International benchmarks for cross-sections qualification are very poor in experimental means able to provide information on the neutron spectrum around 1 MeV. To fill this vacancy, one possible solution is to use the activation of rhodium. The reaction of inelastic neutron scattering on this element, in the energy range of 0.5 MeV to 5 MeV, leads to the formation of 103 Rh m . The return to the ground level of this radionuclide emits X-rays of low energy. This paper describes a method for determining the activity of 103 Rh m taking into account the constraining characteristics of this radionuclide and proposes a computed to measured results comparison for an experiment irradiated in the French CEA critical facility EOLE. Index Terms-efficiency calibration, 103 Rh m , X-ray measurement, scattered rays, escape rays. K α Bump scattered Raie K α = 20,17 keV Raie K α1 = 20,22 keV Raie K α2 = 20,07 keV K β bump scattered Raie K β2 23,20 keV Raie K β1 22,81 keV Raie K β = 22,87 keV K α Bump scattered Raie K α = 20,17 keV Raie K α1 = 20,22 keV Raie K α2 = 20,07 keV K β bump scattered Raie K β2 23,20 keV Raie K β1 22,81 keV Raie K β = 22,87 keV
The main goal of the Reactor Dosimetry is to provide information (reaction rates, fluence, fluence rate...) for the interpretation of experiments irradiated in critical mock-up, test reactors or power nuclear reactors. Various techniques are used, including analysis of irradiated activation or fission dosimeters whose radioactivity is measured afterwards.The MADERE platform (Measurement Applied to DosimEtry for REactors) is a CEA facility which is dedicated to the activation dosimeters manufacturing and their activity measurement after irradiation in a nuclear reactor. The laboratory is accredited by the French Accreditation Committee for specific activity measurements of solid samples using gamma and X-rays spectrometry.The choice of dosimeters takes into account limitations coming from the characteristics of the measurement devices. To meet experimenter's new demands, the MADERE platform set out to improve its offer by lowering the energy of measured radiations down to 10 keV, and the activity level down to the tenth of Becquerel (Bq). Doing so, the range of usable dosimeters and by the way, the energy range of the neutron spectrum is expanded.Dosimeter, wires or foils, few millimeters large, are manufactured using ultra-pure material (Gold, Iron, Nickel,...). Some of them are encapsulated in quartz containers for integration into experimental devices.
CABRI is an experimental pulse reactor operated by CEA at the Cadarache research center. Since 1978 the experimental programs have aimed at studying the fuel behavior under Reactivity Initiated Accident (RIA) conditions. Since 2003, it has been refurbished in order to be able to provide RIA and LOCA (Loss Of Coolant Accident) experiments in prototypical PWR conditions (155bar, 300°C). This project lied within a broader scope including an overall facility refurbishment and a safety review. The global modification is conducted by the CEA project team. It is funded by IRSN, which is conducting the CIP experimental program, in the framework of the OECD/NEA project CIP. It is financed in the framework of an international collaboration. During the reactor restart, commissioning tests are realized for all equipment, systems and circuits of the reactor. In particular neutronics and power commissioning tests will be performed respectively in 2015 and 2016. This paper focuses on the design of a complete and original dosimetry program that was built in support to the CABRI core characterization and to the power calibration. Each one of the above experimental goals will be fully described, as well as the target uncertainties and the forecasted experimental techniques and data treatment.
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