Abstract
The neutron field of various irradiation positions of the TRIGA Mark II reactor of the Jožef Stefan Institute has been thoroughly characterized by neutron activation dosimetry and miniature fission chambers techniques. In order to have a fully validated calculation scheme to analyze and plan experiments, the gamma field also has to be experimentally validated. The 10-year long collaboration between CEA and JSI is a perfect framework to carry out such a study, and measurements of the gamma field started in late 2016. Several measurement techniques were investigated in in-core and ex-core positions. On-line measurements were carried out using miniature ionization chambers manufactured by the CEA and PTW Farmer ionization chambers. Positional dependence was studied, showing a decrease in the delayed gamma contribution to the total gamma flux with increasing distance from the reactor core center. To characterize the gamma dose in the core, as well as in the periphery, thermo- and optically stimulated luminescent detectors were tested. These detectors are commonly used at CEA to measure the gamma dose in a given material in order to study the nuclear heating in various core elements (control rod, baffle, structural material). Different filters were used in order to assess an integrated dose ranging from a few Gy up to several kGy. The feasibility of such measurements demonstrates the complementarity between measurements with dosimetry and ionization chambers from low to very high gamma-dose environment, such as in material testing reactors.
Highlights
IntroductionTHE ability of a research reactor to perform precise irradiations (for electronic components, biological samples, sensors,...) lies with its neutron and gamma fields characterization
THE ability of a research reactor to perform precise irradiations lies with its neutron and gamma fields characterization
In steady state operating mode, the neutron field of various irradiation positions of the TRIGA Mark II reactor of the Jožef Stefan Institute has already been measured by means of neutron activation dosimetry and miniature fission chambers techniques [1]-[3]
Summary
THE ability of a research reactor to perform precise irradiations (for electronic components, biological samples, sensors,...) lies with its neutron and gamma fields characterization. In steady state operating mode, the neutron field of various irradiation positions of the TRIGA Mark II reactor of the Jožef Stefan Institute has already been measured by means of neutron activation dosimetry and miniature fission chambers techniques [1]-[3]. The integrated dose is read thanks to light stimulation of the detector. The read out process is non-destructive, and the detector cannot be annealed afterwards.
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