Transient Reactor Test Facility

Developing robust, safer and higher performing nuclear fuel designs

Enabling the Future of Nuclear Fuels and Reactors

The world’s most dynamic and flexible transient test reactor is available for research and demonstration activities. The Transient Reactor Test (TREAT) Facility provides a transformational research platform that links science and engineering capabilities for the advancement of fundamental science and nuclear technology. TREAT will directly couple the response of fuel and fissile-material systems to complex environments experienced under a variety of operational and off-normal transient events anticipated in nuclear reactors. From scientific discovery to technology development and deployment, TREAT will enable the advancement of nuclear fuel science and engineering required to optimize operation of the existing light water reactor fleet, as well as advanced reactors of the future.

TREAT’s Unique Design Enables Real-Time Nuclear Testing

TREAT is a highly capable test reactor; its unique design offers real-time monitoring of the fuel or materials behavior under postulated reactor accident conditions. This allows scientists to determine the appropriate safe limits for the fuels and materials in nuclear power reactors. TREAT’s simple, self-limiting, air-cooled design can safely accommodate multi-pin test assemblies, fostering the study of fuel melting, metal-liquid reactions, and overheated fuel and coolant interactions, as well as the transient behavior of fuels for high-temperature system applications. It also allows for the detailed monitoring of the specimens during a test via the hodoscope, a system that detects fast neutrons and enables real-time evaluation of the fuel behavior within a test sample.

TREAT Fact Sheet

TREAT Envisions Changing the World's Energy Future

At the Transient Reactor Test Facility (TREAT), we are driven by a bold vision to advance nuclear energy through innovation, precision, and purpose. Our approach reflects a deep commitment to operational excellence and scientific rigor as we support the safe development and deployment of advanced reactor technologies.

Mission

Provide state-of-the-art transient irradiation capabilities and apply expertise to the startup and operation of advanced reactors.

Values

We will accomplish the TREAT mission through safe and error-free execution, valuing operational excellence, technical rigor, and mastery of requirements.

Video Highlights

Step inside the world of TREAT through a dynamic video series that brings transient testing to life. These short features highlight the people, purpose, and progress behind one of INL’s most unique and impactful research capabilities.

Playlist

6 Videos

The History of TREAT

Discover the origins, key milestones, and lasting impact of the TREAT facility, along with the progress and current status of its successful restart efforts.

View the Timeline

TREAT In the News

TREAT’s work continues to make headlines for its role in advancing nuclear safety, innovation, and energy resilience. This collection of news stories highlights how TREAT’s capabilities and collaborations are shaping the future of reactor testing and contributing to solutions that matter worldwide.

U.S. and Japan Perform First Fast Reactor Fuel Safety Test of 21st Century

U.S. Department of Energy

Idaho National Laboratory (INL) conducted the world’s first safety test on a high burnup fast reactor fuel in more than 20 years at its Transient Reactor Test (TREAT) facility.

Read More

TREAT gets a TWIST

American Nuclear Society

Researchers at Idaho National Laboratory have a new experimental tool to study nuclear fuel under simulated loss of coolant accident (LOCA) conditions in INL’s Transient Reactor Test (TREAT) Facility. 

Read More

U.S. Department of Energy Restores Key Safety Test for Nuclear Fuel

U.S. Department of Energy

Idaho National Laboratory performs new experiment that shows what happens to nuclear fuel when there is a loss of coolant accident.

Read More

THOR puts fast reactor fuel to the test in U.S.-Japan TREAT collaboration

American Nuclear Society

Researchers at Idaho National Laboratory have completed initial testing on a newly developed fuel test capsule that is expected to provide crucial performance data for sodium-cooled fast reactors. 

Read More

U.S. and Japan Team Up for World’s First Safety Tests on Fast Reactor Fuels in 20 Years

U.S. Department of Energy

New experiment device will be used to perform the world’s first transient tests on fast reactor fuels in more than two decades.

Read More

A Critical Milestone Success

Idaho National Laboratory

INL’s TREAT reactor successfully completes first fueled experiment.

Read More

U.S. Test Reactor Resumes Operations

Idaho National Laboratory

A test reactor at the U.S. Department of Energy’s Idaho National Laboratory was restarted yesterday after more than 20 years on standby.

Read More

How Testing Works

  • TREAT Reactor Descriptions
    (see sections 2.1 — 2.3)
  • TREAT Experiment Configurations
    (see sections 4.1 — 4.5)
  • Beamline Measurements and In-Pile Instrumentation
    (see sections 5.1 — 5.2)
  • Available Support Services, Equipment, and Specialized Facilities
    (see sections 6.1 — 6.4)
View TREAT User Guide
Download PDF

Transient Testing Publications

Explore a curated collection of publications that showcase the groundbreaking research conducted at the Transient Reactor Test (TREAT) Facility. These works highlight the scientific advancements, experimental insights, and collaborative efforts that support transient testing and fuel behavior analysis under extreme conditions. This archive reflects the depth and impact of TREAT’s contributions to nuclear safety and innovation.

YearReferenceLink
2022Jason Schulthess, David Kamerman, Alexander Winston, Alex Pomo, Tammy Trowbridge, Xiaofei Pu, Nicolas Woolstenhulme, Devin Imholte, Colby Jensen, Daniel Wachs, Post-transient examination of performance of uranium silicide fuel and silicon-carbide composite cladding under reactivity-initiated accident conditions, Journal of Nuclear Materials, Volume 560, 2022. Publication
2021Nicolas Woolstenhulme, Colby Jensen, Charles Folsom, Robert Armstrong, Junsoo Yoo, Daniel Wachs, Thermal-hydraulic and Engineering Evaluations of New LOCA Testing Methods in TREAT, Nuclear Technology, Volume 207, 2021.Publication
2020Nicolas Woolstenhulme, Austin Fleming, Tommy Holschuh, Colby Jensen, David Kamerman, and Dan Wachs, Core-to-Specimen Energy Coupling Results of the First Modern Fueled Experiments in TREAT, Annals of Nuclear Energy, Volume 140, 2020.Publication
2020Richard Hernandez, Charles P. Folsom, Nicolas E. Woolstenhulme, Colby B. Jensen, John D. Bess, Jacob P. Gorton, Nicholas R. Brown, Review of pool boiling critical heat flux (CHF) and heater rod design for CHF experiments in TREAT, Progress in Nuclear Energy, Volume 123, 2020.Publication
2019Nicolas Woolstenhulme, Clint Baker, Colby Jensen, Daniel Chapman, Devin Imholte, Nate Oldham, Connie Hill, and Spencer Snow, Development of Irradiation Test Devices for Transient Testing, Nuclear Technology, Volume 205, 2019. Publication
2019Thomas Holschuh, Nicolas Woolstenhulme, Benjamin Baker, John Bess, Cliff Davis & James Parry, Transient Reactor Test Facility Advanced Transient Shapes, Nuclear Technology Volume 205, 2019.Publication
2019John D. Bess, Nicolas E. Woolstenhulme, Colby B. Jensen, James R. Parry, Connie M. Hill, Nuclear Characterization of a General-Purpose Instrumentation and Materials Testing Location in TREAT, Annals of Nuclear Energy, Volume 124, 2019.Publication
2019John D. Bess, Nicolas E. Woolstenhulme, Cliff B. Davis, Louis M. Dusanter, Charles P. Folsom, James R. Parry, Tate H. Shorthill, and Haihua Zhao, Narrowing Transient Testing Pulse Widths to Enhance LWR RIA Experiment Design in the TREAT Facility, Annals of Nuclear Energy, Volume 124, 2019.Publication
2026Khan, S. A., Schulthess, J. L., Burns, J., Pu, X., Woolstenhulme, N., Charit, I., & O’Brien, R. (2026). Microscopic analysis of irradiated UN–Mo–W for space nuclear propulsion. Nuclear Engineering and Design, 446(Part A), 114546.Publication
2026Chichester, D. L., Johnson, J. T., Hix, J. D., Burggraf, J. S., Ocampo Giraldo, L. A., Thompson, S. J., & Holschuh, T. V. (2025). Expansion of the fast neutron hodoscope at TREAT to support fuel safety experiments. Progress in Nuclear Science and Technology, 8, 127-130.Publication
2025Evans, J. A., Taylor, C. N., Wagner, A. R., Sweet, R. T., Lange, T. L., & Woolstenhulme, N. E. (2025). Sensitivity study of hydrogen Soret transport in yttrium hydride-based nuclear fuel. Nuclear Engineering and Design, 438, 114030.Publication
2025P. A. Ferney, B. A. Baker, M. D. DeHart, SPARTA: A flux adjustment methodology to interpret complex experiments, Annals of Nuclear Energy, 223, December 2025,Publication
2025Khan, S. A., Schulthess, J. L., Charit, I., Craft, A., Chuirazzi, W., Burns, J., Frazer, D., Woolstenhulme, N., & O'Brien, R. (2025). Post-irradiation examination of UN-Mo-W fuels for space nuclear propulsion. Journal of Nuclear Materials, 604, 155476.Publication
2025Mo, K., Oaks, A., Miao, Y., Mei, Z.-g., Lee, S. K., Schulthess, J. L., & Porter, D. L. (2025, June 15). Recent metallic fuel data recovery in FIPD [Conference presentation].Publication
2025Probert, A. R., Schulthess, J. L., Jensen, C. B., Aitkaliyeva, A., Capriotti, L., & Swearingen, A. L. (2025, June 19). Assessing high burnup U-19Pu-10Zr fuel performance against historical and modeled behavior [Conference presentation]. Publication
2025Probert, A. R., Jensen, C. B., & Schulthess, J. L. (2025, May). Pre-transient characterization of MLOF-1 test pin [Conference presentation].Publication
2025Probert, A., Swearingen, A., Schulthess, J., Capriotti, L., Jensen, C., & Aitkaliyeva, A. (2025). Comparative post-irradiation examination of high burnup U-19Pu-10Zr: Assessing steady-state irradiation behavior against historical and modeled fuel performance. Journal of Nuclear Materials, 610, 155782.Publication
2025Probert, Allison Roberts, Schulthess, Jason L, Capriotti, Luca, & Aitkaliyeva, Assel (2025). Examining Constituent Redistribution in U-19Pu-10Zr Fuel as it Evolves with Local Burnup.Publication
2025Prussack, B., Jentz, I., Moreira, T. A., Pagenkopf, E., Woolstenhulme, N., Nellis, G., & Anderson, M. (2025). Local heat transfer measurement in a volumetrically heated TPMS lattice using distributed optical fiber thermal sensing. Applied Thermal Engineering, 269, 126101.Publication
2025Woolstenhulme, N., Bascom, A., Worrall, M. et al. Perspectives on Tailoring Neutron Energy Spectra in Material Test Reactors. JOM 77, 1354–1366 (2025).Publication
2024Anderson, Klint Stephens, Kahn III, Jerry Anthony, Jensen, Colby B, Schulthess, Jason L, Fleming, Austin D, Petersen, Philip G, Argyle, Jordan Michael, & Fife, Cindy (2024). Design of a Loss of Coolant Blowdown Capsule for Remote Assembly with High Burnup Fuel.Publication
2024Chichester, D., Johnson, J., Hix, J., Burggraf, J., Ocampo Giraldo, L., Thompson, S., & Holschuh, T. (2024, October 6-10). Expansion of the Fast Neutron Hodoscope at TREAT to Support Fuel Safety Experiments. Paper presented at GLOBAL 2024, Tokyo, Japan.
2024Ferney, P., Holschuh, T., Chipman, A., & Jensen, C. (2024, October 20-24). Preliminary Analysis of TREAT free-field experiments using OpenMC. Paper presented at the Joint International Conference on Supercomputing in Nuclear Applications and Monte Carlo, Paris, France.Publication
2024Holschuh, T., Quist, T., & Chichester, D. L. (2024). Advanced dosimetry strategies for reactor and fusion neutron energies. Proceedings of the Pacific Basin Nuclear Conference, Idaho Falls, ID, 2-10 October, 339.Publication
2024Martin, N., Bascom, A., Brookman, J., & Woolstenhulme, N. (2024). Conceptual design of a thermal-to-14-MeV neutron conversion device for use in the advanced test reactor. Nuclear Science and Engineering, 1-19.Publication
2024Jaradat, M. K. M., Schunert, S., Gleicher, F. N., Labouré, V. M., & DeHart, M. D. (2024). Forward and inverse predictive transient models of TREAT using surrogate reactivity models. Annals of Nuclear Energy, 201, 110449.Publication
2024Jaradat, M. K. M., Schunert, S., Gleicher, F. N., & DeHart, M. D. (2024, April). Prediction of the TREAT facility power and temperature of Sirius-2c nuclear propulsion fuel experiment. In Proceedings of the International Conference on the Physics of Reactors (PHYSOR 2024), San Francisco, California.Publication
2024Jensen, C., Woolstenhulme, N., Schulthess, J., Kamerman, D., & Wachs, D. (2024). Fuel Safety Testing for Modern Fuel Research Programs at TREAT. 492. Abstract from 2024 Annual Conference on Transactions of the American Nuclear Society, ANS 2024, Las Vegas, United States.Publication
2024Kamerman, David W, Cappia, Fabiola, Jensen, Colby B, Stockwell, Jake Alan, Schulthess, Jason L, Colldeweih, Aaron William, & Wachs, Daniel M (2024). Fuel Performance Studies at Idaho National Laboratory Making Use of the Byron Fuel Shipment.Publication
2024Mo, K., Oaks, A., Lee, S., Yacout, A. M., & Schulthess, J. (2024). Quality Assurance of the Irradiated EBR-II Metallic Fuels Data.Publication
2024Mo, Kun, Oaks, Aaron, Miao, Yinbin, Zhang, Dandan, Porter, Douglas L, Yacout, Abdellatif, & Schulthess, Jason L (2024). Advances in Metallic Fuel Database Development and Data Qualification.Publication
2024Probert, Allison, Schulthess, Jason L, Capriotti, Luca, Hisle, Ethan Jacob, Wright, Karen E, Adkins, Cynthia A, Sevart, Mary, & Aitkaliyeva, Assel (2024). Thermal Conductivity Degradation in High Burnup U-Pu-Zr Fuel.Publication
2024Probert, Allison Roberts, et al. Element Redistribution in Irradiation Metallic Fuel from the Experimental Breeder Reactor-II (EBR-II), Aug. 2024.Publication
2024Probert, Allison, et al. Pre-Transient Characterization of Historic EBR-II Pins for Transient Testing, Jun. 2024.Publication
2024Prussack, B., Jentz, I., Moreira, T. A., Woolstenhulme, N., Jesse, C., Nellis, G., & Anderson, M. (2024). Thermal and hydraulic performance of volumetrically heated triply periodic minimal surface heaters. Applied Thermal Engineering, 123291.Publication
2024Schulthess, Jason L, Jensen, Colby B, Ozawa, Takayuki, Hirooka, Shun, Kato, Masato, Anderson, Klint Stephens, Mihelish, Matthew Phillip, Fleming, Austin D, Chipman, Andrew S, & Wachs, Daniel M (2024). Non-destructive Post-Transient Examination Results of the MOXTOP-1 Experiment.Publication
2024Schulthess, Jason L, Jensen, Colby B, Probert, Allison Roberts, Chuirazzi, William C, Craft, Aaron E, Anderson, Klint Stephens, Mihelish, Matthew Phillip, Fleming, Austin D, Chipman, Andrew S, Wachs, Daniel M, Chichester, David L, & Ocampo Giraldo, Luis A (2024). Resumption of SFR Overpower Testing and Post-Transient Examination of the THOR-C-2 Irradiation Test.Publication
2024Schulthess, Jason L., Folsom, Charles P., & Kamerman, David W. (2024). Investigation of Degradation Mechanisms of Cr-coated Zirconium Alloy Cladding in Reactivity-Initiated Accident.Publication
2024Woolstenhulme, N., Evans, J., Chipman, A., & Armstrong, R. (2024). Nuclear fuels for transient test reactors. Annals of Nuclear Energy, 204, 110519.Publication
2024Woolstenhulme, N. E., Robinson, A. B., Nielsen, J. W., Choi, Y. J., Johnson, T. A., Yim, J. S., Tahk, Y. W., & Park, J. M. (2024). Irradiation performance of a U-7Mo in Al-Si matrix dispersion full-size fuel plate assembly. Nuclear Engineering and Design, 416, 112761.Publication
2024Worrall, M., Woolstenhulme, N., Downey, C., Jesse, C., Murdock, C., & Tippet, M. (2024). Fast neutron irradiation capability in existing thermal test reactors. Annals of Nuclear Energy, 207, 110731.Publication
2024Xu, F., Yao, T., Xu, P., Schulthess, J. L., Matos, M. D., II, Gonderman, S., Gazza, J., Kane, J. J., & Cordes, N. L. (2024). Multi-Scale Characterization of Porosity and Cracks in Silicon Carbide Cladding after Transient Reactor Test Facility Irradiation. Energies, 17(1), 197.Publication
2023Bess, J. D., Chipman, A. S., Pope, C. L., Jensen, C. B., Ozawa, T., Hirooka, S., Kato, M. (2023). EBR-II MOX Fuel Characterization for ARES Phase I Testing, Nuclear Science and Engineering, 197, 1845-1872.Publication
2023Folsom, C. P., Schulthess, J. L., Kamerman, D. W., Hansen, R. S., Woolstenhulme, N. E., Jensen, C. B., Astle, L. A., Ocampo Giraldo, L., Fleming, A., & Wachs, D. M. (2023). Resumption of water capsule reactivity-initiated accident testing at TREAT. Nuclear Engineering and Design, 413, 112509.Publication
2023Gleicher, F. N., Schunert, S., DeHart, M. D., & Jaradat, M. K. M. (2023, May 8-12). Thermal Analysis of the SIRIUS3 Nuclear Propulsion Fuel Calibration Experiment. Paper presented at Nuclear and Emerging Technologies for Space (NETS 2023), Idaho Falls, ID.Publication
2023Hill, C. M., Folsom, C. P., Fleming, A. D., Armstrong, R. J., Woolstenhulme, N. E., Fishler, J. D., Bess, J. D., Hernandez, O. R., Brown, N. R., Jensen, C. B. (2023). A Non-Fueled Nuclear-Heated Rod for In-Pile Transient Boiling Studies, Nuclear Engineering Design, 414:112508.Publication
2023Holschuh, T., Watson, S., Hix, J., Giraud, K., & Chichester, D. (2023, May 6-10). Reactor Dosimetry at the Transient Reactor Test (TREAT) Facility. Paper presented at the International Symposium on Reactor Dosimetry, Lausanne, Switzerland.
2023Jensen, C., Anderson, K., Armstrong, R., Fleming, A., Mihelish , M., Fielding, R., Woolstenhulme, N., Schulthess, J., Ocampo Giraldo, L., Medvedev, P., & Wachs, D. (2023). Integral Performance of Advanced Metallic Fuel During Severe Transient Overpower. Abstract from Materials in Nuclear Energy Systems (MiNES 2023), New Orleans, Louisiana, United States.Publication
2023Kilby, S., Fletcher, J., Avachat, A., Jin, Z., Imholte, D., Woolstenhulme, N., Lee, H. K., & Graham, J. (2023). Multi-modal tomographic imaging system for poolside characterization of nuclear test fuels: Design considerations and studies. Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, 1045, 167553.Publication
2023Martin, N., Seo, S., Balderrama Prieto, S., Jesse, C., & Woolstenhulme, N. (2023). Reactor physics characterization of triply periodic minimal surface-based nuclear fuel lattices. Progress in Nuclear Energy, 165, 104895.Publication
2023McDeavitt, S. M., Wootan, D., Kimber, M., Vierow Kirkland, K., Ortega, L. H., Perez-Nunez, D., Tsvetkov, P., Hearne, J., Weiss, A., Drera, S., & Woolstenhulme, N. E. (2023). Concept descriptions for the VTR rabbit system and driver fuel test assemblies. Nuclear Science and Engineering, 197(11), 2840-2852.Publication
2023Probert, Allison Roberts, Capriotti, Luca, & Schulthess, Jason L. (2023). Characterization of Mk-IV and EBR-II X441A Metallic Fuel Pins for the THOR-C-2 and THOR-M-TOP-1 Experiments: Results from Post-Transient Neutron Tomography of THOR-C-2 Capsule and Pre-transient Non-Destructive and Destructive Examination of DP 36 and DP 40 (Rev.1).Publication
2023Pu, X., Schulthess, Jason L., Chuirazzi, William C., Kancharla, Rahul Reddy, Winston, Alexander J., Cordes, N., & Cetiner, N. (2023). Low-Power Nuclear Heating Tests of UN Fuel Particles in Hydrogen Environment for Nuclear Thermal Propulsion.Publication
2023Schulthess, J., Pu, X., Petersen, P., Burns, J., Jerred, N., Fleming, A., Craft, A., Chuirazzi, W., Woolstenhulme, N., & O'Brien, R. (2023). Post-irradiation examination of the Sirius-1 nuclear thermal propulsion fuel test. Acta Astronautica, 212, 187-197.Publication
2023Schulthess, J. L., Spencer, B. W., Petersen, P. G., Woolstenhulme, N. E., Ban, D., Frazer, D., Sudderth, L., Hamilton, S., Jewell, J. K., & Mariani, R. D. (2023). Experimental results of conductive inserts to reduce nuclear fuel temperature during nuclear volumetric heating. Journal of Nuclear Materials, 574, 154176.Publication
2023Schulthess, Jason L (2023). Neutron Imaging of Transient Irradiated Nuclear Fuels.Publication
2023Spencer, B., Woolstenhulme, N. E., Schulthess, J. L., & Fleming, A. D. (2023). Research Objectives and Findings from the DRIFT Experiments. Transactions of the American Nuclear Society, 128, 188-189.Publication
2023Woolstenhulme, N., Chapman, D., Cordes, N., Fleming, A., Hill, C., Jensen, C., Schulthess, J., Ramirez, M., Linton, K., Schappel, D., & Vasudevamurthy, G. (2023). TREAT testing of additively manufactured SiC canisters loaded with high-density TRISO fuel for the Transformational Challenge Reactor project. Journal of Nuclear Materials, 575, 154204.Publication
2023Xu, F., Kane, J. J., Xu, P., Schulthess, J. L., Gonderman, S., & Cordesa, N. L. (2023). Advanced analytics on 3D X-ray tomography of irradiated silicon carbide claddings. arXiv.Publication
2022Argyle, J. M., Schulthess, J. L., Yarrington, J. D., Turner, C. G., Parker, S. H., Stanek, J. D., & Christensen, C. L. (2022). Experiment Assembly and Testing in Hot Cell in Support of Advanced Fuels Irradiation Testing.Publication
2022Bess, J. D., Pope, C. L., Chipman, A. S., Jensen, C. B., (2022). Nuclide Inventory Characterization of EBR-II MOX Fuel Test Pins, PHYSOR 2022, Pittsburgh, PA, May 15-20.Publication
2022Chuirazzi, W., Kane, J., Craft, A., et al. (2022). Image fusion for neutron tomography of nuclear fuel. Journal of Radioanalytical and Nuclear Chemistry, 331, 5223–5229.Publication
2022Curnutt, B., Woolstenhulme, N., Nielsen, J., Oldham, N., Weaver, K., & Jensen, C. (2022). A neutronics investigation simulating fast reactor environments in the thermal-spectrum advanced test reactor. Nuclear Engineering and Design, 387, 111623.Publication
2022Epiney, A. S., Bess, J. D., Woolstenhulme, N. E. (2022). Big BUSTER Testing Environment in TREAT: Preliminary Thermal-Hydraulics for the Graphite Filler Assemblies, ATH’22, CA, June 12-16.Publication
2022Folsom, C. P., Armstrong, R. J., Woolstenhulme, N. E., Fleming, A. D., Hill, C. M., Jensen, C. B., & Wachs, D. M. (2022). Design of separate-effects in-pile transient boiling experiments at the TREAT Facility. Nuclear Engineering and Design, 397, 111919.Publication
2022Goldner, F., McCaughey, W., Wachs, D., Kamerman, D., Jensen, C., Woolstenhulme, N., Cappia, F., Schulthess, J., Medvedev, P., Nelson, A., Capps, N., Linton, K., Harp, J., Massey, C., Saleh, T., Eftink, B., & White, J. (2022). THE U.S. ACCIDENT TOLERANT FUELS PROGRAM - Transforming the Future of LWR Fuels. In Proceedings of TopFuel 2022 Light Water Reactor Fuel Performance Conference (pp. 90-97). (Proceedings of TopFuel 2022 Light Water Reactor Fuel Performance Conference). American Nuclear Society.Publication
2022Huynh, T., Mehta, A., Graydon, K., Woo, J., Park, S., Hyer, H., Zhou, L., Imholte, D. D., Woolstenhulme, N. E., Wachs, D. M., & Sohn, Y. (2022). Microstructural development in Inconel 718 nickel-based superalloy additively manufactured by laser powder bed fusion. Metallography, Microstructure, and Analysis, 11, 88-107.Publication
2022Jin, Z., Kilby, S., Avachat, A., Kanies, B., Woolstenhulme, N., Lee, H. K., & Graham, J. (2022). Accelerated radiation transport modeling techniques for pencil beam computed tomography using gamma rays. Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, 1039, 167165.Publication
2022Jing, T., Schunert, S., Labouré, V. M., DeHart, M. D., Lin, C. S., & Ortensi, J. (2022). Multiphysics Simulation of the NASA SIRIUS-CAL Fuel Experiment in the Transient Test Reactor Using Griffin. Energies, 15(17), 6181.Publication
2022Ocampo Giraldo, L. A., Holschuh, T. V., Thompson, S. J., Hix, J. D., Johnson, J. T., & Chichester, D. L. (2022). Design and validation of a gamma-ray scanning system for measuring irradiated nuclear fuel. Journal of Radioanalytical and Nuclear Chemistry, 331, 4919-4927.Publication
2022Ocampo Giraldo, L., Holschuh, T., Thompson, S., Hix, J., Johnson, J., & Chichester, D. (2022, April 6-10). Design and Validation of a Gamma-Ray Scanning System for Measuring Irradiated Nuclear Fuel. Paper presented at Methods and Applications of Radioanalytical Chemistry, Kona, HI.Publication
2022Paaren, K. M., Boutros, C., Armstrong, R. J., Medvedev, P. G., Woolstenhulme, N. E., & Jensen, C. (2022). BISON automation to predict transient power history based off prescribed cladding temperature. Nuclear Engineering and Design, 389, 111665.Publication
2022Schulthess, J. L., Spencer, B. W., Petersen, P. G., Woolstenhulme, N. E., Hamilton, S. R., Sudderth, L. K., & Jewell, J. K. (2022). Cracking in first ramp to power of standard versus high thermal conductivity UO2 pellets via internal nuclear heating.Publication
2022Schulthess, J. L., Kamerman, D. W., Woolstenhulme, N. E., Jensen, C. B., Emerson Astle, L. A., Armstrong, R. J., Wachs, D. M., Petersen, P. G., Hansen, R. S., & Folsom, C. P. (2022). Post-Transient Examination Results of RIA Commissioning Tests at the Transient Reactor Test Facility.Publication
2022Schulthess, J. L., Petersen, P. G., Pu, X., Burns, J., Jerred, N. D., Fleming, A. D., Craft, A. E., Chuirazzi, W. C., Woolstenhulme, N. E., & O'Brien, R. C. (2022). Sirius Irradiation Experiments and Post-Irradiation Examinations for Nuclear Thermal Propulsion.Publication
2022Schulthess, J., Kamerman, D., Winston, A., Pomo, A., Trowbridge, T., Pu, X., Woolstenhulme, N., Imholte, D., Jensen, C., & Wachs, D. (2022). Post-transient examination of performance of uranium silicide fuel and silicon-carbide composite cladding under reactivity-initiated accident conditions. Journal of Nuclear Materials, 560, 153520.Publication
2022Spencer, B. W., Woolstenhulme, N. E., Schulthess, J. L., Fleming, A. D., Astle, L. A., Imholte, D. D., Hill, C. M., Parry, J. R., Chapman, D. B., Folsom, C. P., Ban, D., Ramirez, M. R., Woolum, C. T., Yeh, J.-Y., Dunzik-Gougar, M. L., Jensen, C. B., & Wachs, D. M. (2022). Dry in-pile fracture test (DRIFT) for separate-effects validation of ceramic fuel fracture models. Journal of Nuclear Materials, 568, 153816.Publication
2022Woolstenhulme, N. (2022). The Transient Reactor Test Facility In Nuclear Reactors - Spacecraft Propulsion, Research Reactors, and Reactor Analysis Topics. IntechOpen.Publication
2022Yarrington, J. D., Schulthess, J. L., Parker, S. H., Argyle, J. M., Turner, C. G., Stanek, J. D., & Christensen, C. L. (2022). Advanced autonomous welding for refabrication and follow-on testing of previously irradiated nuclear fuel. Nuclear Technology, 209(2), 127–143.Publication
2021Bess, J. D. (2021). Neutronics Characterization of EBR-II X462/X462A Test Fuel Pins UW02009, UW02011, and UW06024, ECAR-5391, Idaho National Laboratory, March.
2021Bess, J. D. (2021). Reactor Physics Analyses of Big-BUSTER and Filler Assemblies in TREAT, ECAR-5360, Idaho National Laboratory, March.
2021Bess, J. D. (2021). Utility of EBR-II Benchmark Model to Enable Fuel Pin Reactor Physics Characterization, ECAR-5374, Idaho National Laboratory, February.
2021Weaver, K., Woolstenhulme, N., Bess, J., Epiney, A., Johnson, J. (2021). Irradiation Test Plan for eVinci Microreactor, INL/LTD-21-61283, Idaho National Laboratory, February.
2021Bess, J. D., Woolstenhulme, N. E., Ramirez, M. R., Smith, W. T., Epiney, A. S. (2021). Reactor Physics Analyses of the Big-BUSTER Testing Environment in TREAT, ANS Virtual Annual Meeting, June 13-16.Publication
2021Bess, J. D., Pope, C. L., Chipman, A. S., Jensen, C. B. (2021). Utility of EBR-II Benchmark Model to Enable MOX Fuel Pin Characterization, ANS Virtual Annual Meeting, June 13-16.Publication
2021Bess, J. D., Woolstenhulme, N. E., Chapman, D. B., Epiney, A. S., Johnson, J. T., Ramirez, M. R., Smith, W. T., Weaver, K. D. (2021). Upgrading Test Vehicle Capacity to Enable Future Space and Microreactor Testing in TREAT, NETS 2021, April 26-30.
2021Capps, N., Jensen, C., Cappia, F., Harp, J., Terrani, K., Woolstenhulme, N., & Wachs, D. (2021). A critical review of high burnup fuel fragmentation, relocation, and dispersal under loss-of-coolant accident conditions. Journal of Nuclear Materials, 546, 152750.Publication
2021Folsom, C.P., Schulthess, J.L., Kamerman, D.W., Woolstenhulme, N.E., Jensen, C.B., & Wachs, D.M. (2021). Overview of the Water-Based RIA Testing in TREAT.Publication
2021Folsom, Charles P., Schulthess, Jason L., Kamerman, David W., Woolstenhulme, Nicolas E., Jensen, Colby B., Pomo, Alex N., Petersen, Philip G., & Wachs, Daniel M. (2021). Water-based Ria Testing in TREAT: Commissioning and Early Results.Publication
2021Jensen, C. B., & Woolstenhulme, N. E. (2021). Irradiation performance: Fast reactor fuels. E. Greenspan (Ed.), Encyclopedia of Nuclear Energy (pp. 392-406).Publication
2021Jensen, C. B., Imholte, D. D., Armstrong, R. J., Chapman, D. B., Chipman, A. S., Bess, J. D., Blakley, C. D., Dempsey, D., Ellis, K. D., Medvedev, P. G., Smuin, T. J., Wachs, D. M., Woolstenhulme, N. E. (2021). Final Design of the MOXTOP Experiment in TREAT, INL/LTD-21-62032, Idaho National Laboratory, March.
2021Kamerman, D., Woolstenhulme, N., Imholte, D., Fleming, A., Jensen, C., Folsom, C., Woolum, C., Tritthart, K., Schulthess, J., & Wachs, D. (2021). Transient testing of uranium silicide fuel in zircaloy and silicon carbide cladding. Annals of Nuclear Energy, 160, 108410.Publication
2021Kilby, S., Fletcher, J., Jin, Z., Avachat, A., Imholte, D., Woolstenhulme, N., Lee, H. K., & Graham, J. (2021). Comparison of a semi-analytic variance reduction technique to classical Monte Carlo variance reduction techniques for high aspect ratio pencil beam collimators for emission tomography applications. Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, 1001, 165236.Publication
2021Mahmud, A., Huynh, T., Zhou, L., Hyer, H., Mehta, A., Imholte, D. D., Woolstenhulme, N. E., Wachs, D. M., & Sohn, Y. (2021). Mechanical behavior assessment of Ti-6Al-4V ELI alloy produced by laser powder bed fusion. Metals, 11(11), 1671.Publication
2021Mehta, A., Zhou, L., Huynh, T., Park, S., Hyer, H., Song, S., Bai, Y., Imholte, D. D., Woolstenhulme, N. E., Wachs, D. M., & Sohn, Y. (2021). Additive manufacturing and mechanical properties of the dense and crack free Zr-modified aluminum alloy 6061 fabricated by the laser-powder bed fusion. Additive Manufacturing, 41, 101966.Publication
2021Ortensi, J., Baker, B. A., Johnson, M. P., Wang, Y., Labouré, V. M., Schunert, S., Gleicher, F. N., & DeHart, M. D. (2021). Validation of the Griffin application for TREAT transient modeling and simulation. Nuclear Engineering and Design, 385, 111478.Publication
2021Schulthess, Jason L., Woolum, Connor T., Palmer, Joe, Terrill, Kevin J., Michelich, Connor D., Parker, Spencer Hugh, Knight, Collin J., Jensen, Colby B., & Cole, Mark R. (2021). FY21 Progress Report for Advanced Re fabrication/Re-instrumentation Capability Development.Publication
2021Woolstenhulme, N., Jensen, C., Folsom, C., Armstrong, R., Yoo, J., & Wachs, D. (2021). Thermal-hydraulic and engineering evaluations of new LOCA testing methods in TREAT. Nuclear Technology, 207(5), 637-652.Publication
2020Bess, J. D., Woolstenhulme, N. E., Aranguren, B., Chapman, D. B., Clements, K. B., Epiney, A. S., Fleming, A. D., Johnson, J. T., Ramirez, M. R., Wachs, D. M., Weaver, K. D. (2020). Enabling Future Microreactor Testing with the NIMBLE Platform in TREAT, ANS Virtual Winter Meeting, November 15-19.Publication
2020Bess, J. D., Woolstenhulme, N. E., Parry, J. R. (2020). Neutron Damage Assessment Supporting TREAT Facility Fuel SiC Recladding, ANS Virtual Winter Meeting, November 15-19.Publication
2020Bess, J. D., Woolstenhulme, N. E. (2020). Neutronic Consideration of TREAT Facility Fuel SiC Recladding, ANS Virtual Annual Meeting, June 7-11.Publication
2020Bess, J. D., Woolstenhulme, N. E., Parry, J. R. (2020). Establishing Maximal Core Excess Reactivity Envelope for TREAT Test Vehicle Insertion, ANS Virtual Annual Meeting, June 7-11.Publication
2020Di Lemma, F. G., Liu, X., Holschuh, T. V., Folsom, C. P., Murray, D. J., Teng, F., & Jensen, C. B. (2020). Investigation of the Microstructure Evolution of Alpha Uranium after In Pile Transient. Journal of Nuclear Materials, 542, 152467.Publication
2020Epiney, A. S., Aranguren, Bess, J. D., B., Chapman, D. B., Clements, K. B., Fleming, A. D., Johnson, J. T., Ramirez, M. R., Wachs, D. M., Weaver, K. D., Woolstenhulme, N. E. (2020). NIMBLE Microreactor Testing Platform for TREAT: Preliminary Thermal-Hydraulic Considerations, ANS Virtual Winter Meeting, November 15-19.Publication
2020Hernandez, R., Folsom, C. P., Woolstenhulme, N. E., Jensen, C., Bess, J. D., Gorton, J. P., Brown, N. R. (2020). Review of Pool Boiling Critical Heat Flux (CHF) and Heater Rod Design for CHF Experiments in TREAT, Progress in Nuclear Energy, 123: 103303.Publication
2020Holschuh, T., Watson, S., & Chichester, D. (2020, February). Reactor Metrology for TREAT Experiments (INL/MIS-20-57521). Idaho National Laboratory.Publication
2020Holschuh, T., Watson, S., & Chichester, D. (2020, March). TREAT Reactor Metrology Results from CTFW-4 and CTFW-5 (INL/EXT-20-57177). Idaho National Laboratory.
2020Imholte, D. D., Woolstenhulme, N. E., Jensen, C. B., Chipman, A. S., Chapman, D. B., Bess, J. D., Blakley, C. D. Wachs, D. M. (2020). Conceptual Design of the Temperature Heat-sink Overpower Response (THOR) Module, CDR-196, Idaho National Laboratory, March.
2020Keiser, D. D., Wachs, D. M., Robinson, A. B., Williams, W. J., Lillo, M., Woolstenhulme, N. E., Moore, G. A., Jue, J.-F., & Hofman, G. L. (2020). The use of U3Si2/Al dispersion fuel for high power research reactors. Journal of Nuclear Materials, 528, 151820.Publication
2020Marcum, W., LaBrier, D., Brown, E., Yan, Y., & Woolstenhulme, N. (2020). Developing separate effects transient test experiments using an out-of-pile flowing water loop. Nuclear Technology, 206(6), 895-910.Publication
2020Ortensi, J., Wang, Y., Labouré, V., Gleicher, F. N., Schunert, S., & DeHart, M. D. (2020, March 29-April 2). Improvements to the Modeling of the TREAT Reactor and Experiments. Paper presented at PHYSOR 2020: Transition to a Scalable Nuclear Future, Cambridge, United Kingdom.Publication
2020Schulthess, J., Woolstenhulme, N., Craft, A., Kane, J., Boulton, N., Chuirazzi, W., Winston, A., Smolinski, A., Jensen, C., Kamerman, D., & Wachs, D. (2020). Non-destructive post-irradiation examination results of the first modern fueled experiments in TREAT. Journal of Nuclear Materials, 541, 152442.Publication
2020Schunert, S., Zabriskie, A. X., Schwen, D., Labouré, V. M., & DeHart, M. D. (2020). Impact of grain size on performance degradation of TREAT LEU. Annals of Nuclear Energy, 139, 107294.Publication
2020Weaver, K., Windes, W., Woolstenhulme, N., Bess, J., Johnson, J., Griffin, M., Maguire, H., Levinsky, A. (2020). Irradiation Test Plan for eVinci™ Microreactor Fuel and Core Materials, INL/LTD-20-58891, Idaho National Laboratory, July.
2020Wonders, M. A., Johnson, J. T., Watson, S. M., Chichester, D. L., & Flaska, M. (2020). Optimization and characterization of a silicon photomultiplier-based ZnS(Ag) proton recoil fast neutron detector for nuclear fuel performance monitoring at TREAT. Journal of Instrumentation, 15, P09025.Publication
2020Woolstenhulme, N., Fleming, A., Holschuh, T., Jensen, C., Kamerman, D., & Wachs, D. (2020). Core-to-Specimen Energy Coupling Results of the First Modern Fueled Experiments in TREAT. Annals of Nuclear Energy, 140, 107117.Publication
2020Woolstenhulme, N. E., Aranguren, B., Bess, J. D., Chapman, D. B., Clements, K. B., Epiney, A. S., Fleming, A. D., Johnson, J. T., Ramirez, M. R., Wachs, D. M., Weaver, K. D. (2020). Conceptual Design of the NIMBLE Test Series for Westinghouse eVinci™, INL/LTD-20-59193, Idaho National Laboratory, July.
2019Bess, J. D., Woolstenhulme, N. E., Davis, C., B., Dusanter, L. M., Folsom, C. P., Parry, J. R., Shorthill, T. H., Zhao, H. (2019). Narrowing Transient Testing Pulse Widths to Enhance LWR RIA Experiment Design in the TREAT Facility, Annals of Nuclear Energy, 124: 548-571.Publication
2019Bess, J. D., Woolstenhulme, N. E., Jensen, C. B., Parry, J. R., Hill, C. M. (2019). Nuclear Characterization of a General-Purpose Instrumentation and Materials Testing Location in TREAT, Annals of Nuclear Energy, 124: 270-294.Publication
2019Bess, J. D. (2019). Heat Generation, Activation, and Decay Heat Calculations with BUSTER, ECAR-4383, Idaho National Laboratory, February.
2019Bess, J. D., Woolstenhulme, N. E., Hill, C. M. (2019). Investigating Increased Volumetric Capacity BUSTER Test Vehicle Variants for TREAT, ANS Winter Meeting, Washington, D.C., November 17-21.Publication
2019Bess, J. D., Woolstenhulme, N. E., Jensen, C. B., Parry, J. R., & Hill, C. M. (2019). Nuclear characterization of a general-purpose instrumentation and materials testing location in TREAT. Annals of Nuclear Energy, 124, 270-294.Publication
2019Bess, J. D., Woolstenhulme, N. E., Davis, C. B., Dusanter, L. M., Folsom, C. P., Parry, J. R., Shorthill, T. H., & Zhao, H. (2019). Narrowing transient testing pulse widths to enhance LWR RIA experiment design in the TREAT facility. Annals of Nuclear Energy, 124, 548-571.Publication
2019Bess, J., Holschuh, T., & Woolstenhulme, N. (2019, June 9-13). Investigating Simply Physical Means to Reduce TREAT Core Neutron Lifetime. Paper presented at ANS 2019 Annual Meeting, Minneapolis, MN.Publication
2019Bess, J. D., Hill, C. M., Parry, J. R., Woolstenhulme, N. E., Jensen, C. B. (2019). Activation and Decay Heat Calculations Supporting MIMIC Experiment Design in TREAT, ANS Annual Meeting, Minneapolis, Minnesota, June 9-13.Publication
2019Bess, J. D., Marshall, M. A., Saenz, B. (2019). Revisiting Saxton Plutonium Project MOX Fuel Experiments as International Benchmarks, ANS Annual Meeting, Minneapolis, Minnesota, June 9-13.
2019Clements, K. B., Bess, J. D. (2019). Enhancing TREAT’s Pulsing Capabilities Using TREAT Upgrade Fuel, INL/MIS-19-55298 & INL/EXP-19-55146, Idaho National Laboratory, August.Publication
2019Hill, C. M., Woolstenhulme, N. E., Imholte, D. D., Bess, J. D. (2019). MCNP Analysis of the Aqua-SETH Experiment in TREAT, ANS Annual Meeting, Minneapolis, Minnesota, June 9-13.Publication
2019Holschuh, T., Watson, S., & Chichester, D. (2019). Metrology for Transient Reactor Characterization Using Uranium Wires. Nuclear Technology, 205(10).Publication
2019Holschuh, T., Watson, S., & Chichester, D. (2019, September). TREAT Reactor Metrology Program Status – FY2019 (INL/EXT-19-55987). Idaho National Laboratory.
2019Holschuh, T., & Wachs, D. (2019, June 9-13). Measurement of Reactor Kinetics Parameters in TREAT during Temperature Limited Transients. Paper presented at ANS 2019 Annual Meeting, Minneapolis, MN.Publication
2019Holschuh, T., Woolstenhulme, N., Baker, B., Bess, J., Davis, C., Parry, J. (2019). Transient Reactor Test Facility Advanced Transient Shapes, Nuclear Technology, 205: 1346-1353.Publication
2019Kalcheva, S., Van den Branden, G., Van Dyck, S., Van den Berghe, S., Housley, G. K., Woolstenhulme, N. E., Glagolenko, I., & Cole, J. I. (2019). Feasibility studies for simultaneous irradiation of NBSR & MITR fuel elements in the BR2 reactor. Annals of Nuclear Energy, 127, 303-318.Publication
2019Kilby, S., Jin, Z., Avachat, A., Kanies, B., Woolstenhulme, N., Lee, H. K., & Graham, J. (2019). A source biasing and variance reduction technique for Monte Carlo radiation transport modeling of emission tomography problems. Journal of Radioanalytical and Nuclear Chemistry, 320, 37-45.Publication
2019Schulthess, Jason L, Kamerman, David W, Woolstenhulme, Nicolas E, Jensen, Colby B, Folsom, Charles P, Wachs, Daniel M, Craft, Aaron E, Smolinski, Andrew T, Boulton, Nicholas M, Kane, Joshua J, Winston, Alexander J, & Chuirazzi, William C (2019). Testing Accident Tolerant Fuels in Reactivity Initiated Accident Conditions -- PIE Results.Publication
2019Wonders, M. A., Chichester, D. L., & Flaska, M. (2019). Development of a ZnS (Ag)-silicon photomultiplier fast neutron detector for the neutron hodoscope at TREAT. IEEE Nuclear Science Symposium Conference Record, Manchester, United Kingdom, Oct. 26-Nov. 2.Publication
2019Woolstenhulme, N., Baker, C., Jensen, C., Chapman, D., Imholte, D., Oldham, N., Hill, C., & Snow, S. (2019). Development of irradiation test devices for transient testing. Nuclear Technology, 205(10), 1251-1265.Publication
2019Woolstenhulme, N., Bess, J., Calderoni, P., Heidrich, B., Hurley, D., Jensen, C., Schley, R., Tsai, K. (2019). Overview of I2 Irradiation Deployment Activities in TREAT, ANS Annual Meeting, Minneapolis, Minnesota, June 9-13.Publication
2019Zabriskie, A. X., Schunert, S., Schwen, D., Ortensi, J., Baker, B. A., Wang, Y., Labouré, V. M., DeHart, M. D., & Marcum, W. R. (2019). A Coupled Multiscale Approach to TREAT LEU Feedback Modeling Using a Binary-Collision Monte-Carlo–Informed Heat Source. Nuclear Science and Engineering, 193(4), 368-387.Publication
2018Baker, B. A., Ortensi, J., & DeHart, M. D. (2018, April 22-26). Modeling of the TREAT M8 Calibration Series Measurements Using MAMMOTH. Paper presented at PHYSOR 2018: Reactor Physics Paving the Way Towards More Efficient Systems, Cancun, Mexico.Publication
2018Bess, J. D., Parry, J. R., Hill, C. M., Woolstenhulme, N. E., Jensen, C. B., McQuate, K. G. (2018). Comparison of Displacement Damage Calculations Supporting MIMIC Analysis and Design for TREAT, ANS Winter Meeting, Orlando, Florida, November 11-15.Publication
2018Bess, J. D., Dusanter, L. M., Woolstenhulme, N. E., Parry, J. R., Hill, C. M., Davis, C. B. (2018). Core Power Flattening Studies Supporting Narrowing Transient Pulse Widths in TREAT, ANS Annual Meeting, Philadelphia, PA, June 17-21.Publication
2018Goluoglu, S., & DeHart, M. D. (2018). On the Effects of Pre- and Post-Transient Rod Positions for TREAT Temperature-limited Transient Powers. Nuclear Engineering and Design, 331, 97-102.Publication
2018Holschuh, T., Watson, S., & Chichester, D. (2019, January). Metrology Results for Transient Prescription Tests in TREAT using Gamma Spectroscopy (INL/EXT-18-51647). Idaho National Laboratory.
2018Holschuh, T. V. (2018, December). Methodology for Evaluation of Irradiated Activation and Fission Wires in TREAT (INL-TEV-3579). Idaho National Laboratory.
2018Jones, W. F., Marcum, W. R., Weiss, A. W., Jensen, C. B., Hawkes, G. L., Murray, P. E., ... & Phillips, A. M. (2018). Reducing uncertainty in hydrodynamic modeling of ATR experiments via flow testing, validation, and optimization. Nuclear Technology, 201(3), 286-303.Publication
2018Latimer, G., Marcum, W. R., Howard, T. K., Jones, W., Phillips, A. M., Woolstenhulme, N., Liu, S., Weiss, A., Campbell, J., Moussaoui, M., & Jensen, C. (2018). On the flow induced vibration of an externally excited nuclear reactor experiment. Nuclear Engineering and Design, 335, 1-17.Publication
2018Mausolff, Z., DeHart, M., & Goluoglu, S. (2018). Enhanced Geometric Capabilities for the Transient Analysis Code TReX and Its Application to Simulating TREAT Experiments. Progress in Nuclear Energy, 105, 236-246.Publication
2018Wachs, D., Woolstenhulme, N., Jensen, C., Chichester, D., & Broussard, D. (2018). The Transient Reactor Test (TREAT) Facility: A new era in fuel safety research. NEA News No. 36.1.Publication
2018Weems, Z., Goluoglu, S., & DeHart, M. D. (2018). Investigations of Rod Positions for TREAT M8CAL Analyses. Journal of Nuclear Engineering and Radiation Science, 4(3), 031017-1 – 031017-7.Publication
2018Woolstenhulme, N., Baker, C., Bess, J., Chapman, D., Dempsey, D., Hill, C., Jensen, C., Snow, S., Wachs, D. (2018). A Modular Irradiation Vehicle System for High-Throughput Science-Based Testing in TREAT, Nuclear Fuels & Materials Spotlight, INL/EXT-18-51258, Idaho National Laboratory, 6, 41-46.
2018Woolstenhulme, N. E., Bess, J. D., Davis, C. B., Dusanter, L. M., Folsom, C. P., Parry, J. R., Shorthill, T. H., Zhao, H. (2018). Optimization Options for Narrowing Transient Testing Pulse Widths Necessary to Enhance LWR RIA Simulations in the TREAT Facility, PHYSOR 2018, Cancun, Mexico, April 22-26.Publication
2018Woolstenhulme, N. E., Baker, C., Bess, J., Chapman, D., Dempsey, D., Hill, C., Jensen, C., Snow, S. (2018). New Capabilities for In-Pile Separate Effects Tests in TREAT, ANS Annual Meeting, Philadelphia, PA, June 17-21.Publication
2017Bess, J. D., Hill, C. M. (2017). Neutronics Analysis of Baseline Configuration Multi-SERTTA Experiment Vehicle in TREAT, ECAR-3372, Idaho National Laboratory, February.
2017Bess, J. D., Hill, C. M., Jensen, C. B., Woolstenhulme, N. E. (2017). Analyses Supporting Design Review of TREAT Multi-SERTTA Experiment Test Vehicle, M&C 2017, Jeju, Korea, April 16-20.Publication
2017DeHart, M. D., Baker, B. A., & Ortensi, J. (2017). Interpretation of Energy Deposition Data from Historical Operation of the Transient Test Facility (TREAT). Nuclear Engineering and Design, 322, 504-521.Publication
2017DeHart, M. D., Baker, B. A., & Ortensi, J. (2017, October 29 - November 2). Assessment of Uncertainties in Energy Deposition Data for the Transient Test Facility (TREAT). Transactions of the American Nuclear Society, 117, 799-803. Washington, DC.Publication
2017Hix, J. D., Chichester, D. L., Watson, S. M., Johnson, J. T., & Thompson, S. J. (2017). The evaluation, refurbishment, and characterization of fast neutron scintillation detectors for the Transient Test Reactor Test Facility (TREAT) fuel motion monitoring system. IEEE Nuclear Science Symposium Conference Record, Atlanta, Georgia, Oct. 21-28.Publication
2017Holschuh, T. (2017, November). Primer for Reactor Pulses in the Transient Reactor Test Facility (INL/INT-17-43904). Idaho National Laboratory.
2017Smith, K., DeHart, M. D., & Goluoglu, S. (2017, June 11-15). Optimization of a Monte Carlo Model of the Transient Reactor Test Facility. Transactions of the American Nuclear Society, 116, 1021-1024. San Francisco, California.Publication
2017Sorrell, N. C., Hawari, A. I., DeHart, M. D., & Bess, J. D. (2017, June 11-15). Investigation of Treat M2 and M3 Calibration Experiments for Benchmark Analysis. Transactions of the American Nuclear Society, 116, 1225-1228. San Francisco, California.Publication
2017Vaughn, K., Mausolff, Z., Gonzalez, E., DeHart, M. D., & Goluoglu, S. (2017, June 11-15). Effects of Boron and Graphite Uncertainty in Fuel for TREAT Simulations. Transactions of the American Nuclear Society, 116, 721-723. San Francisco, California.Publication
2017Wang, C., Talbot, P. W., Schunert, S., Baker, B. A., Wang, Y., Ortensi, J., Gleicher, F. N., DeHart, M. D., & Rabiti, C. (2017, June 11-15). Surrogate Models for TREAT Transient Calculations. Transactions of the American Nuclear Society, 116, 1127-1130. San Francisco, California.Publication
2017Wang, C., Talbot, P. W., Schunert, S., Baker, B. A., Wang, Y., Ortensi, J., Gleicher, F. N., DeHart, M. D., & Rabiti, C. (2017, June 11-15). Uncertainty and Sensitivity Analysis of TREAT Transient Test #15. Transactions of the American Nuclear Society, 116, 625-628. San Francisco, California.Publication
2017Woolstenhulme, N., Baker, C., Bess, J., Chapman, D., Jensen, C., Hill, C., Wachs, D., Wilson, S. (2017). Status Report for NEET In-Pile Sensor Irradiation Capabilities at TREAT, INL/EXT-17-43274, Idaho National Laboratory.Publication
2017Woolstenhulme, N., Bess, J., Davis, C., Dusanter, L., Folsom, C., Parry, J., Shorthill, T., Zhao, H. (2017). Conceptual Report on Narrowing TREAT’s Pulse Width for Enhanced LWR RIA Simulation, INL/LTD-17-43163, Idaho National Laboratory.
2016Baker, B. A., DeHart, M. D., Ortensi, J., Wang, Y., Gleicher, F. N., & Schunert, S. (2016, January). Recommendations for TREAT Historical Data to Validate MAMMOTH (INL/EXT-16-38059). Idaho National Laboratory.
2016Bess, J. D., Hill, C. M., Parry, J. R., Woolstenhulme, N. E. (2016). Scoping Studies to Determine TREAT’s Capabilities for Testing PWR Multi-Rod Bundles, INL/INT-16-37910, Idaho National Laboratory, February.
2016Bess, J. D., Woolstenhulme, N. E., Hill, C. M., Jensen, C. B., Snow, S. D. (2016). TREAT Neutronics Analysis and Design Support, Part I: Multi-SERTTA, Top Fuel 2016, Boise, ID, September 11-15.Publication
2016Bess, J. D., Woolstenhulme, N. E., Hill, C. M., Snow, S. D. , Jensen, C. B. (2016). TREAT Neutronics Analysis and Design Support, Part II: Multi-SERTTA-CAL, Top Fuel 2016, Boise, ID, September 11-15.Publication
2016Bess, J. D., Chase, B. M., Parry, J. R. (2016). Benchmark Progress towards TREAT M8CAL Core Loading to Support Validation of TREAT Operations, PHYSOR 2016, Sun Valley, Idaho, May 1-5.Publication
2016Bess, J. D., Woolstenhulme, N. D., Hill, C. M. (2016). Neutronics Analysis Supporting Baseline Fuel-Rodlet Irradiation Design in TREAT Multi-SERTTA Vehicle, NFSM-2016, New Orleans, LA, June 12-16.Publication
2016Bess, J. D., Downar, T. (2016). IRPhEP Benchmark Process and the Current Status for TREAT, Transient Test Reactor Physics Workshop, PHYSOR 2016, Sun Valley, Idaho, May 1-5.
2016DeHart, M., Baker, B., Ortensi, J., Woolstenhulme, N., Bess, J., Jensen, C., Parry, J., Hill, T., Phoenix, W. (2016). Interdisciplinary Collaboration in Support of the Post-Standby TREAT Mission, INL/EXT-16-40100, Idaho National Laboratory.Publication
2016Hill, C. M., Woolstenhulme, N. E., Parry, J. R., Bess, J. D., Housley, G. K. (2016). TREAT Neutronics Analysis of Water-Loop Concept Accommodating LWR 9-Pin Bundle, Top Fuel 2016, Boise, ID, September 11-15.Publication
2016Hill, C. M., Bess, J. D., Woolstenhulme, N. E., Parry, J. R., Bays, S. E. (2016). MCNP Water Physics Scoping Study to Support LWR Accident Tolerant Fuel Testing in TREAT, PHYSOR 2016, Sun Valley, Idaho, May 1-5.Publication
2016Jensen, C. B., Woolstenhulme, N. E., Bess, J. D., Folsom, C. P., O’Brien, R. C., Ban, H., Wachs, D. M. (2016). Environment Modeling and Instrumentation for Pellet-Cladding Interaction Studies in TREAT, OECD/NEA Workshop: Pellet-Cladding Interaction (PCI) in Water-Cooled Reactors, Lucca, Italy, June 22-24.
2016Jensen, C. B., Davis, C. B., Folsom, C. P., Woolstenhulme, N. E., O’Brien, R. C., Bess, J. D., Ban, H., Wachs, D. M. (2016). Thermal-Hydraulic Modeling for Reactivity Insertion Accident Experiments in TREAT Multi-SERTTA, Top Fuel 2016, Boise, ID, September 11-15.
2016Johnson, J. T., Chichester, D. L., Watson, S. M., & Thompson, S. J. (2016). Optimization of a fast neutron scintillator for real-time pulse shape discrimination in the Transient Reactor Test Facility (TREAT) hodoscope. IEEE Nuclear Science Symposium Conference Record, Strasbourg, France, Oct. 31-Nov. 6.Publication
2016Mausolff, Z., DeHart, M. D., & Goluoglu, S. (2016, November 6-10). Parallel Performance of the Time Dependent Transport Code TDKENO with Applications to TREAT Simulations. Paper presented at the 2016 ANS Winter Meeting and Nuclear Technology Expo, Las Vegas, NV.Publication
2016O’Brien, R. C., Woolstenhulme, N. E., Jensen, C. B., Folsom, C. P., Bess, J. D., Wachs, D. M. (2016). Accident Tolerant Fuel Pellet-Cladding Interaction Studies Under Transient Accident Test Conditions in the TREAT Reactor, OECD/NEA Workshop on Pellet-Cladding Interaction (PCI) in Water-Cooled Reactors, Lucca, Italy, June 22-24.
2016Ortensi, J., Schunert, S., Wang, Y., Baker, B. A., Gleicher, F. N., & DeHart, M. D. (2016, November 6-10). A Neutron Streaming Problem to Test Rattlesnake Methods for TREAT. Paper presented at the 2016 ANS Winter Meeting and Nuclear Technology Expo, Las Vegas, NV.
2016Wachs, D. M., Robinson, A. B., Rice, F. J., Kraft, N. C., Taylor, S. C., Lillo, M., Woolstenhulme, N., Roth, G. A. (2016). Swelling of U-7Mo/Al-Si dispersion fuel plates under irradiation – Non-destructive analysis of the AFIP-1 fuel plates. Journal of Nuclear Materials, 476, 270-292.Publication
2016Woolstenhulme, N. E., Baker, C. C., Bess, J. D., Davis, C. B., Hill, C. M., Housley, G. K., Jensen, C. B., Jerred, N. D., O’Brien, R. C., Snow, S. D., Wachs, D. M. (2016). Capabilities Development for Transient Testing of Advanced Nuclear Fuels at TREAT, Top Fuel 2016, Boise, ID, September 11-15.Publication
2016Woolstenhulme, N. E., Bess, J. D., Davis, C. B., Housley, G. K., Jensen, C. B., O’Brien, R. C., Wachs, D. M. (2016). TREAT Irradiation Vehicle Designs, Capabilities, and Future Plans, PHYSOR 2016, Sun Valley, Idaho, May 1-5.Publication
2016Youngblood, R., Jamison, K., Coryell, B., Parga, C., Bess, J., Smith, R., van Rooyen, I. (2016). Initial Conceptual HAZOP of TREAT Fuel Element Assemblies, INL/MIS-16-37924, Idaho National Laboratory, February.
2015Alberti, A. L., Palmer, T. S., Ortensi, J., & DeHart, M. D. (2016, May 1-5). Steady State Modeling of the Minimum Critical Core of the Transient Reactor Test Facility. Paper presented at PHYSOR 2016: Unifying Theory and Experiments in the 21st Century, American Nuclear Society, Sun Valley, Idaho.Publication
2015Beasley, A., Bess, J. D., Davis, C. B., Hill, C. M., Hone, L. A., Jensen, C. B., Jerred, N. D., Navarro, J., O’Brien, R. C., Patel, V. K., Snow, S. D., Woolstenhulme, N. (2015). Preliminary Design and Safety Analysis Needs for the TREAT Static Capsule, INL/LTD-15-36929, Idaho National Laboratory, October.
2015Bess, J. D., DeHart, M. D. (2015). Baseline Assessment for TREAT Modeling and Analysis Needs, INL/EXT-15-35372, Idaho National Laboratory, October.Publication
2015Bess, J. D., Woolstenhulme, N. E., Hill, C. M., O’Brien, R. C., Bays, S. E. (2015). TREAT Multi-SERTTA Neutronics Design and Analysis Support, PHYSOR 2016, Sun Valley, Idaho, May 1-5.Publication
2015Bess, J. D., DeHart, M. D. (2015). TREAT Fuel Assembly Characterization for Modern Neutronics Validation Methods, ANS Annual Meeting, San Antonio, Texas, June 7-11.Publication
2015Chichester, D. L., Watson, S. M., Johnson, J. T., & Wachs, D. M. (2015). The TREAT fast-neutron hodoscope and plans for restoring it to operations. Transactions of the American Nuclear Society, 112, 377-380.Publication
2015DeHart, M. D. (2015, October). TREAT Modeling and Simulation Strategy (INL/EXT-15-36893). Idaho National Laboratory.Publication
2015DeHart, M. D., Mausolff, A., Goluoglu, S., Prince, Z., Ragusa, J., Haugen, C., Ellis, M., Roget, B., Smith, K. S., Alberti, A. L., & Palmer, T. S. (2015, September). NEAMS-Funded University Research in Support of TREAT Modeling and Simulation, FY15 (INL/EXT-36827). Idaho National Laboratory.Publication
2015DeHart, M. D. (2015, June 7-11). Modeling and Simulation Development in Support of the Transient Test Reactor (TREAT). Panel discussion with M. Petit, M. L. Corradini, H. Ban, D. M. Wachs, and A. C. Klein at the ANS Annual Meeting, San Antonio, Texas.
2015DeHart, M. D., Gleicher, F. N., Ortensi, J., Wang, Y., Alberti, A. L., & Palmer, T. S. (2015, November 8-12). Multi-Physics Simulation of TREAT Kinetics using MAMMOTH. Paper presented at the 2015 ANS Winter Meeting, American Nuclear Society, Washington D.C.Publication
2015Ortensi, J., DeHart, M. D., Gleicher, F. N., Wang, Y., Alberti, A. L., & Palmer, T. S. (2015, September). Full Core TREAT Kinetics Demonstration Using Rattlesnake/BISON Coupling Within MAMMOTH (INL/EXT-15-36268). Idaho National Laboratory.Publication
2015Woolstenhulme, N. E., Baker, C. C., Bess, J. D., Davis, C. B., Housley, G. K., Jensen, C. B., Snow, S. D. (2015). TREAT Experiment Vehicle Design and Future Plans, ANS Annual Meeting, San Antonio, Texas, June 7-11.Publication
2014DeHart, M. D., et al. (2014, September 28 - October 2). Studies of Potential for Conversion of the Idaho National Laboratory Transient Test Reactor (TREAT) to Low-Enrichment Fuel. Paper, presented at PHYSOR 2014, Kyoto, Japan. (INL/CON-14-31328).
2014Meyer, M. K., Gan, J., Jue, J.-F., Keiser, D. D., Perez, E., Robinson, A., Wachs, D. M., Woolstenhulme, N., Hofman, G. L., & Kim, Y. S. (2014). Irradiation performance of U-Mo monolithic fuel. Nuclear Engineering and Technology, 46(2), 169-182.Publication
2014Woolstenhulme, N. E., Bess, J. D. (2014) Scoping Calculations of the MP-1-C Irradiation Experiment, INL/LTD-33178, Idaho National Laboratory, September.
2011Keiser, D. D., Jue, J.-F., Woolstenhulme, N. E., & Ewh, A. (2011). Potential annealing treatments for tailoring the starting microstructure of low-enriched U–Mo dispersion fuels to optimize performance during irradiation. Journal of Nuclear Materials, 419(1-3), 226-234.Publication
2011Schulthess, J. L. (2011). Post Irradiation Capabilities at the Idaho National Laboratory.Publication
2011Schulthess, Jason L (2011). National Postirradiation Examination Workshop Report.Publication
2011Yao, B., Perez, E., Keiser, D. D., Jue, J.-F., Clark, C. R., Woolstenhulme, N., & Sohn, Y. (2011). Microstructure characterization of as-fabricated and 475°C annealed U–7wt.% Mo dispersion fuel in Al–Si alloy matrix. Journal of Alloys and Compounds, 509(39), 9487-9496.Publication
2015Bess, J. D., & DeHart, M. D. (2015, November 8-12). Development of a Baseline Assessment of TREAT for Modeling and Analysis Needs. Paper presented at the 2015 ANS Winter Meeting, American Nuclear Society, Washington D.C.Publication

Contact Information

Transient Testing Team

Send a Message

TREAT Partners

advanced fuels campaign logo
nsuf logo
GAIN logo
NRIC logo