出版社:SISSA, Scuola Internazionale Superiore di Studi Avanzati
摘要:In present-day Boiling Water Reactors (BWR), the only in-core neutron diagnostics in fullpower
operation (Power-Range Mode, PRM) is performed with fission-based ionisation chambers
loaded with 235U. Since both the neutron flux and the neutron-induced fission cross section
on 235U are the highest at thermal energies, the count rate from such PRM detectors is essentially
due to the thermal neutrons. It has recently been proposed that adding PRM detectors loaded with
238U, thereby being sensitive only to fast neutrons (above about 1.5 MeV), to the BWR core could
facilitate void monitoring.
The neutron energy spectrum in a BWR is very sensitive to the boiling. Since the moderation
of neutrons requires the presence of hydrogen, which in reality means water, the moderation
gets significantly less efficient in regions of the reactor where the void fraction (the fraction of the
water that is in steam phase) is high. Because the density of steam is significantly lower than when
water is in liquid phase, increased void results in reduced moderation. Less moderation results in
a neutron energy spectrum with a lower fraction of thermal neutrons and a correspondingly larger
number of fast neutrons. Thereby, a simultaneous measurement of the fluxes of thermal and fast
neutrons may be used to determine the void in a BWR. The potential of this technique will be
outlined, as well as applications in realistic technical systems.