Published 1989 | Version v1
Journal article

Interaction of cladding materials with fission fragments of oxide fuel elements of a fast neutron reactor

  • 1. Nauchno-Issledovatel'skij Inst. Atomnykh Reaktorov, Dimitrovgrad (USSR)

Description

Optical microscopy and X-ray spectrum microanalysis were used to investigate physical-chemical interaction of claddings with fission fragments of oxide fuel of BOR-60 reactor fuel elements which were irradiated up to maximal burn up 19.7 FIMA %. It was shown that cladding erosion damage was mostly due to cesium, iodine and tellurium. Contribution of each of these elements into physicochemical processes at the core-cladding interface was determined. Some regularities of corrosion behaviour of claddings of different materials were established along with an influence of alloying and preliminary treatment on their corrosion resistance. Quantitative data on corrosion depth versus different paremeters are presented

Additional details

Additional titles

Original title (Russian)
Взаимодействие материалов оболочек с осколками деления оксидного топлива твэлов реактора на быстрых нейтронах

Publishing Information

Journal Title
Voprosy Atomnoj Nauki i Tekhniki. Fizika Radiatsionnykh Povrezhdenij i Radiatsionnoe Materialovedenie
Journal Issue
no.2
Series
Vopr. At. Nauki Tekh., Fiz. Radiat. Povrezhdenij Radiat. Materialoved. ;Fizika radiatsionnykh povrezhdenij i radiatsionnoe materialovedenie.
ISSN
0134-5400
CODEN
VAFMD