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Rousseau, G.; Chambru, L.; Authier, N.
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] In the context of criticality accident alarm system tests, several experiments were carried out in 2013 on the PROSPERO reactor to study the response to neutron and gamma of different devices and dosimeters, particularly on the SNAC2 dosimeter. This article presents the results of this criticality dosimeter in different configurations, and compares the experimental measurements with the results of calculation performed with the TRIPOLI-4 Monte-Carlo Neutral Particles transport code. PROSPERO is a metallic critical assembly managed by the Criticality, Neutron Science and Measurement Department located at the French CEA Research Center of Valduc. The core, surrounded by a reflector of depleted uranium, is composed of 2 horizontal cylindrical blocks made of a highly enriched uranium alloy which can be placed in contact, and of 4 depleted uranium control rods which allow the reactor to be driven. This reactor, placed in a cell 10 m x 8 m x 6 m high, with 1.4-meter-thick concrete walls, is used as a fast neutron spectrum source and is operated at stable power level in delayed critical state, which can vary from 3 mW to 3 kW. PROSPERO is extensively used for electronic hardening or to study the effect of the neutrons on various materials. The SNAC2 criticality dosimeter is a zone dosimeter allowing the off line measurement of criticality accident neutron doses. This dosimeter consists of the pile up of seven activation foils embedded into a 23 mm diameter x 21 mm height cadmium container. The activation measurement of each foil, using a gamma spectroscopy technique, gives information about the neutron reaction rates. The SNAC2 software allows the spectrum unfolding from these values, taking into account the hypothesis of a particular spectrum shape, in three components: a Maxwell spectrum component for the thermal range, a 1/E component for the epithermal range, and a Watt spectrum component for the high energy range. Moreover, from the neutron spectrum, the SNAC software can calculate the neutron fluence integrated by the dosimeter and the neutron dose. During the 3 weeks measurement campaign many radioprotection devices were used. To modify the spectrum seen by these devices, several shields of various thicknesses made of concrete or polyethylene, with or without cadmium covers, were placed in the PROSPERO cell. These devices allow the study of criticality accident spectra in several environments: from metal to pseudo liquid. The fluxes measured by the SNAC2 devices were compared with TRIPOLI-4 calculations. (authors)
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2015; 13 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; 1 Refs.
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Miscellaneous
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Conference
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ALARM SYSTEMS, CADMIUM, COMPARATIVE EVALUATIONS, CRITICALITY, DEPLETED URANIUM, DOSEMETERS, FAST NEUTRONS, GAMMA SPECTROSCOPY, HIGHLY ENRICHED URANIUM, METERS, MONTE CARLO METHOD, NEUTRAL-PARTICLE TRANSPORT, NEUTRON REACTIONS, NEUTRON SPECTRA, POLYETHYLENES, RADIATION ACCIDENTS, SPECTRA UNFOLDING, ZERO POWER REACTORS
ACCIDENTS, ACTINIDES, BARYON REACTIONS, BARYONS, CALCULATION METHODS, DATA PROCESSING, ELEMENTARY PARTICLES, ELEMENTS, ENRICHED URANIUM, EVALUATION, EXPERIMENTAL REACTORS, FERMIONS, HADRON REACTIONS, HADRONS, ISOTOPE ENRICHED MATERIALS, MATERIALS, MEASURING INSTRUMENTS, METALS, NEUTRONS, NUCLEAR REACTIONS, NUCLEON REACTIONS, NUCLEONS, ORGANIC COMPOUNDS, ORGANIC POLYMERS, POLYMERS, POLYOLEFINS, PROCESSING, RADIATION TRANSPORT, REACTORS, RESEARCH AND TEST REACTORS, SPECTRA, SPECTROSCOPY, URANIUM
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