting 18O diffusion profiles. Nitrogen appears to have no or only a limited influence on the oxygen diffusivity, but it is observed to reach the metal-oxide interface faster than oxygen, at which point it reacts with the metal and the sub-stoichiometric oxide to form zirconium nitride.The later conversion of the ZrN into ZrO2 might lead to the destabilization of the LT scale and to the loss of its protective effect. (authors)
Availability note (English)
Available from doi: http://dx.doi.org/10.1520/STP159720160037Additional details
Identifiers
Publishing Information
- Publisher
- ASTM International
- Imprint Place
- West Conshohocken, PA (United States)
- Imprint Pagination
- 34 p.
Conference
- Title
- 18. International Symposium on Zirconium in the Nuclear Industry
- Dates
- 15-19 May 2016
- Place
- Hilton Head, SC (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 50032037
- Subject category
- S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CORROSION; CROSS SECTIONS; FUEL ASSEMBLIES; FUEL STORAGE POOLS; LAYERS; LOSS OF COOLANT; OXIDATION; OXYGEN; POROSITY; REACTOR VESSELS; SPENT FUEL STORAGE; SPENT FUELS; TRACER TECHNIQUES; ZIRCALOY 4; ZIRCONIUM; ZIRCONIUM NITRIDES; ZIRCONIUM OXIDES
- Descriptors DEC
- ACCIDENTS; ALLOYS; ALLOY-ZR98SN-4; CHALCOGENIDES; CHEMICAL REACTIONS; CHROMIUM ADDITIONS; CHROMIUM ALLOYS; CONTAINERS; CORROSION RESISTANT ALLOYS; ELEMENTS; ENERGY SOURCES; FUELS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; IRON ADDITIONS; IRON ALLOYS; ISOTOPE APPLICATIONS; MATERIALS; METALS; NITRIDES; NITROGEN COMPOUNDS; NONMETALS; NUCLEAR FUELS; OXIDES; OXYGEN COMPOUNDS; PNICTIDES; REACTOR ACCIDENTS; REACTOR MATERIALS; STORAGE; TIN ALLOYS; TRANSITION ELEMENT ALLOYS; TRANSITION ELEMENT COMPOUNDS; TRANSITION ELEMENTS; ZIRCALOY; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS; ZIRCONIUM COMPOUNDS
Optional Information
- Notes
- 49 refs