Published 1993 | Version v1
Miscellaneous Open

Monitoring of the moderator temperature coefficient of reactivity in a PWR reactor

Creators

  • 1. Institute of Nuclear Sciences VINCA, Belgrade (Yugoslavia)

Description

A new method is described for determining temperature coefficient of reactivity (TCR) of pressurised water reactor based on the correlation of fluctuations in in-core neutron detector and core-exit thermocouple signals. It is shown that the moderator temperature coefficient of reactivity can be monitored during the fuel cycle by measuring the frequency response functions between these fluctuations. (author)

Availability note (English)

Available from INIS in electronic form; Also available from Institute of Nuclear Sciences VINCA

Files

38007710.pdf

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Additional details

Additional titles

Original title (Serbian)
Pracenje temperaturnog koeficijenta reaktivnosti u PWR reaktoru

Publishing Information

Publisher
Society for Electronics,Telecommunications, Computers, Automation, and Nuclear Engineering
Imprint Place
Belgrade (Yugoslavia)
ISBN
86-80509-06-X
Imprint Pagination
6 p.
Report number
INIS-RS--0408

Conference

Title
Society for Electronics, Telecommunications, Computers, Automation, and Nuclear Engineering
Original Conference Title
ETRAN '93: 37. Konferencija za elektroniku, telekomunikacije, racunarstvo, automatiku i nuklearnu tehniku
Acronym
37. Conference - ETAN '93
Dates
20-23 Sep 1993
Place
Beograd (Yugoslavia)

Optional Information

Notes
6 refs., 5 figs.