Steady-state and transient simulations of the MTR research reactor using the high-fidelity N-TH coupling method

Q Xie, X Chai, X Liu - Progress in Nuclear Energy, 2023 - Elsevier
The tremendous advancement in computer technology makes it feasible to perform high-
fidelity and multi-physics numerical simulations of reactors, allowing for a more accurate and …

Developing a practical optimization of the refueling program for ordinary research reactors using a modified simulated annealing method

A Hedayat - Progress in Nuclear Energy, 2014 - Elsevier
Each core configuration of a research reactor can be optimized to provide particular or
general multi-purpose irradiating conditions; specially, it includes refueling cycle length and …

High-fidelity steady-state and transient simulations of an MTR research reactor using Serpent2/subchanflow

JC Almachi, VH Sánchez-Espinoza, U Imke - Energies, 2022 - mdpi.com
In order to join efforts to develop high-fidelity multi-physics tools for research reactor
analysis, the KIT is conducting studies to modify the coupled multi-physics codes developed …

Highly-detailed neutronic and thermal-hydraulic coupled calculations for OPAL reactor using diverse codes and approaches

D Ferraro, I Ferrari, A Doval, E Villarino… - Nuclear Engineering and …, 2024 - Elsevier
The industry-standard approach for designing and operating research reactors cores relies
on well-established methodologies that consider uncoupled neutronic calculations and a …

International benchmark study of advanced thermal hydraulic safety analysis codes against measurements on IEA-R1 research reactor

A Hainoun, A Doval, P Umbehaun… - … Engineering and Design, 2014 - Elsevier
In the framework of the IAEA Coordination Research Project on “Innovative methods in
research reactor analysis: Benchmark against experimental data on neutronics and thermal …

Research of two-phase flow instability in parallel narrow multi-channel system

G Xia, M Peng, Y Guo - Annals of Nuclear Energy, 2012 - Elsevier
Two-phase flow instabilities have been highly researched in the past decades. Many
researches gave different stability criterions based on experiments or calculations. However …

Benchmarking verification of the control rod effects on the MTR core parameters using the MTR-PC and MCNP codes throughout 3D core modeling and rod-drop …

A Hedayat - Progress in Nuclear Energy, 2016 - Elsevier
Verification of nuclear data and codes is highly recommended for reactor safety analyses. In
this research, MTR-PC package and MCNP 4C are used as deterministic and Monte Carlo …

Neutronic analysis of the LVR-15 research reactor using the PARCS code

A Dambrosio, M Ruščák, G Mazzini, A Musa - Annals of Nuclear Energy, 2018 - Elsevier
Research reactors, together with the computational codes, represent a valuable tool
combination to investigate over phenomena which can take place in nuclear power plants …

Source term evaluation for the upgraded LEU Pakistan Research Reactor-1 under severe accidents

S Ullah, SE Awan, NM Mirza, SM Mirza - Nuclear Engineering and Design, 2010 - Elsevier
Evaluation of source term has been carried out for the upgraded LEU PARR-I system taken
as a typical material test reactor (MTR). The modeling and simulation of release of …

Analysis of loss of flow events on brazilian multipurpose reactor using the relap5 code

HV Soares, ID Aronne, AL Costa… - … Journal of Nuclear …, 2014 - Wiley Online Library
This work presents the thermal hydraulic simulation of the Brazilian multipurpose reactor
(RMB) using a RELAP5/MOD3. 3 model. Beyond steady state calculations, three transient …