Author

Javier Ortensi

Observed names: J Ortensi, J. Ortensi, Javier (Javi) Ortensi, Ortensi, J., Ortensi, Javier

Observed institutions: Argonne National Laboratory, United States Department of Energy, Office of Scientific and Technical Information, Idaho National Laboratory, Government of the United States of America, University of Chicago, National Technical Information Service, Massachusetts Institute of Technology

ORCID: 0000-0003-1685-3916

Observed ORCID: 0000-0003-1685-3916

OpenAlex ID: A5032016396

Physics-based multiscale coupling for full core nuclear reactor simulation

2014 · Derek R. Gaston, Cody J. Permann, et al. · Annals of Nuclear Energy · 327

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Coupled Multiphysics Simulations of Heat Pipe Microreactors Using DireWolf

2021 · Christopher Matthews, Vincent Laboure, et al. · Nuclear Technology · 85

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Rattlesnake: A MOOSE-Based Multiphysics Multischeme Radiation Transport Application

2021 · Yaqi Wang, Sebastian Schunert, et al. · Nuclear Technology · 75

Griffin Software Development Plan

2021 · Changho Lee, Yeon Jung, et al. · 56

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The US Department of Energy’s high temperature reactor research and development program – Progress as of 2019

2019 · H.D. Gougar, D.A. Petti, et al. · Nuclear Engineering and Design · 45

Cumulative migration method for computing rigorous diffusion coefficients and transport cross sections from Monte Carlo

2017 · Zhaoyuan Liu, Kord Smith, et al. · Annals of Nuclear Energy · 45

A Newton solution for the Superhomogenization method: The PJFNK-SPH

2017 · Javier Ortensi, Yaqi Wang, et al. · Annals of Nuclear Energy · 45

Multi-Physics Simulations of Heat Pipe Micro Reactor

2019 · Argonne National Lab. (ANL), Argonne, IL (United States), G. Hu, et al. · 42

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Survey of dust production in pebble bed reactor cores

2011 · Joshua J. Cogliati, Abderrafi M. Ougouag, et al. · Nuclear Engineering and Design · 31

Deterministic Modeling of the High Temperature Test Reactor

2010 · J Ortensi, J Cogliati, et al. · 26

A flexible nonlinear diffusion acceleration method for the S transport equations discretized with discontinuous finite elements

2017 · Sebastian Schunert, Yaqi Wang, et al. · Journal of Computational Physics · 24

Two-step neutronics calculations with Shift and Griffin for advanced reactor systems

2022 · Tara M. Pandya, Friederike Bostelmann, et al. · Annals of Nuclear Energy · 21

An equilibrium core depletion algorithm for pebble-bed reactors in the Griffin code

2023 · Sebastian Schunert, Javier Ortensi, et al. · Annals of Nuclear Energy · 20

Validation of the Griffin application for TREAT transient modeling and simulation

2021 · Javier Ortensi, Benjamin A. Baker, et al. · Nuclear Engineering and Design · 20

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CYNOD: A Neutronics Code for Pebble Bed Modular Reactor Coupled Transient Analysis

2008 · Hikaru Hiruta, Abderrafi M. Ougouag, et al. · 18

Automated power-following control for nuclear thermal propulsion startup and shutdown using MOOSE-based applications

2023 · Vincent M. Labouré, Sebastian Schunert, et al. · Progress in Nuclear Energy · 16

Full Core TREAT Kinetics Demonstration Using Rattlesnake/BISON Coupling Within MAMMOTH

2015 · Javier Ortensi, USDOE Office of Nuclear Energy (NE), et al. · 16

Interpretation of energy deposition data from historical operation of the transient test facility (TREAT)

2017 · Mark D. DeHart, Benjamin A. Baker, et al. · Nuclear Engineering and Design · 15

PBMR Coupled Neutronics/Thermal-hydraulics Transient Benchmark. The PBMR-400 Core Design - Volume 1 The Benchmark Definition

2013 · Frederik Reitsma, Kostadin Ivanov, et al. · 13

Analysis of an Earthquake-Initiated-Transient in a PBR

2009 · Ougouag, A. M., Ortensi, J., et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 13

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Criticality calculations of the Very High Temperature Reactor Critical Assembly benchmark with Serpent and SCALE/KENO-VI

2015 · Friederike Bostelmann, Hans R. Hammer, et al. · Annals of Nuclear Energy · 11

Gas-Cooled High-Temperature Pebble-Bed Reactor Reference Plant Model

2023 · Mustafa Jaradat, USDOE Office of Nuclear Energy (NE), Nuclear Energy Advanced Modeling and Simulation (NEAMS), et al. · 10

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Performance Improvements for the Griffin Transport Solvers

2021 · Yaqi Wang, Zachary Prince, et al. · 10

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THETRIS: A micro-scale temperature and gas release model for TRISO fuel

2011 · Javier Ortensi, Brian Boer, et al. · Nuclear Engineering and Design · 10

Improved Prediction of the Temperature Feedback in TRISO-Fueled Reactors

2009 · Javier Ortensi, Abderrafi M. Ougouag · 10

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Works count: 127

Citation count: 1,256

H-index: 16

I10-index: 25