Results 71 to 80 of about 449 (175)

JSI TRIGA fuel rod reactivity worth experiments for validation of Serpent-2 and RAPID fuel burnup calculations

Nuclear Engineering and Technology
Reactivity worth of fuel rods at the JSI TRIGA research reactor was measured. Differently burned fuel rods were chosen to validate fuel burnup calculations.
Anže Pungerčič, Alireza Haghighat, Luka Snoj   +2 more
doaj   +1 more source

Benchmarking COMSOL Multiphysics Single-Subchannel Thermal-Hydraulic Analysis of a TRIGA Reactor with RELAP5 Results and Experimental Data

Science and Technology of Nuclear Installations, 2019
COMSOL Multiphysics has been used to conduct thermal-hydraulic analysis in multiple nuclear applications. The aim of this study is to benchmark the prediction accuracy of COMSOL Multiphysics in performing thermal-hydraulic analysis of TRIGA (Training ...
Ahmed K. Alkaabi, Jeffrey C. King
doaj   +1 more source

Reactor test of beryllium as self-powered neutron detector emitter for fast neutron flux measurement [PDF]

EPJ Web of Conferences
Neutron flux in nuclear reactors causes damages to material components. Fast neutrons, above 1 MeV, modify mechanical and structural properties of materials.
Dupin Elsa, Barbot Loïc, Normand Stéphane, Fontbonne Jean-Marc, Thiollay Nicolas, Destouches Christophe   +5 more
doaj   +1 more source

Thermal Hydraulic Analysis of 3 MW TRIGA Research Reactor of Bangladesh Considering Different Cycles of Burnup

Atom Indonesia, 2014
Burnup dependent steady state thermal hydraulic analysis of TRIGA Mark-II research reactor has been carried out utilizing coupled point kinetics, neutronics and thermal hydraulics code EUREKA-2/RR.
M.H. Altaf, N.H. Badrun
doaj  

Enhancing signal integrity and reactor power measurement in BTRR using line driver

Measurement: Energy
The performance of the Bangladesh Atomic Energy Commission (BAEC) TRIGA Research Reactor (BTRR) was significantly improved by addressing signal integrity issues related to the NLW-1000 logarithmic power channel.
Md. Sayed Hossain
doaj   +1 more source

Design and Implementation of a Fuzzy Controller for a TRIGA Mark III Reactor

Science and Technology of Nuclear Installations, 2012
The design and testing of a fuzzy rule based controller to regulate the power of a TRIGA Mark III research nuclear reactor are presented. The design does not require the current exact parameters of the point kinetic equations of the reactor.
Tonatiuh Rivero-Gutiérrez, Jorge S. Benítez-Read, Armando Segovia-De-los-Ríos, Luis C. Longoria-Gándara, Javier C. Palacios-Hernández   +4 more
doaj   +1 more source

Nuclear Cogeneration of Methanol and Acetaldehyde from Ethylene Glycol Using Ionizing Radiation. [PDF]

Ind Eng Chem Res, 2023
Plant AG, Kos B, Jazbec A, Snoj L, Joyce MJ, Najdanovic-Visak V.   +5 more
europepmc   +1 more source

Full core fuel burnup assessment of the ITU TRIGA Mark II research reactor using gamma spectroscopy

Nuclear Engineering and Technology
This study investigates the burnup distribution of fuel elements in the ITU TRIGA Mark II research reactor core through gamma spectroscopy using 137Cs as a burnup indicator.
Z. Boduroglu, A. Kaya, O. Erbay, I.A. Reyhancan, M.S. Kiziltas, T. Akyurek   +5 more
doaj   +1 more source

Development of a Novel Passive Monitoring Technique to Showcase the 3D Distribution of Tritiated Water (HTO) Vapor in Indoor Air of a Nuclear Facility. [PDF]

Environ Sci Technol, 2023
Feng B, Ibesich M, Hainz D, Waidhofer D, Veit-Öller M, Trunner C, Stummer T, Foster M, Nemetz M, Welch JM, Villa M, Sterba JH, Musilek A, Renz F, Steinhauser G.   +14 more
europepmc   +1 more source

Piping Flexibility Analysis of the Primary Cooling System of TRIGA 2000 Bandung Reactor due to Earthquake

Atom Indonesia, 2011
Earthquakes in a nuclear installation can overload a piping system which is not flexible enough. These loads can be forces, moments and stresses working on the pipes or equipments.
H.P. Rahardjo
doaj