If you made any changes in Pure, your changes will be visible here soon.

Research Output 2008 2020

Filter
Conference contribution
2019

Fuel cycle performance of fast spectrum molten salt reactor designs

Rykhlevskii, A., Betzler, B. R., Worrall, A. & Huff, K., Jan 1 2019, International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019. American Nuclear Society, p. 342-353 12 p. (International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019).

Research output: Chapter in Book/Report/Conference proceedingConference contribution

Salt
Reactor
Cycle
Unit
Cell
2017

Benefits of siting a borehole repository on non-operating nuclear facility

Bae, J. W., Roy, W. & Huff, K., Jan 1 2017, ANS IHLRWM 2017 - 16th International High-Level Radioactive Waste Management Conference: Creating a Safe and Secure Energy Future for Generations to Come - Driving Toward Long-Term Storage and Disposal. American Nuclear Society, p. 876-883 8 p. (ANS IHLRWM 2017 - 16th International High-Level Radioactive Waste Management Conference: Creating a Safe and Secure Energy Future for Generations to Come - Driving Toward Long-Term Storage and Disposal).

Research output: Chapter in Book/Report/Conference proceedingConference contribution

repository
borehole
power plant
nuclear power plant
viability
2016

A sensitivity study of a coupled kinetics and thermal-hydraulics model for fluoride-salt-cooled, high-Temperature reactor (FHR) transient analysis

Wang, X., Huff, K. D., Aufiero, M., Peterson, P. F. & Fratoni, M., Jan 1 2016, International Congress on Advances in Nuclear Power Plants, ICAPP 2016. American Nuclear Society, p. 399-406 8 p. (International Congress on Advances in Nuclear Power Plants, ICAPP 2016; vol. 1).

Research output: Chapter in Book/Report/Conference proceedingConference contribution

High temperature reactors
Hydraulic models
Transient analysis
Salts
Kinetics

Coupled reactor kinetics and heat transfer model for fluoride salt-cooled high-temperature reactor transient analysis

Wang, X., Huff, K. D., Aufiero, M., Peterson, P. F. & Fratoni, M., Jan 1 2016, Student Paper Competition. American Society of Mechanical Engineers (ASME), V005T15A055. (International Conference on Nuclear Engineering, Proceedings, ICONE; vol. 5).

Research output: Chapter in Book/Report/Conference proceedingConference contribution

High temperature reactors
Transient analysis
Neutrons
Salts
Heat transfer
2014

Design of the Mark-I pebble-bed, fluoride-salt-cooled, high-temperature reactor commercial power plant

Krumwiede, D. L., Andreades, C., Choi, J. K., Cisneros, A. T., Huddar, L., Huff, K. D., Laufer, M. R., Munk, M., Scarlat, R. O., Seiffied, J. E., Zweibaum, N., Greenspan, E. & Peterson, P. F., Jan 1 2014, International Congress on Advances in Nuclear Power Plants, ICAPP 2014. American Nuclear Society, p. 413-422 10 p. (International Congress on Advances in Nuclear Power Plants, ICAPP 2014; vol. 1).

Research output: Chapter in Book/Report/Conference proceedingConference contribution

High temperature reactors
Power plants
Salts
Coolants
Computer aided design