Filters
Results 1 - 1 of 1
Results 1 - 1 of 1.
Search took: 0.02 seconds
AbstractAbstract
[en] 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
Original Title
Analisis de distribucion de porosidad en barras combustibles de oxidos mixtos bajo irradiacion
Primary Subject
Source
1987; 132 p
Record Type
Report
Report Number
Country of publication
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
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue