Title :
Monitoring the fast neutrons in a high flux: the case for 242Pu fission chambers
Author :
Filliatre, P. ; Jammes, C. ; Oriol, L. ; Geslot, B. ; Vermeeren, L.
Author_Institution :
Centre de Cadarache, Commissariat a l´´Energie Atomique, St. Paul-lez-Durance, France
Abstract :
Fission chambers are widely used for on-line monitoring of neutron fluxes in irradiation reactors. A selective measurement of a component of interest of the neutron flux is possible in principle thanks to a careful choice of the deposit material. However, measuring the fast component is challenging when the flux is high (up to 1015 n/cm2/s) with a significant thermal component. The main problem is that the isotopic content of a material selected for its good response to fast neutrons evolves with irradiation, so that the material is more and more sensitive to thermal neutrons. Within the framework of the FNDS (Fast Neutron Detector System) project, we design tools that simulate the evolution of the isotopic composition and fission rate for several deposits under any given flux. In the case of a high flux with a significant thermal component, 242Pu is shown after a comprehensive study of all possibilities to be the best choice for measuring the fast component, as long as its purity is sufficient. If an estimate of the thermal flux is independently available, one can correct the signal for that component. This suggests a system of two detectors, one of which being used for such a correction. It is of very high interest when the detectors must be operated up to a high neutron fluence.
Keywords :
fission of plutonium; fission reactors; neutron detection; particle detectors; radiation monitoring; 242Pu fission chambers; FNDS; Fast Neutron Detector System; fission rate; high flux fast neutron monitoring; irradiation reactors; isotopic composition evolution; on line neutron flux monitoring; thermal neutron component; Computational modeling; Detectors; Electrodes; Fission reactors; Inductors; Isotopes; Jamming; Monitoring; Neutrons; Voltage; Fission reactor measurements; Neutron detectors; Simulation;
Conference_Titel :
Advancements in Nuclear Instrumentation Measurement Methods and their Applications (ANIMMA), 2009 First International Conference on
Conference_Location :
Marseille
Print_ISBN :
978-1-4244-5207-1
Electronic_ISBN :
978-1-4244-5208-8
DOI :
10.1109/ANIMMA.2009.5503819