Microstructural evolution of Q12TM alloy irradiated in PWRs and comparison with other Zr base alloys - 2016-0061
Creators
- 1. 1CEA, Universite Paris-Saclay, DEN, Service de Recherches Metallurgiques Appliquees, Gif-sur-Yvette, F-91191 (France)
- 2. CEA, Universite Paris Saclay, DEN, Service d'Etude des Materiaux Irradies, Gif-sur-Yvette, F-91191 (France)
- 3. CEA, Universite Paris-Saclay, DEN, Departement des Materiaux pour le Nucleaire, Gif-sur-Yvette, F-91191 (France)
- 4. AREVA NP, Fuel Business Unit, 10 rue Juliette Recamier, Lyon Cedex 06, 69456 (France)
- 5. Electricite de France, DIN Septen, 12-14 Avenue Dutrievoz, Villeurbanne Cedex, 69628 (France)
- 6. Electricite de France, R and D Division, Materials and Mechanics of Components, Les Renardieres, Moret sur Loing, Cedex, 77818 (France)
Description
Based on the M5R* alloy metallurgy, the Q12TM alloy (Zr-1Nb-0.5Sn-0.1Fe) was developed by AREVA NP for structural components, with ultra-low tin addition and slightly increased iron content. The behavior of this alloy was tested under irradiation in a pressurized water reactor (PWR) and has shown improvement in irradiation creep strength and similar free growth compared with M5. This paper provides results on dimensional stability and details the microstructural evolution of the Q12 alloy under neutron irradiation in PWRs. The Q12 microstructural evolution under irradiation was studied for fast neutron fluences up to 13 X 1025 n/m2 (E>1 MeV) with analytical transmission electron microscopy observations. We focused on radiation-enhanced needle-like particles, Laves phases, and the linear density of -component loops. These results are compared with other quaternary zirconium-niobium-tin-iron alloys and with M5. All these results allow a general discussion about microstructural evolution and behavior under irradiation of quaternary-type alloys compared to M5 alloy. This study, in agreement with previous works on Zr-1Nb and quaternary alloys, seems to show that increasing the iron content with the presence of niobium and tin will decrease the -component loop linear density and delay the growth breakaway. (authors)
Availability note (English)
Available from doi: http://dx.doi.org/10.1520/STP159720160061Additional details
Identifiers
Publishing Information
- Publisher
- ASTM International
- Imprint Place
- West Conshohocken, PA (United States)
- Imprint Pagination
- 35 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
- 50032049
- Subject category
- S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CREEP; CRYSTAL GROWTH; DENSITY; FAST NEUTRONS; IRON; IRON ALLOYS; IRRADIATION; LAVES PHASES; METALLURGY; MICROSTRUCTURE; NEUTRON FLUENCE; NIOBIUM; PARTICLES; PWR TYPE REACTORS; QUATERNARY ALLOY SYSTEMS; TIN ADDITIONS; TRANSMISSION ELECTRON MICROSCOPY; ZIRCONIUM; ZIRCONIUM ALLOYS
- Descriptors DEC
- ALLOY SYSTEMS; ALLOYS; BARYONS; ELECTRON MICROSCOPY; ELEMENTARY PARTICLES; ELEMENTS; ENRICHED URANIUM REACTORS; FERMIONS; HADRONS; MECHANICAL PROPERTIES; METALS; MICROSCOPY; NEUTRONS; NUCLEONS; PHYSICAL PROPERTIES; POWER REACTORS; REACTORS; REFRACTORY METALS; THERMAL REACTORS; TIN ALLOYS; TRANSITION ELEMENT ALLOYS; TRANSITION ELEMENTS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 34 refs.