Comparison of experimental and simulated critical heat flux tests with various cladding alloys: Sensitivity of iron-chromium-aluminum (FeCrAl) to heat transfer coefficients and material properties
Gorton, Jacob P., Lee, Soon K., Lee, Youho, Brown, Nicholas R.
Published in Nuclear engineering and design (01.11.2019)
Published in Nuclear engineering and design (01.11.2019)
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Journal Article
Reactor performance and safety characteristics of ThN-UN fuel concepts in a PWR
Gorton, Jacob P., Collins, Benjamin S., Nelson, Andrew T., Brown, Nicholas R.
Published in Nuclear engineering and design (15.12.2019)
Published in Nuclear engineering and design (15.12.2019)
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Journal Article
Review of pool boiling critical heat flux (CHF) and heater rod design for CHF experiments in TREAT
Hernandez, Richard, Folsom, Charles P., Woolstenhulme, Nicolas E., Jensen, Colby B., Bess, John D., Gorton, Jacob P., Brown, Nicholas R.
Published in Progress in nuclear energy (New series) (01.05.2020)
Published in Progress in nuclear energy (New series) (01.05.2020)
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Journal Article
Heat transfer optimization of uo2-mo fuel using genetic algorithms
Gorton, Jacob P., McDuffee, Joel L., Snarr, Patrick L., Petrie, Christian M., Nelson, Andrew T.
Published in Nuclear engineering and design (01.03.2024)
Published in Nuclear engineering and design (01.03.2024)
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Journal Article
Reactivity-initiated accidents in two pressurized water reactor high burnup core designs
Fox, Mason A., Lindsay, Isabelle O., Gorton, Jacob P., Brown, Nicholas R.
Published in Nuclear engineering and design (15.12.2023)
Published in Nuclear engineering and design (15.12.2023)
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Journal Article
Reactivity-initiated accidents in two pressurized water reactor high burnup core designs
Fox, Mason A., Lindsay, Isabelle O., Gorton, Jacob P., Brown, Nicholas R.
Published in Nuclear engineering and design (10.11.2023)
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Published in Nuclear engineering and design (10.11.2023)
Journal Article
Surface wettability and pool boiling Critical Heat Flux of Accident Tolerant Fuel cladding-FeCrAl alloys
Ali, Amir F., Gorton, Jacob P., Brown, Nicholas R., Terrani, Kurt A., Jensen, Colby B., Lee, Youho, Blandford, Edward D.
Published in Nuclear engineering and design (01.11.2018)
Published in Nuclear engineering and design (01.11.2018)
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Journal Article
Modeling and design of a separate effects irradiation test targeting fission gas release from Cr-doped UO2
Gorton, Jacob P., Le Coq, Annabelle G., Wallen, Zane G., Petrie, Christian M., White, Joshua T., Dunwoody, John T., Mann, Shane, Capps, Nathan A., Nelson, Andrew T.
Published in Nuclear engineering and design (01.12.2024)
Published in Nuclear engineering and design (01.12.2024)
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Journal Article
Simulation of a TRISO MiniFuel irradiation experiment with data-informed uncertainty quantification
Gorton, Jacob P., Gallagher, Ryan C., Wallen, Zane G., Le Coq, Annabelle G., Helmreich, Grant W., Petrie, Christian M., Linton, Kory D., Latta, Ryan, Gerczak, Tyler J.
Published in Nuclear engineering and design (01.04.2023)
Published in Nuclear engineering and design (01.04.2023)
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Journal Article
Pre-conceptual high temperature gas cooled microreactor design utilizing two-phase composite moderators. Part II: Design space and safety characteristics
Duchnowski, Edward M., Karriem, Veronica, Skidmore, Khian, Gorton, Jacob P., Snead, Lance L., Trelewicz, Jason R., Brown, Nicholas R.
Published in Progress in nuclear energy (New series) (01.07.2022)
Published in Progress in nuclear energy (New series) (01.07.2022)
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Journal Article
Comparison of experimental and simulated critical heat flux tests with various cladding alloys: Sensitivity of iron-chromium-aluminum (FeCrAl) to heat transfer coefficients and material properties
Gorton, Jacob P., Lee, Soon K., Lee, Youho, Brown, Nicholas R.
Published in Nuclear engineering and design (23.08.2019)
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Published in Nuclear engineering and design (23.08.2019)
Journal Article
Impact of control blade insertion on the deformation behavior of SiC-SiC channel boxes in BWRs
Singh, Gyanender, Gorton, Jacob P., Schappel, Danny, Collins, Benjamin S., Kato, Yutai, Brown, Nicholas R., Wirth, Brian D.
Published in Nuclear engineering and design (06.04.2020)
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Published in Nuclear engineering and design (06.04.2020)
Journal Article