Neutronics and thermal hydraulic analysis of TRIGA Mark II reactor using MCNPX and COOLOD-N2 computer code
Author:
Publisher
IOP Publishing
Subject
General Physics and Astronomy
Link
http://stacks.iop.org/1742-6596/860/i=1/a=012035/pdf
Reference11 articles.
1. Benchmark Analysis of Criticality Experiments in the TRIGA Mark II Using a Continuous Energy Monte Carlo Code MCNP
2. Steady-state thermal-hydraulic analysis of the Moroccan TRIGA MARK II reactor by using PARET/ANL and COOLOD-N2 codes
3. Fuel behavior comparison for a research reactor
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1. Neutronic Parameter Analysis of Plate-Type Fueled TRIGA 2000 Reactor by MCNPX;Atom Indonesia;2023-06-13
2. Neutronic calculations and thermalhydraulic application using CFD for the nuclear research reactor NUR at steady state mode;Progress in Nuclear Energy;2023-05
3. CFD simulation of partial channel blockage on plate-type fuel of TRIGA-2000 conversion reactor core;Acta Polytechnica;2022-08-31
4. Analysis of DNBR TRIGA 2000 calculation results using STAT and COOLOD-N2;PROCEEDINGS OF INTERNATIONAL CONFERENCE ON NUCLEAR SCIENCE, TECHNOLOGY, AND APPLICATION 2020 (ICONSTA 2020);2021
5. Heat removal analysis in the AP1000 reactor’s refuelling process;Journal of Physics: Conference Series;2019-04
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