Status of FIPRED development
- 1. Institute for Nuclear Research, PO Box 78, Campului 1, RO-115400 Pitesti-Mioveni (Romania)
Description
Full text: The paper present the results of the study of UO2 sintered pellets oxidation, part of FIPRED (Fission Product Release from Debris Bed) Project. The FIPRED Project is dedicated to the study the fission products release from irradiated pellets existing in debris bed. The product release is produced by oxidative self-disintegration of sintered pellets at air ingress and it is temperature dependent. The experimental program covered experiments of 30 deg. C -1000 deg.C in air diluted with nitrogen at different concentration of oxygen. The experiments were performed using the SETARAM thermo-gravimetric equipment and the FIPRED EQ equipment designed and manufactured especially for this type of experiment. The powders (fragments), resulted from UO2 pellets self-disintegration, were characterized by sieving and SEM. The self-disintegration mechanism was demonstrated using the experimental results obtained and thermodynamically data of uranium oxides. (authors)
Availability note (English)
Available from author(s)Additional details
Publishing Information
- Publisher
- Romanian Nuclear Energy Association, AREN
- Imprint Place
- Bucharest (Romania)
- Imprint Title
- International Symposium on Nuclear Energy SIEN 2007. Nuclear Power - A New Challenge. Volume of abstracts
- Imprint Pagination
- 68 p.
- Journal Page Range
- p. 41
Conference
- Title
- international symposium on nuclear energy: nuclear power - a new challenge
- Acronym
- SIEN 2009
- Dates
- 12-16 Oct 2009
- Place
- Bucuresti (Romania)
INIS
- Country of Publication
- Romania
- Country of Input or Organization
- Romania
- INIS RN
- 42083065
- Subject category
- S36: MATERIALS SCIENCE; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Non-conventional Literature, Conference
- Descriptors DEI
- FISSION PRODUCTS; FUEL PELLETS; MOLECULAR SIEVE PROCESS; NITROGEN; OXIDATION; POWDERS; SCANNING ELECTRON MICROSCOPY; SINTERED MATERIALS; SPENT FUEL ELEMENTS; TEMPERATURE RANGE 0273-0400 K; TEMPERATURE RANGE 1000-4000 K; THERMAL GRAVIMETRIC ANALYSIS; URANIUM DIOXIDE
- Descriptors DEC
- ACTINIDE COMPOUNDS; CHALCOGENIDES; CHEMICAL ANALYSIS; CHEMICAL REACTIONS; DESULFURIZATION; ELECTRON MICROSCOPY; ELEMENTS; FUEL ELEMENTS; GRAVIMETRIC ANALYSIS; ISOTOPES; MATERIALS; MICROSCOPY; NONMETALS; OXIDES; OXYGEN COMPOUNDS; PELLETS; QUANTITATIVE CHEMICAL ANALYSIS; RADIOACTIVE MATERIALS; REACTOR COMPONENTS; TEMPERATURE RANGE; THERMAL ANALYSIS; URANIUM COMPOUNDS; URANIUM OXIDES
Optional Information
- Notes
- Available in abstract form only, full text entered this record