Abstract
A well characterized radiation field inside a research nuclear reactor irradiation facilities enables precise qualification of radiation effects to the irradiated samples such as nuclear heating or changes in their electrical or material properties. To support the increased utilization of the JSI TRIGA reactor irradiation facilities in the past few years mainly on account of testing novel detector designs, electronic components and material samples, we are working on increasing the neutron and gamma field characterization accuracy using various modeling and measurement techniques. In this paper we present the dose field measurements using thermo-luminescent detectors (TLD’s) with different sensitivities neutron and gamma sensitivities, along with multiple ionization and fission chamber. Experiment was performed in several steps from reactor start-up, steady operation and a rapid shutdown, during which the ionization and fission chamber signals were acquires continuously, while the TLD’s were being irradiated at different stages during reactor operation and after shutdown, to also capture response to delayed neutron and gamma field. The results presented in this paper serve for validation of JSI designed JSIR2S code for delayed radiation field determination, initial results of its application on the JSI TRIGA TLD measurements will also be presented.
Highlights
In order to increase the utilization of irradiation facilities inside a research nuclear reactor for purpose of sample irradiation and characterization of its response, a detailed radiation field characterization is required
In order to obtain absolute dose-rate values, a series of TLD measurements were performed in different irradiation, which were irradiated during different stages of of reactor operation and after shutdown
In this paper we present the use of nautroal and enriched Li thermo-luminescent detectors (TLD’s) for measurements of high intensity mixed radiation field of the Jozef Stefan Institute (JSI) TRIGA reactor irradiation facilities, using high temperature readout techniques for a dose measurement range from 0.1 Gy to MGy
Summary
In order to increase the utilization of irradiation facilities inside a research nuclear reactor for purpose of sample irradiation and characterization of its response, a detailed radiation field characterization is required. This is usually performed as a combination of experiments and simulations, which are validated by experimental data. The Jozef Stefan Institute (JSI) TRIGA Mark II research reactor is equipped with numerous in-core and ex-core irradiation facilities, utilization of which has increased mainly on account of a well characterized neutron field and increasing accuracy of gamma field characterization for the novel radiation detectors and measurement techniques [1], Identify applicable funding agency here. In this paper we present the use of nautroal and enriched Li TLD’s for measurements of high intensity mixed radiation field of the JSI TRIGA reactor irradiation facilities, using high temperature readout techniques for a dose measurement range from 0.1 Gy to MGy
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