Published 1981 | Version v1
Report Metadata-only

An analysis of the thermal and structure behaviour of the UO2-PuO2 fuel in the irradiation experiment FR2 capsule test series 5a

Creators

Description

In the Karlsruhe research reactor FR2 nine fuel pins were irradiated within three irradiation capsules in the course of the test series 5a. The pins contained UO2-PuO2 fuel pellets. They reached burnup values of about 6,17 and 47 MWd/KgMe with linear rod powers of 400 to 600 W/cm and clad surface temperature between 500 and 700 deg C. A detailed analysis of the fuel structuration data (columnar-grain and equiaxed-grain growth regions) have allowed to determine, with the help of physic-mathematical models, the radii of these regions and the heat transfer through the contact zone between fuel and clad depending on the burnup. The results of the analysis showed that the fuel surface temperature rose with increasing burnup. (author)

Availability note (English)

MF available from INIS under the Report Number.

Additional details

Additional titles

Original title (Spanish)
Analisis termico y estructural del combustible UO

Publishing Information

Imprint Pagination
64 p.
Report number
JEN--501

INIS

Country of Publication
Spain
Country of Input or Organization
Spain
INIS RN
12640975
Subject category
S36: MATERIALS SCIENCE;
Descriptors DEI
BURNUP; FR-2 REACTOR; FUEL PINS; IRRADIATION CAPSULES; PLUTONIUM OXIDES; STRUCTURAL CHEMICAL ANALYSIS; THERMAL ANALYSIS; URANIUM OXIDES
Descriptors DEC
ACTINIDE COMPOUNDS; CHALCOGENIDES; FUEL ELEMENTS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; IRRADIATION REACTORS; ISOTOPE PRODUCTION REACTORS; NATURAL URANIUM REACTORS; OXIDES; OXYGEN COMPOUNDS; PLUTONIUM COMPOUNDS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; TANK TYPE REACTORS; TEST REACTORS; THERMAL REACTORS; TRANSURANIUM COMPOUNDS; URANIUM COMPOUNDS

Optional Information

Notes
22 figs.; 16 refs.