b'PUBLICATIONS: Jensen, C., et al., High speed boiling detector based on electrical Hernandez, R., R. J. Armstrong, S. B. Seo, C. P. Folsom, C. B. Jensen,impedance measurement for advanced in-pile boiling studies, and N. R. Brown, Sensitivity analysis of in-pile CHF experimentsAmerican Nuclear Society Winter Meeting, Nov. 15-19, 2019.in the TREAT facility: Characterization of impacts of fuel system thermal properties, Annals of Nuclear Energy 165 (2022) 108645. Terrill, K., C. Jensen, C. Folsom, N. Woolstenhulme, D. Wachs, N. Smith, R. Christensen, R. Hernandez, and N. Brown, Transient Seo, S. B., R. J. Armstrong, R. Hernandez, C. P. Folsom, C. B. Jensen,boiling during RIA: Out-of-pile testing and in-pile design for and N. R. Brown, Sensitivity analysis of in-pile critical heat fluxTREAT, Top Fuel 2019.experiments in TREAT for characterization of reactivity-initiated accident power-transient effects, Annals of Nuclear Energy 161Hernandez, R., C. Folsom, N. Woolstenhulme, C. Jensen, and (2021) 108448. N. Brown, Preliminary heater rod design for transient critical heat flux experiments in TREAT. Transactions of 2019 American Hernandez, R., C. Folsom, N. Woolstenhulme, C. Jensen, J. Bess,Nuclear Society Annual Meeting, American Nuclear Society, J. Gorton, and N. Brown, Review of pool boiling critical heatJune 9-13, 2019.flux (CHF) and heater rod design for CHF experiments in TREAT, Progress in Nuclear Energy 123 (2020) 103303. Jensen, C., C. Folsom, N. Woolstenhulme, N. Smith, K. Condie, K. Terrill, and R. Christensen, Facility for Simulating Transient Boiling PRESENTATIONS: Behavior under PWR Conditions, Transactions of 2019 American Armstrong, R., et al., Results of the CHF-SERTTA in-pile transientNuclear Society Annual Meeting, American Nuclear Society, boiling experiments at TREAT, Top Fuel 2021, Oct. 24-28, 2021. June 9-13, 2019.Melgar, A., et al., Design of the mechanical seal for the sightHernandez, R., C. Folsom, N. Woolstenhulme, C. Jensen, J. window used for an advanced visualization instrument workingGorton, and N. Brown, Sensitivity studies of heater rod design for in a high-pressure, high-temperature environment, Americantransient critical heat flux experiments in TREAT, 18th International Nuclear Society Student Conference, April 810, 2021. Topical Meeting on Nuclear Reactor Thermal Hydraulics, American Armstrong, R., et al., Calculation of critical heat flux using anNuclear Society, Aug. 18-23, 2019.inverse heat transfer method to support TREAT experimentTerrill, K., R. Christensen, A. Fleming, and C. Jensen, Advanced analysis, American Society of Mechanical Engineers InternationalInstrumentation to Detect Boiling, 18th International Topical Conference on Nuclear Engineering (ICONE)-28-Power2020,Meeting on Nuclear Reactor Thermal Hydraulics, American Nuclear Aug. 4-5, 2020. Society, Aug. 18-23, 2019.Hernandez, R., et al., Incorporating axial boron gradients intoJensen, C., N. Woolstenhulme, C. Folsom, D. Kamerman, A. a heater tube experiment for pool boiling CHF testing in TREAT,Fleming, and D. Wachs, Experimental design for transient in-pile American Society of Mechanical Engineers International Conferenceboiling studies at the TREAT Facility. 18th International Topical on Nuclear Engineering (ICONE)-28-Power2020, Aug. 4-5, 2020. Meeting on Nuclear Reactor Thermal Hydraulics, American Nuclear Seo, S., et al., Optimization study for uncertainty reduction ofSociety, Aug. 18-23, 2019.in-pile CHF experiments in TREAT, American Society of Mechanical Engineers International Conference on Nuclear Engineering (ICONE)-28-Power2020, Aug. 4-5, 2020.Jensen, C., et al., Preliminary results from in-pile transient boiling experiments at the TREAT facility, American Nuclear Society Annual Meeting, June 7-11, 2020.17'