Development of U-Mo for applications on high density MTR fuels
- 1. Comision Chilena de Energia Nuclear, Santiago (Chile)
Description
The application of U-Mo alloys is considered in the RERTR (Reduced Enrichment for Research and Test Reactors) program as an alternative for obtaining MTR nuclear fuels with higher uranium densities than those obtained with U3Si2. The CCHEN Fuel Fabrication Plant has developed studies since 2002 to obtain U-Mo alloys through induction melting followed by physical, chemical and metallurgical characterization and studying the phase transformations that occurs in the binary U-Mo system. The alloys were developed and obtained through induction melting in Ar inert atmosphere and then poured from 1350oC to 1550oC. The chemical characterization was carried out using atomic absorption spectrometry (ICP) and X-ray fluorescence (FRX). Optical and electronic microscopy, together with microanalysis by dispersive energy (EDAX) was used for the metallurgical characterization of the alloys. The microstructure was identified, the macro-segregations were quantified, the microstructure and phase compositions were revealed and concentration profiles and presence and composition of precipitates were determined. The alloys UMo 7wt%, UMo 8wt% and UMo 10wt% were obtained and characterized without important macrosegregations, a cubic gamma phase like matrix was founded, metastable at room temperature and a minority and discontinuous phase located on the grain boundaries identified as alpha phase (orthorhombic). The study of the solid state phase transformations was carried out with thermal treatments of homogenization and isothermal cooling for the alloy U-7%Mo. The conditions were a homogenization temperature of 980oC, with isothermal cooling between 400oC and 590oC and times of 1 to 44 hours. The result was the experimental determination of the TTT-IT diagram for this alloy (author)
Additional details
Additional titles
- Original title (Spanish)
- Desarrollo de aleaciones de U-Mo para aplicaciones en combustible tipo MTR de alta densidad
Publishing Information
- Publisher
- ANS-LAS; CCEN
- Imprint Place
- Santiago (Chile)
- Imprint Title
- Symposium 2003 Nuclear Technologies for the development of priority areas in Latin America. Extended abstracts
- Imprint Pagination
- 306 p.
- Journal Page Range
- p. 229-237
Conference
- Title
- nuclear technologies for the development of priority areas in Latin America
- Original Conference Title
- Simposio 2003 de la Seccion Latinoamericana de la Sociedad Nuclear Americana: las tecnologias nucleares para el desarrollo de areas prioritarias en America Latina
- Acronym
- Symposium 2003 of the Latin American Section - American Nuclear Society
- Dates
- 25-28 Aug 2003
- Place
- Santiago (Chile)
INIS
- Country of Publication
- Chile
- Country of Input or Organization
- Chile
- INIS RN
- 34083837
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- CHILE; FUEL ELEMENTS; MOLYBDENUM; MTR REACTOR; NUCLEAR FUELS; URANIUM
- Descriptors DEC
- ACTINIDES; DEVELOPING COUNTRIES; ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUELS; IRRADIATION REACTORS; LATIN AMERICA; MATERIALS; MATERIALS TESTING REACTORS; METALS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; REFRACTORY METALS; SOUTH AMERICA; TANK TYPE REACTORS; THERMAL REACTORS; TRANSITION ELEMENTS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Imprint:Simposio 2003 de la Seccion Latinoamericana de la Sociedad Nuclear Americana: las tecnologias nucleares para el desarrollo de areas prioritarias en America Latina. Resumenes extendidos