Published 1987 | Version v1
Report Open

Analysis of the porosity distribution of mixed oxide pins

Creators

Description

In the frame of the Joint Irradiation Program IVO-FR2-Vg7 between the Centre of Nuclear Research of Karlsruhe (KfK), the irradiation of 30 mixed-oxide fuel rods in the FR2 experimental reactor was carried out. The pins were located in 10 single-walled NaK capsules. The behaviour of the fuel during its burnup was studied, mainly, the rest-porosity and cracking distribution in the pellet, partial densification, etc. In this work 3 pins from the capsule No. 165 were analyzed. The experimental results (pore and cracking profiles) were interpreted by the fuel rod code SATURN. (Author) 20 refs

Availability note (English)

Available from INIS in electronic form

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Additional details

Additional titles

Original title (Spanish)
Analisis de distribucion de porosidad en barras combustibles de oxidos mixtos bajo irradiacion

Publishing Information

Imprint Pagination
132 p.
Report number
CIEMAT--608

INIS

Country of Publication
Spain
Country of Input or Organization
Spain
INIS RN
38063285
Subject category
S42: ENGINEERING;
Descriptors DEI
CRACKING; DISTRIBUTION; FR-2 REACTOR; FUEL DENSIFICATION; FUEL RODS; IRRADIATION CAPSULES; MIXED OXIDE FUELS; POROSITY; POST-IRRADIATION EXAMINATION; S CODES
Descriptors DEC
CHEMICAL REACTIONS; COMPUTER CODES; DECOMPOSITION; ENERGY SOURCES; FUEL ELEMENTS; FUELS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; IRRADIATION REACTORS; ISOTOPE PRODUCTION REACTORS; MATERIALS; NATURAL URANIUM REACTORS; NUCLEAR FUELS; PYROLYSIS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SOLID FUELS; TANK TYPE REACTORS; TEST FACILITIES; TEST REACTORS; THERMAL REACTORS; THERMOCHEMICAL PROCESSES