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
doaj +1 more source
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
doaj +1 more source
Proposed design for the PGAA facility at the TRIGA IPR-R1 research reactor [PDF]
SpringerPlus, 2013 Abstract Background This work presents an initial proposed design of a Prompt Gamma Activation Analysis (PGAA) facility to be installed at the TRIGA IPR-R1, a 60 years old research reactor of the Centre of Development of Nuclear Technology (CDTN) in Brazil.
Guerra, Bruno T +3 more
openaire +2 more sources
Revista Investigaciones y Aplicaciones Nucleares, 2019 With cooperation of the International Atomic Energy Agency (IAEA), thermal-hydraulic calculations were carried out for conversion of the IAN-R1 Reactor from MTR-HEU fuel to TRIGA-LEU fuel. To establish thermal-hydraulic calculation and analysis research
José Antonio Sarta +1 more
doaj +1 more source
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
doaj +1 more source
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
doaj +1 more source
Determination of backscattered neutrons/gammas from open beam port of a research reactor [PDF]
EPJ Web of Conferences, 2020 Neutron and gamma dose rate calculations were carried out around horizontal beam tube no. 5 at the Jožef Stefan Institute (JSI) TRIGA Mark II research reactor.
Jazbec Anže +4 more
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Power calibration of the TRIGA mark I nuclear research reactor [PDF]
Journal of the Brazilian Society of Mechanical Sciences and Engineering, 2007 This paper presents the results and methodology used to calibrate the thermal power of the TRIGA Mark I IPR-R1 Research Reactor at the Nuclear Technology Development Centre (CDTN), in Belo Horizonte, Brazil. The TRIGA Mark I is a pool type reactor, cooled by water natural convection.
Mesquita, Amir Z. +2 more
openaire +3 more sources
Validation of a New Design of Tellurium Dioxide-Irradiated Target
Nuclear Engineering and Technology, 2016 Production of iodine-131 by neutron activation of tellurium in tellurium dioxide (TeO2) material requires a target that meets the safety requirements. In a radiopharmaceutical production unit, a new lid for a can was designed, which permits tight sealing
Aziz Fllaoui +6 more
doaj +1 more source
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
doaj +1 more source