Overview
Education/Academic qualification
Eng-Nuclear, Doctorate Degree
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Dive into the research topics where Padhraic Mulligan is active. These topic labels come from the works of this person. Together they form a unique fingerprint.
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An Instrumented Capsule Design to Measure Thermal Conductivity in Miniature UO2 Specimens
Gorton, J., Parker, T., Godsey, K., Cranford, D., Mulligan, P., Howard, R., Capps, N., Petrie, C. & Nelson, A., 2025, Proceedings of the TopFuel 2025: Nuclear Reactor Fuel Performance Conference. American Nuclear Society, p. 592-601 10 p. (Proceedings of the TopFuel 2025: Nuclear Reactor Fuel Performance Conference).Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review
2 Scopus citations -
Design of an Out-Of-Pile Experimental Facility to Demonstrate the Feasibility of In Situ Thermal Conductivity Measurements of Nuclear Fuels Under Irradiation
Parker, T., Gorton, J., Cooper, K., Cranford, D., Sweeney, D. C., Mulligan, P., Howard, R., Petrie, C. & Nelson, A., 2025, Proceedings of the TopFuel 2025: Nuclear Reactor Fuel Performance Conference. American Nuclear Society, p. 602-611 10 p. (Proceedings of the TopFuel 2025: Nuclear Reactor Fuel Performance Conference).Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review
1 Scopus citations -
Design Report on the MiniFuel Instrumented Test Apparatus for Understanding Radiation Effects
Gorton, J., Mulligan, P. L., Parker, T., Godsey, K., Cooper, K., Cranford, D., Sitterson, R., Wang, H., Helmreich, G., Howard, R., Ezell, N. D., Harp, J., Nelson, A., Capps, N. & Petrie, C., 2025, United StatesResearch output: Other contribution › Technical Report
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Development of an In Situ Fission Gas Release Instrument for Fuel Sample Irradiations in the High Flux Isotope Reactor
Mulligan, P. L., Gorton, J., Parker, T., Cranford, D., Ezell, N. D. B., Howard, R., Petrie, C., Godsey, K., Capps, N. & Harp, J., 2025, Proceedings of the TopFuel 2025: Nuclear Reactor Fuel Performance Conference. American Nuclear Society, p. 612-620 9 p. (Proceedings of the TopFuel 2025: Nuclear Reactor Fuel Performance Conference).Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review
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Standardization of Silicon Carbide Passive Temperature Monitors for In-Core Irradiation Experiments
Mulligan, P. L., Campbell, A. A. & Wilding, M., 2025, Proceedings of Nuclear Plant Instrumentation and Control and Human-Machine Interface Technology, NPIC and HMIT 2025. American Nuclear Society, p. 1541-1550 10 p. (Proceedings of Nuclear Plant Instrumentation and Control and Human-Machine Interface Technology, NPIC and HMIT 2025).Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review