Jordan G. Gilbert

Papers

Total Citations

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About

Jordan G. Gilbert is a nuclear engineering researcher whose work focuses on advancing the safety and efficiency of CANDU® reactor inspections. His most-cited paper, "MCNP Simulation of In-Core Dose Rates for an Offline CANDU® Reactor" (2017), addresses a critical operational challenge: the current inspection system, CIGAR, can only examine one pressure tube channel at a time, limiting maintenance throughput. By employing Monte Carlo N-Particle (MCNP) simulations to model in-core dose rates during offline conditions, Gilbert provides essential data to optimize inspection protocols and reduce worker radiation exposure. While his citation count is modest, his contributions are foundational for developing multi-channel inspection technologies, directly impacting reactor longevity and safety. Gilbert’s work exemplifies the intersection of computational modeling and practical nuclear engineering, offering a pathway to more efficient and safer CANDU® reactor maintenance. His research is particularly valuable for students and professionals seeking to understand radiation transport in reactor environments and improve operational procedures in the nuclear industry.