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Rossa, Riccardo; Borella, Alessandro; Van der Meer, Klaas; Labeau, Pierre-Etienne; Pauly, Nicolas
Institute of Electrical and Electronics Engineers - IEEE, 3 Park Avenue, 17th Floor, New York, N.Y. 10016-5997 (United States)2015
Institute of Electrical and Electronics Engineers - IEEE, 3 Park Avenue, 17th Floor, New York, N.Y. 10016-5997 (United States)2015
AbstractAbstract
[en] The Self-Interrogation Neutron Resonance Densitometry (SINRD) is a passive neutron technique that aims at a direct quantification of "2"3"9Pu in the fuel assemblies by measuring the attenuation of the neutron flux in the energy region close to the 0.3 eV resonance of "2"3"9Pu. The "2"3"9Pu mass is estimated by calculating the SINRD signature, that is the ratio between the neutron flux integrated over the fast energy region and around the 0.3 eV resonance region. The SINRD measurement approach considered in this study consists in introducing a small neutron detector in the central guide tube of a PWR 17x17 fuel assembly. In order to measure the neutron flux in the energy regions defined in the SINRD signature, different detector types are used. The response of a bare "2"3"8U fission chamber is considered for the determination of the fast neutron flux, while other thermal-epithermal detectors wrapped in neutron absorbers are envisaged to measure the neutron flux around the resonance region. This paper provides an estimation of the count rate that can be achieved with the detector types proposed for the SINRD measurement. In the first section a set of detectors are evaluated in terms of count rate and sensitivity to the "2"3"9Pu content, in order to identify the optimal measurement configuration for each detector type. Then a study is performed to increase the count rate by increasing the detector size. The study shows that the highest count rate is achieved by using either "3He or "1"0B proportional counters because of the high neutron efficiency of these detectors. However, the calculations indicate that the biggest contribution to the measurement uncertainty is due to the measurement of the fast neutron flux. Finally, similar sensitivity to the "2"3"9Pu content is obtained by using the different detector types for the measurement of the neutron flux close to the resonance region. Therefore, the count rate associated to each detector type will play a major role in the selection of the detector types used for the SINRD measurement. (authors)
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2015; 2 p; ANIMMA 2015: 4. International Conference on Advancements in Nuclear Instrumentation Measurement Methods and their Applications; Lisboa (Portugal); 20-24 Apr 2015; Available from the INIS Liaison Officer for France, see the 'INIS contacts' section of the INIS website for current contact and E-mail addresses: http://www.iaea.org/inis/Contacts/; Country of input: France
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ACTINIDE NUCLEI, ALPHA DECAY RADIOISOTOPES, BARYONS, BORON ISOTOPES, ELEMENTARY PARTICLES, ENERGY SOURCES, ENRICHED URANIUM REACTORS, EVEN-EVEN NUCLEI, EVEN-ODD NUCLEI, FERMIONS, FUELS, HADRONS, HEAVY NUCLEI, HELIUM ISOTOPES, IONIZATION CHAMBERS, ISOTOPES, LIGHT NUCLEI, MATERIALS, MEASURING INSTRUMENTS, NEUTRON DETECTORS, NEUTRONS, NUCLEAR FUELS, NUCLEI, NUCLEONS, ODD-ODD NUCLEI, PHYSICAL PROPERTIES, PLUTONIUM ISOTOPES, POWER REACTORS, PROPORTIONAL COUNTERS, RADIATION DETECTORS, RADIATION FLUX, RADIOISOTOPES, REACTOR MATERIALS, REACTORS, SPONTANEOUS FISSION RADIOISOTOPES, STABLE ISOTOPES, THERMAL REACTORS, TUBES, URANIUM ISOTOPES, WATER COOLED REACTORS, WATER MODERATED REACTORS, YEARS LIVING RADIOISOTOPES
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