Thermal and Fast Neutron Measurement in the STU Mini Labyrinth Experiment
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Abstract
The Mini Labyrinth experiment is a neutron and gamma shielding experiment constructed at the Slovak University of Technology in Bratislava (STU). The STU Mini Labyrinth consists of NEUTRONSTOP shielding, blocks of moderators, various neutron sources, a graphite prism, and the detector handling robot. It was designed for research and education purposes, while several experiments are also available online or a hybrid form. There have been several versions of the Mini Labyrinth developed, while currently the V3 version is available. This paper presents the methodology to effectively perform thermal and fast neutron measurements using a PuBe neutron source. In the experiment presented in this paper also active and passive detectors were used, and moderator materials were investigated to slightly shift the neutron spectrum. As for active detectors, the SNM-11 boron coated corona detector was used. Among passive detectors the CR-39 track detectors were investigated. The measurements were carried out in two configurations and the results were evaluated by simulations using the SCALE6 system
Article Details
Keywords
Mini Labyrinth, Radiation protection, SCAL6, CR-39, SNM-11
References
[2]. Š. Čerba, B. Vrban, J. Lüley et al., Monitoring og the Radiation Doses Around the Mini Labyrinth experimental Workspace at STU, Radiation Protection Dosimetry, Vol 198, 628-633 (2022).
[3]. B. Vrban, Š. Čerba, J. Lüley et al., The Mini Labyrinth Benchmark for Radiation Protection and Shielding Analysis, IEEE Transactions of Nuclear Science, Vol 69, 745-752 (2022).
[4]. Š. Čerba, B. Vrban, J. Lüley et al., Thermal neutron measurement in the STU Mini Labyrinth experiment, The European Physics Journal Special Topics, Vol 232, 1665-1676 (2023).
[5]. Š. Čerba, B. Vrban, J. Lüley et al., Evaluation of Shielding Materials for the DD Type Neutron Generator in the Mini Labyrinth Experiment. Proc. APCOM 2023. Melville: AIP Publishing, Accepted for publication.
[6]. Track Analysis Systems Ltd., Tasl Image System, (TASL, 2022)
[7]. T. Yamauchi, M. Kanasaki, R.Barillon, Methodological and conceptual progress in studies on the latetnt track in PADC, Polymers, Vol 13 (2021)
[8]. B. T. Rearden and M. A. Jessee, SCALE Code System, Version 6.2.3. Oak Ridge, Tennesse: Oak Ridge National Laboratory, (ORNL, USA, 2018).
[9]. M. B. Chadwick, M. Herman, P. Obložinský, ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and Decay Data, Nuclear Data Sheets 112, 2887-2996 (2011).
[10]. International Commission of Regulation Units, ICRU Report 57: Conversion Coefficients for use in Radiological Protection against External Radiation, (ICRU, Bethesda, 1998).