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A wide variety of irradiation experiments to study the performance behaviour of Fast Breeder Reactor fuel pins have been and are currently carried out in the High Flux Reactor of the Joint Research Centre Petten. For each experiment the correct fissile power determination is of fundamental importance. The fissile power is essentially determined by the temperature increase of the coolant water. In order to check the continuous on-line measurements (over long periods, sometimes years), alternative techniques have been exploited and are currently used in independently determining the fissile power. To that purpose neutron fluence detectors and noise analysis and correlation techniques of the neutron detectors and thermocouples output signals can be successfully applied. The paper gives a brief description of the rig and its instrumentation and examples of results obtained by the application of the above-mentioned techniques.

Additional information

Authors: MOSS R L, JRC Petten (NL);DEBARBERIS L, JRC Petten (NL);BEERS M, JRC Petten (NL)
Bibliographic Reference: Paper presented: VIII Congresso Trasmissione Calore, Ancona (IT), April 28-30, 1990
Availability: Available from (1) as Paper IT 35460 ORA
Record Number: 199011234 / Last updated on: 1994-12-01
Original language: it
Available languages: it