UO$sub 2$--PuO$sub 2$ fuel-rod-bundle irradiation Mol-7A. Evaluation of the investigation results on the irradiated fuel rods

Technical Report · Fri Jun 01 04:00:00 EDT 1973

OSTI ID:4932655

Dienst, W; Ehrlich, K; Goetzmann, O; Hoffmann, H; Kleykamp, H; Schaefer, L; Schulz, B; Zimmermann, H

Seven UO/sub 2/ --20% PuO/sub 2/ fuel rods (500-mm fuel length) were irradiated in a fuel rod bundle cooled by flowing sodium. Irradiation was performed in the epithermal neutron flux of the test reactor BR 2 (Mol) at rod powers between about 300 W/cm (fuel end) and 560 W/cm (neutron flux maximum) to a maximum burnup of about 45 MWd/kg (U+Pu). The maximum fuel center temperature was calculated to be about 2800 deg C in the beginning, and about 2000 deg C for the largest part of irradiation time. The maximum cladding intennal temperature (at the hot rod ends) was between 570 and 620 deg C. The post-irradiation volume distribution in fuel rod cross-sections was investigated along with fission product composition and quantity, Pu redistrlbution, U redistribution chemical reactions between the fuel and stainless steel cladding, and mechanical properties. (15 figures, 88 references) (JRD)

• Research Organization: Kernforschungszentrum Karlsruhe (F.R. Germany). Inst. fuer Material- und Festkoerperforschung
• Sponsoring Organization: Sponsor not identified
• NSA Number: NSA-29-000916
• OSTI ID: 4932655
• Report Number(s): KFK--1736
• Country of Publication: Germany
• Language: German

Related Subjects

BURNUP
COOLANTS
CRACKS
EPITHERMAL NEUTRONS
FISSION PRODUCTS
FUEL CANS
FUEL ELEMENT CLUSTERS
FUEL RODS
IN PILE LOOPS
LIQUID METALS
N50120* --Metals
Ceramics
& Other Materials--Ceramics & Cermets--Preparation & Fabrication
N79300 --Reactors--Reactor Fuels
NEUTRON BEAMS
PHYSICAL RADIATION EFFECTS
PLUTONIUM OXIDES
STAINLESS STEELS
URANIUM DIOXIDE
VERY HIGH TEMPERATURE
VOIDS
VOLUME