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J.E. Matos

Observed names: J. E. Matos, J. Matos, Matos, J. E., Matos, J.E.
Observed institution: Argonne National Laboratory
ORCID: 0009-0006-1626-8329
Observed ORCID: 0009-0006-1626-8329
OpenAlex ID: A5065510316
Monte Carlo simulation of core physics parameters of the Nigeria Research Reactor-1 (NIRR-1)
2007 · S.A. Jonah, J.R. Liaw, et al. · Annals of Nuclear Energy · 38
Progress in the neutronic core conversion (HEU-LEU) analysis of Ghana research reactor-1.
2006 · S. Anim-Sampong, B.T. Maakuu, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 16
Safety-related benchmark calculations for MTR-type reactors with HEU, MEU and LEU fuels
1992 · J.E. Matos, E.M. Pennington, et al. · 15
MNSR transient analyses and thermal hydraulic safety margins for HEU and LEU cores using the RELAP5-3D code
2008 · F.E. Dunn, Justin Thomas, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 9
Neutronic Analysis of the Oregon State TRIGA Reactor in Support of Conversion from HEU Fuel to LEU Fuel
2013 · M. R. Hartman, S. T. Keller, et al. · Nuclear Science and Engineering · 8
Neutronic performance of the WWR-M research reactor in Ukraine.
2002 · R. B. Pond, N. A. Hanan, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 8
Comparison of the FRM-II HEU design with an alternative LEU design
1995 · Mo, S. C., Hanan, N. A., et al. · University of North Texas Digital Library (University of North Texas) · 7
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MNSR flux performance and core lifetime analysis with HEU and LEU fuels
2008 · J.R. Liaw, J.E. Matos · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 6
Comparison of the PARET/ANL and RELAP5/MOD3 codes for the analysis of IAEA benchmark transients and the SPERT experiments
1997 · W.L. Woodruff, N. A. Hanan, et al. · Transactions of the American Nuclear Society · 6
Selected thermal properties and uranium density relations for alloy, aluminide, oxide, and silicide fuels
1992 · J.E. Matos, J.L. Snelgrove · 6
Core conversion anaylses for the Portuguese Research Reactor.
2006 · J.E. Matos, John G. Stevens, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 5
An alternative LEU design for the FRM-II
1997 · N. A. Hanan, S.C. Mo, et al. · University of North Texas Digital Library (University of North Texas) · 5
RERTR 2009 (Reduced Enrichment for Research and Test Reactors)
2010 · T. Totev, John G. Stevens, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 4
Nuclear Mass Inventory, Photon Dose Rate and Thermal Decay Heat of Spent Research Reactor Fuel Assemblies (Rev. 2)
2000 · R. Pond, USDOE National Nuclear Security Administration (NNSA), et al. · 4
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Neutronic safety parameters and transient analyses for Poland's MARIA research reactor.
1999 · M.M. Bretscher, N. A. Hanan, et al. · University of North Texas Digital Library (University of North Texas) · 4
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Neutronic Safety Parameters and Transient Analyses for Potential Leu Conversion of the Budapest Research Reactor
1999 · R. B. Pond, N. A. Hanan, et al. · University of North Texas Digital Library (University of North Texas) · 4
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Modification of the RINSC LEU core to increase fluxes for BNCT study.
2000 · S.C. Mo, R. S. Smith, et al. · University of North Texas Digital Library (University of North Texas) · 3
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Continuing investigations on electrochemical preparation of LEU targets for 99 Mo production
1993 · S.L. Marshall, L. Redey, et al. · 3
Conversion feasibility studies for the Grenoble high flux reactor
1989 · S.C. Mo, J.E. Matos · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 3
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Fuel Plate Surface Temperature in a Fully-Uncovered Fuel Assembly after a Loss-of-Coolant Accident in an MTR-Type Research Reactor
2019 · M. Kalimullah, USDOE National Nuclear Security Administration (NNSA), et al. · 2
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Reversal of OFI and CHF in Research Reactors Operating at 1 to 50 Bar. Version 1.0
2014 · Argonne National Lab. (ANL), Argonne, IL (United States), M. Kalimullah, et al. · 2
Accelerating the design and testing of LEU fuel assemblies for conversion of Russian-designed research reactors outside Russia
2003 · J.E. Matos · 2
Methods and Codes for Neutronic Calculations of the Maria Research Reactor
2002 · Krzysztof Andrzejewski, T. Kulikowska, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 2
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Beryllium poisoning in the MARIA reactor.
2001 · Krzysztof Andrzejewski, T. Kulikowska, et al. · University of North Texas Digital Library (University of North Texas) · 2
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Photon dose rates from spent fuel assemblies with relation to self- protection
1995 · Pond, R.B., Matos, J.E. · University of North Texas Digital Library (University of North Texas) · 2
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Works count: 79
Citation count: 183
H-index: 7
I10-index: 3
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