SYMPOSIA PAPER Published: 01 January 1994
STP15094S

VVER-440 Reactor Vessel Exposure Monitoring in the Czech Republic

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A short review of the current reactor pressure vessel fast neutron fluence monitoring and evaluation methodology is presented. The reactor pressure vessel exposure must be evaluated for every fuel cycle combining calculations, surveillance monitors, exvessel (cavity) monitors and other experimental results. The series of WER-440 mock-up experiments were carried out in the LR-0 experimental reactor in the Nuclear Research Institute. The results were revised and the authorized data files were completed. A recommended practice for the use of mock-up results in fluence monitoring system was prepared. A database consisting of the surveillance and exvessel fast monitor data and the mock-up results is used to increase the reliability of the reactor pressure vessel exposure evaluation.

Author Information

Ošmera, B
Nuclear Research Institute plc, Czech Republic
Svoboda, č
Nuclear Research Institute plc, Czech Republic
Hep, J
škoda, Nuclear Machinery, Plzeň, Co. Ltd, Czech Republic
Holman, M
škoda, Nuclear Machinery, Plzeň, Co. Ltd, Czech Republic
Hógel, J
škoda, Nuclear Machinery, Plzeň, Co. Ltd, Czech Republic
Valenta, V
škoda, Nuclear Machinery, Plzeň, Co. Ltd, Czech Republic
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Details
Developed by Committee: E10
Pages: 29–37
DOI: 10.1520/STP15094S
ISBN-EB: 978-0-8031-5281-6
ISBN-13: 978-0-8031-1899-7