A Comparison of the PARET/ANL and RELAP5/MOD3 Codes for the Analysis of IAEA Benchmark Transients
WL Woodruff, NA Hanan, RS Smith, JE Matos - 1996 - osti.gov
The PARET/ANL and RELAP5/MOD3 codes are used to analyze the series of benchmark
transients specified for the IAEA Research Reactor Core Conversion Guidebook (IAEA …
transients specified for the IAEA Research Reactor Core Conversion Guidebook (IAEA …
Spatially-Dependent Reactor Kinetics and Supporting Physics Validation Studies at the High Flux Isotope Reactor
D Chandler - 2011 - trace.tennessee.edu
The computational ability to accurately predict the dynamic behavior of a nuclear reactor
core in response to reactivity-induced perturbations is an important subject in the field of …
core in response to reactivity-induced perturbations is an important subject in the field of …
Predicting large deflections of multiplate fuel elements using a monolithic FSI approach
As part of the Global Threat Reduction Initiative, the Oak Ridge National Laboratory is
evaluating conversion of fuel for the High Flux Isotope Reactor (HFIR) from high-enriched …
evaluating conversion of fuel for the High Flux Isotope Reactor (HFIR) from high-enriched …
Conceptual design loss-of-coolant accident analysis for the advanced neutron source reactor
NCJ Chen, MW Wendel, GL Yoder Jr - Nuclear technology, 1994 - Taylor & Francis
A RELAP5 system model for the Advanced Neutron Source Reactor has been developed for
performing conceptual safety analysis report calculations. To better represent thermal …
performing conceptual safety analysis report calculations. To better represent thermal …
Evaluation of HFIR LEU Fuel Using the COMSOL Multiphysics Platform
LP Tschaepe - 2009 - trace.tennessee.edu
A finite element computational approach to simulation of the HFIR core thermal-fluid
behavior is developed. These models were developed to facilitate design of a low enriched …
behavior is developed. These models were developed to facilitate design of a low enriched …
Deflection predictions of involute-shaped fuel plates using a fully-coupled numerical approach
This paper describes the modeling and simulation of fluid structure interactions (FSI) of
involute-shaped fuel plates used in nuclear research reactors. We believe this to be the first …
involute-shaped fuel plates used in nuclear research reactors. We believe this to be the first …
Engineering uncertainty analysis of the heat transfer of fuel plates
W Xu, H Xie, J Li, F Xie, L Shi - Nuclear Engineering and Design, 2023 - Elsevier
Uranium-containing aluminum-cladding dispersion plate fuels are widely used in various
research reactors owing to their excellent heat-transfer capability. In the nuclear design …
research reactors owing to their excellent heat-transfer capability. In the nuclear design …
[PDF][PDF] Application of COMSOL Pipe Flow Module To Develop a High Flux Isotope Reactor (HFIR) System Loop Model
Application of COMSOL Pipe Flow Module To Develop a High Flux Isotope Reactor (HFIR)
System Loop Model Page 1 Application of COMSOL Pipe Flow Module To Develop a High …
System Loop Model Page 1 Application of COMSOL Pipe Flow Module To Develop a High …
Thermal Hydraulic Characteristics of Fuel Defects in Plate Type Nuclear Research Reactors
IT Bodey - 2014 - trace.tennessee.edu
Turbulent flow coupled with heat transfer is investigated for a High Flux Isotope Reactor
(HFIR) fuel plate. The Reynolds Averaged Navier-Stokes Models are used for fluid dynamics …
(HFIR) fuel plate. The Reynolds Averaged Navier-Stokes Models are used for fluid dynamics …
Complex Geometry Creation and Turbulent Conjugate Heat Transfer Modeling
I Bodey, R Arimilli, JD Freels - 2011 - osti.gov
The multiphysics capabilities of COMSOL provide the necessary tools to simulate the
turbulent thermal-fluid aspects of the High Flux Isotope Reactor (HFIR). Version 4.1, and …
turbulent thermal-fluid aspects of the High Flux Isotope Reactor (HFIR). Version 4.1, and …