Title :
Gamma and neutron detector performance in a MOX fuel fabrication plant environment
Author :
Lavietes, Anthony ; Liguori, Cesare ; Pickrell, Mark ; Plenteda, Romano ; Sweet, Martin ; Shigeyama, Masura ; Asano, Takashi ; Nagatani, Taketeru ; Nakajima, Shinji
Author_Institution :
Int. Atomic Energy Agency, Vienna, Austria
fDate :
Oct. 30 2010-Nov. 6 2010
Abstract :
Effectively implementing safeguards in fuel reprocessing and fuel fabrication plants requires the extensive use of state-of-the-art instrumentation for accurate material characterization. The ability to rapidly and continuously determine the material balance in a large facility is essential to control and reduce the risk of diversion. Multiple detection technologies are implemented that provide the necessary Continuity of Knowledge (CoK) and inventory control required for effective safeguards. In a Pu/U-oxide (MOX) fuel processing facility, much of the detection technology is based on moderated 3He neutron detectors. Recent concerns with respect to the possible lack of sufficient quantities of 3He has resulted in the interest in developing alternative detection technologies for current and future needs and applications. To address this situation, we have begun a series of experiments at a MOX fuel fabrication facility to determine the performance and suitability of liquid scintillator neutron detectors. MOX fuel in the form of reactor fuel assembly fuel rods and large volume MOX powder containers typically found in such production facilities were measured. In addition, high-purity Germanium (HPGe) and cadmium zinc telluride (CZT) detectors will be included to determine their respective performance characteristics in a large and complex fuel production environment. The results of these experiments will be used for consideration in the development and deployment of new safeguards systems in large, complex facilities such as the Japan Mixed-Oxide Fuel Fabrication Facility (J-MOX) or the Rokkasho Reprocessing Plant (RRP). This paper will present and discuss the results of the first series of experiments, conducted at PPFF (Plutonium Fuel Development Center Plutonium Fuel Facility) of JAEA, as well as describe the next steps in this process.
Keywords :
fission reactor fuel reprocessing; germanium radiation detectors; liquid scintillation detectors; neutron detection; nuclear materials safeguards; 3He neutron detectors; MOX fuel fabrication plant environment; Pu-U-oxide fuel processing facility; cadmium zinc telluride detector; continuity of knowledge; detection technology; fuel fabrication plant; fuel production environment; fuel reprocessing plant; gamma detector performance; high-purity germanium detector; inventory control; large volume MOX powder containers; liquid scintillator neutron detectors; material balance; material characterization; multiple detection technologies; neutron detector performance; performance characteristics; reactor fuel assembly fuel rods; Data acquisition; Detectors; Fabrication; Fuels; Neutrons; Pins; Powders; Electromechanically-cooled high purity germanium; MOX fuel fabrication; liquid scintillator neutron detector; neutron coincidence counting;
Conference_Titel :
Nuclear Science Symposium Conference Record (NSS/MIC), 2010 IEEE
Conference_Location :
Knoxville, TN
Print_ISBN :
978-1-4244-9106-3
DOI :
10.1109/NSSMIC.2010.5873846