In-Pile Qualification of a Fast-Neutron-Detection-System

• Published in: IEEE transactions on nuclear science Vol. 65; no. 9; pp. 2443 - 2447
• Main Authors: Fourmentel, D., Villard, J.-F, Destouches, C., Barbot, L., Geslot, B., Vermeeren, L., Schyns, M.
• Format: Journal Article
• Language: English
• Published: New York IEEE 01.09.2018; The Institute of Electrical and Electronics Engineers, Inc. (IEEE)
• Subjects: Coatings; Computer simulation; Depletion; Detectors; Dosimeters; Energy; Evaluation; Fast neutrons; Fission chamber; Fluctuations; Inductors; Instrumentation; Instruments; Internet; Irradiation; Isotopes; Measurement techniques; Neutron counters; Neutron flux; Neutrons; Nuclear energy; Nuclear fuels; nuclear measurements; Nuclear reactors; Nuclear research; On-line systems; Prototypes; R&D; reactor instrumentation; Reactors; Research & development; Sensitivity; Sensitivity analysis; Thermal neutrons; Velocity measurement
• ISSN: 0018-9499; 1558-1578
• DOI: 10.1109/TNS.2018.2860060

In order to ensure the quality and the relevance of irradiation programs in the future Jules Horowitz Reactor (JHR), the French Alternative Energies and Atomic Energy Commission (CEA) has significantly increased its research and development effort in the field of in-pile instrumentation during the last decade. Major progress has been achieved in the capability to perform accurate in-pile measurements using reliable and updated techniques. A significant part of this effort has been conducted in the framework of the Joint Instrumentation Laboratory between the CEA and the Belgian Nuclear Research Centre (SCK · CEN). In order to improve measurement techniques for neutron flux assessment, a unique system for online measurement of fast neutron flux has been developed and recently qualified in-pile. The fast-neutron-detection-system (FNDS) has been designed to monitor accurately high-energy neutron flux (E > 1 MeV) in typical material testing reactor (MTR) conditions, where neutron flux levels can be as high as 10 15 N · cm -2 · s -1 and are generally dominated by thermal neutrons. Moreover, the neutron flux is coupled with a high gamma flux of typically a few 10 15 γ · cm -2 · s -1 , which can be highly disturbing for the online measurement of neutron fluxes. The patented FNDS system is based on two detectors allowing the simultaneous detection of both thermal- and fast-neutron flux. Thermal neutrons can be measured using a self-powered neutron detector or a 235 U miniature fission chamber, while fast neutron detection requires a miniature fission chamber with a special fissile material presenting an energy threshold near 1 MeV, which can be 242 Pu for MTR conditions. Fission chambers are operated in Campbelling mode for an efficient gamma rejection. FNDS also includes a specific software that processes measurements to compensate online the fissile material depletion and to adjust the sensitivity of the detectors, in order to produce a precise evaluation of both thermal and fast neutron flux even after longterm irradiation. FNDS has been validated through a two-step experimental program. A first set of tests was performed at BR2 reactor operated by SCK· CEN in Belgium. Two FNDS prototypes were operated in-pile during nearly 1000 h. These tests exhibited the consistency of the measurement of thermal to fast neutron flux ratio with Monte Carlo neutron and photon transport calculations, as well as the right compensation of fissile material depletion. This paper describes a second test recently completed at ISIS reactor operated by CEA in France. For this irradiation, FNDS signal was compared to reference thermaland fast-neutron flux measurements using activation dosimeters analyzed under COFRAC Quality Certification. During thislatter test, FNDS proved its ability to measure online the fast neutron flux with an overall accuracy better than 5%. FNDS is now operational and is assumed to be the first and unique acquisition system able to provide an online measurement of the fast neutron flux in MTR conditions. This system will be used to perform spectral neutron characterization of JHR channels, but it may also be implemented in future irradiation experiments, for a better and real-time evaluation of the fast neutron flux received by material and fuel samples.