Radiation characterization summary of the NETL beam port 1/5 free-field environment at the 128-inch core centerline adjacent location [PDF]
EPJ Web of ConferencesThe characterization of the neutron, prompt gamma-ray, and delayed gamma-ray radiation fields in the University of Texas at Austin Nuclear Engineering Teaching Laboratory (NETL) TRIGA reactor for the beam port (BP) 1/5 free-field environment at the 128 ...
Redhouse Danielle +6 more
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Urania, 2019 NEUTRONIC AND THERMAL HYDRAULICS ANALYSIS OF CONTROL ROD EFFECT ON THE OPERATION SAFETY OF TRIGA 2000 REACTOR. Analysis of neutronic and thermal-hydraulics parameters of whole operation cycle is very important for the safety of reactor operation.
Surian Pinem +2 more
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TRIGA-2000 Research Reactor Thermal-hydraulic Analysis using RELAP/SCDAPSIM/MOD3.4
International Journal of Technology, 2017 Any events presumed to risk the safety of a nuclear reactor should be analyzed. In a research reactor, the applicability of best estimate thermal-hydraulic codes has been assessed for safety analysis purposes.
Anhar Riza Antariksawan +4 more
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E-SiCure Collaboration Project: Silicon Carbide Material Studies and Detector Prototype Testing at the JSI TRIGA Reactor [PDF]
EPJ Web of Conferences, 2020 In 2016, the ”E-SiCure” project (standing for Engineering Silicon Carbide for Border and Port Security), funded by the NATO Science for Peace and Security Programme, was launched.
Radulović Vladimir +10 more
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Qualification of the Industrialized Libera MONACO 3 Digital Acquisition System dedicated to Fission/Ion Chamber Measurements in Research Reactors [PDF]
EPJ Web of Conferences, 2023 The CEA Sensor, Dosimetry and Instrumentation Laboratory (LDCI) has been working since 2011 on an integrated acquisition system called MONACO, ’Multichannel Online Neutron Acquisition in Campbell mOde’, for fission chamber measurements.
Barbot Loic +10 more
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SILICON CARBIDE NEUTRON DETECTOR PROTOTYPE TESTING AT THE JSI TRIGA REACTOR FOR ENHANCED BORDER AND PORTS SECURITY [PDF]
EPJ Web of Conferences, 2021 In 2016, the “E-SiCure” project (standing for “Engineering Silicon Carbide for Border and Port Security”), funded by the NATO Science for Peace and Security Programme was launched.
Radulović Vladimir +11 more
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MethodsX, 2018 This paper describes the development of a custom-designed underwater scanner to support the experimental works for characterizing irradiated fuel stored in the TRIGA PUSPATI pool by means of radiography technique. Materials used to build the scanner are aluminum 6061, lead and teflon.
Mohamad Annuar Assadat Husain +3 more
openaire +6 more sources
Estimation of Na-24 activity concentration in BAEC TRIGA Research Reactor
Results in Physics, 2017 The Bangladesh Atomic Energy Commission (BAEC) TRIGA Research Reactor is a unique nuclear installation of the country generally implemented for a wide variety of research applications and serves as an excellent source of neutron. During reactor operation
M. Ajijul Hoq +4 more
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Calculation of the Neutron Parameters for Accelerator-Driven Subcritical Reactors
Science and Technology of Nuclear Installations, 2021 In this paper, the accelerator-driven subcritical reactor (ADSR) is simulated based on structure of the TRIGA-Mark II reactor. A proton beam is accelerated and interacts on the lead target. Two cases of using lead are considered here: firstly, solid lead
Tien Tran Minh, Dung Tran Quoc
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Experimental and MCNP5 based evaluation of neutron and gamma flux in the irradiation ports of the University of Utah research reactor [PDF]
Nuclear Technology and Radiation Protection, 2012 Neutron and gamma flux environment of various irradiation ports in the University of Utah training, research, isotope production, general atomics reactor were experimentally assessed and fully modeled using the MCNP5 code.
Noble Brooklyn +2 more
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