Published August 1982 | Version v1
Report Restricted

Determination of retained gas in irradiated fuel samples

Creators

Description

Fuel cross section samples from water reactor fuel pins are oxidized in molten NaNo3 containing about 10% NaOH and 5% Na2O2. During this oxidation the fission gases Kr and Xe are released. The gas volume is measured, and the gas is analysed by mass spectrometry. The generated amount of gas in the samples analysed is calculated from measured burn-up, from measured Xe and Kr isotope ratios and from fission yields of stable Xe and Kr isotopes with low neutron cross sections. From the fission gas generated and measured amount of gas retained, the gas retention and release percentage cn be found. Examples of results are reported. Retained gas plus released gas (measured by puncturing) and the calculated gas generation agreed within 6 percent. (author)

Availability note (English)

MF available from INIS under the Report Number; Also available from Risoe Library, DK-4000 Roskilde, Denmark.

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Additional details

Publishing Information

ISBN
87-550-0873-9
Imprint Pagination
19 p.
Report number
RISO-M--2352

Conference

Title
EEC hot laboratory committee meeting.
Dates
10 - 11 Jun 1982.
Place
Mol (Belgium).

INIS

Country of Publication
Denmark
Country of Input or Organization
Denmark
INIS RN
14720422
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
FISSION PRODUCT RELEASE; FISSION PRODUCTS; FISSION YIELD; FUEL PINS; ISOTOPE RATIO; KRYPTON; KRYPTON ISOTOPES; MASS SPECTROSCOPY; MEASURING METHODS; MOLTEN SALTS; OXIDATION; POST-IRRADIATION EXAMINATION; RADIATION CHEMISTRY; SPENT FUELS; URANIUM DIOXIDE; XENON; XENON ISOTOPES
Descriptors DEC
ACTINIDE COMPOUNDS; CHALCOGENIDES; CHEMICAL REACTIONS; CHEMISTRY; ELEMENTS; ENERGY SOURCES; FUEL ELEMENTS; FUELS; ISOTOPES; MATERIALS; NONMETALS; NUCLEAR FUELS; NUCLEAR REACTION YIELD; OXIDES; OXYGEN COMPOUNDS; RADIOACTIVE MATERIALS; RARE GASES; REACTOR COMPONENTS; REACTOR MATERIALS; SALTS; SPECTROSCOPY; URANIUM COMPOUNDS; URANIUM OXIDES