Overview of the FUTURIX-FTA irradiation experiment in the Phenix reactor - 5268
Creators
- 1. Idaho National Laboratory, 2525 Fremont Ave., Idaho Falls, ID, 83415-6188 (United States)
- 2. Los Alamos National Laboratory, NM 87545 (United States)
- 3. CEA - Centre de Cadarache, 13108 St Paul Les Durance (France)
- 4. CEA - Centre de Marcoule, F-30207 Bagnols-sur-Ceze Cedex (France)
Description
A joint fast reactor irradiation experiment, known as FUTURIX-FTA, was conducted in the Phenix reactor to evaluate the transmutation of minor actinides in metallic and nitride fuels, among others. The experiment was a collaboration between the Department of Energy of the United States of America and CEA (France). Fuels with the same compositions were also irradiated in AFC-1 experiment series in the Advanced Test Reactor (ATR) using a modified neutron spectrum to create fast reactor thermal profiles in the fuel. Comparisons of results from both sets of experiments will be used to validate fuel performance in the ATR experiments. This paper presents a summary of the FUTURIX-FTA experiment design, test matrix, and irradiation in the Phenix reactor
Availability note (English)
Available (USB stick) from: SFEN, 103 rue Reaumur, 75002 Paris (France)Additional details
Publishing Information
- Publisher
- Societe Francaise d'Energie Nucleaire - SFEN
- Imprint Place
- Paris (France)
- ISBN
- 978-1-4951-6286-2
- Imprint Title
- GLOBAL 2015 Proceedings
- Imprint Pagination
- 2455 p.
- Journal Page Range
- p. 1800-1805
Conference
- Title
- Nuclear fuel cycle for a low-carbon future
- Acronym
- GLOBAL 2015
- Dates
- 21-24 Sep 2015
- Place
- Paris (France)
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 49058640
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ALLOY NUCLEAR FUELS; AMERICIUM; AMERICIUM NITRIDES; IRRADIATION DEVICES; MIXED NITRIDE FUELS; PHENIX REACTOR; PLUTONIUM; TRANSMUTATION; URANIUM; ZIRCONIUM ALLOYS
- Descriptors DEC
- ACTINIDE COMPOUNDS; ACTINIDES; ALLOYS; AMERICIUM COMPOUNDS; BREEDER REACTORS; ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FUELS; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; MATERIALS; METALS; NITRIDES; NITROGEN COMPOUNDS; NUCLEAR FUELS; PLUTONIUM REACTORS; PNICTIDES; POWER REACTORS; REACTOR MATERIALS; REACTORS; SODIUM COOLED REACTORS; SOLID FUELS; TRANSITION ELEMENT ALLOYS; TRANSPLUTONIUM COMPOUNDS; TRANSPLUTONIUM ELEMENTS; TRANSURANIUM COMPOUNDS; TRANSURANIUM ELEMENTS
Optional Information
- Notes
- 6 refs.