Burn-up determination of mixed-oxide fuels using TIMS
Creators
- 1. Fuel Chemistry Div., Bhabha Atomic Research Centre, Mumbai (India)
Description
The term burn-up is used to denote the atom present fission of heavy elements (mass >225). Mixed oxides consisting of a homogenous solution of (UO2+PuO2) have been proposed as a substitute to enriched uranium used in boiling water reactors. Determination of nuclear fuel burn-up is important for fuel management, fuel development, fuel performance evaluation and for validation of computer codes. The atom percent fission is obtained from the concentration of a suitable fission product isotope (burn-up monitor) relative to those of heavy element isotopes. The method for the experimental determination of burn-up involves the dissolution of fuel sample, separation of U, Pu and burn-up monitor and their concentration determination. The concentrations of the heavy elements and those of burn-up monitor were determined by isotope dilution mass spectrometry (IDMS) in order to circumvent the problems associated with quantitative separation and handling of radioactive samples. ID-TIMS provides the most reliable and accurate data for the concentration determination
Additional details
Publishing Information
- Publisher
- Indian Society for Mass Spectrometry
- Imprint Place
- Mumbai (India)
- ISBN
- 81-901115-5-8
- Imprint Title
- ISMAS silver jubilee symposium on mass spectrometry. V. 2: contributed papers
- Imprint Pagination
- 476 p.
- Journal Page Range
- p. 884-887
Conference
- Title
- 9. ISMAS silver jubilee symposium on mass spectrometry
- Acronym
- ISMAS-SJS-2003
- Dates
- 27-31 Jan 2003
- Place
- Dona Paula (India)
INIS
- Country of Publication
- India
- Country of Input or Organization
- India
- INIS RN
- 34052788
- Subject category
- S37: INORGANIC, ORGANIC, PHYSICAL AND ANALYTICAL CHEMISTRY; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; FISSION PRODUCTS; ISOTOPE DILUTION; MASS SPECTROSCOPY; MIXED OXIDE FUELS; PLUTONIUM OXIDES; QUANTITATIVE CHEMICAL ANALYSIS; SPENT FUEL ELEMENTS; URANIUM OXIDES; VALIDATION
- Descriptors DEC
- ACTINIDE COMPOUNDS; CHALCOGENIDES; CHEMICAL ANALYSIS; ENERGY SOURCES; FUEL ELEMENTS; FUELS; ISOTOPE APPLICATIONS; ISOTOPES; MATERIALS; NUCLEAR FUELS; OXIDES; OXYGEN COMPOUNDS; PLUTONIUM COMPOUNDS; RADIOACTIVE MATERIALS; REACTOR COMPONENTS; REACTOR MATERIALS; SOLID FUELS; SPECTROSCOPY; TESTING; TRACER TECHNIQUES; TRANSURANIUM COMPOUNDS; URANIUM COMPOUNDS
Optional Information
- Notes
- 4 refs., 3 tabs.