SYMPOSIA PAPER Published: 01 January 1993

Surveillance of WWER-440Č Reactor Pressure Vessels


In Czechoslovakia there are six units of Water-Water Power Reactor (WWER)-440Č type reactors (pressurized water reactor [PWR] type) incorporated with pressure vessel surveillance specimens. These sets of specimens are kept for carrying out static tensile testing, impact notch toughness testing, and static fracture toughness testing, and are supplemented by necessary sets of neutron flux monitors.

Results of mechanical testing of these specimens evaluated after one to five years of reactor operation are summarized and discussed with respect to the effect of individual heats and welding joints, radiation embrittlement laws, and lead factor and pressure vessel lifetime assessment.

Author Information

Brumovský, M
Nuclear Research Institute, Czech Republic
áš Páv, T
Nuclear Research Institute, Řež, Czech Republic
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Developed by Committee: E10
Pages: 57–70
DOI: 10.1520/STP24763S
ISBN-EB: 978-0-8031-5228-1
ISBN-13: 978-0-8031-1478-4