Abstract
Preliminary calculations were performed with the aim to establish optimal experimental conditions for the measurement campaign within the collaboration between the Jožef Stefan Institute (JSI) and Commissariat à l’Énergie Atomique et aux Énergies Alternatives (CEA Cadarache). The goal of the project is to additionally characterize the neutron spectruminside the JSI TRIGA reactor core with focus on the measurement epi-thermal and fast part of the spectrum. Measurements will be performed with fission chambers containing different fissile materials (235U, 237Np and 242Pu) covered with thermal neutron filters (Cd and Gd). The changes in the detected signal and neutron flux spectrum with and without transmission filter were studied. Additional effort was put into evaluation of the effect of the filter geometry (e.g. opening on the top end of the filter) on the detector signal. After the analysis of the scoping calculations it was concluded to position the experiment in the outside core ring inside one of the empty fuel element positions.
Highlights
The power distribution in a nuclear reactor can be monitored by neutron detectors, the signal of which depends on the neutron spectrum
Within the bilateral collaboration project between the Jozef Stefan Institute (JSI) and the Commissariat al’Energie Atomique et aux Energies Alternatives (CEA Cadarache), an extensive experimental campaign is planned at the JSI TRIGA reactor [1] with the aim to establish an on-line neutron spectrum adjustment method
It can be observed that both filter materials efficiently decrease the thermal neutron part
Summary
The power distribution in a nuclear reactor can be monitored by neutron detectors, the signal of which depends on the neutron spectrum. Within the bilateral collaboration project between the Jozef Stefan Institute (JSI) and the Commissariat al’Energie Atomique et aux Energies Alternatives (CEA Cadarache), an extensive experimental campaign is planned at the JSI TRIGA reactor [1] with the aim to establish an on-line neutron spectrum adjustment method. Fission chambers containing different fissile deposits have different energy sensitivity profiles due to different energy dependences of the fission cross-section. The transmission filters act as thermal neutron absorbers and shift the sensitivities to the epi-thermal and fast parts of the neutron spectrum. From the measured fission rates, the magnitudes of the thermal, epi-thermal and fast components of the neutron spectra will be deduced. The effect of different filter geometries (dimensions, material and presence of openings) on the neutron spectra was evaluated
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