Michael Hone Email & Phone Number

Prospect, Pa

Performed Nuclear Criticality Safety evaluations and SCALE calculations supporting the TRISO-X fuel plant design. This includes evaluations for high uranium density containers (containing High Assay Low Enriched Uranium), and the waste and recovery operations planned for the TRISO-X plant. Also performed reviews of NCS evaluations performed by other members of the NCS team.

Pittsburgh, Pennsylvania, United States

Started as a Sr. Engineer A performing core design for Westinghouse 4-loop plants, including Seabrook Station and eventually Indian Point. Developed nuclear design models and loading patterns and calculated safety and operating nuclear parameters for multiple 4-loop Westinghouse plants. Also developed models and loading patterns for other Westinghouse and non-Westinghouse plant types in support of fuel proposals. Was then assigned to the New Reactor Technology group as a nuclear designer for AP1000 PWRs. I assisted with the qualification of a new pin power reconstruction methodology for the ANC code using MCNP code benchmark cases, and also performed a criticality analysis of the new fuel storage area using the SCALE code. I also developed the methodology used for directly monitoring shutdown margin in AP1000 plants. I performed the nuclear design of the AP1000 gray control rodlets, including absorber material selection, evaluating the effect of gray rods on operations and fuel performance, and obtaining patents for the new gray control rod design. I also finished development of the Mechanical Shim (MSHIM) Operation and Control Strategy and the nuclear design analytical methods supporting that type of operation. Co-authored topical reports on the gray control rodlet design, MSHIM Operation and Control Strategy, and the AP1000 Core Reference Report. Provided training on multiple AP1000 topics to both Chinese and US customers. I was promoted to Fellow Engineer in February 2015. I developed and implemented a new method for determining more accurate fits of transient limit functions in the Westinghouse VENUS code. I was also the licensed methodology expert for Westinghouse power distribution control methods and their associated technical specifications, and was recognized as an expert on the 3D FAC methods used for AP1000 plants. Won two company-level George Westinghouse Signature Awards for AP1000 relating to the gray rod design and the core reference report.

Piketon, Ohio, United States

Section Manager for the Nuclear Criticality Safety group at the Portsmouth Gaseous Diffusion Plant. Supervised a team of NCS engineers and contractors performing NCS evaluations for the plant. Also developed a writer's guide for NCSEs and assisted with development and changes to plant NCS procedures and NCS engineer training requirements. Provided staffing of the site emergency operations center during drills and an event requiring its activation. Interacted with the plant management and NRC inspectors as needed. Served on the Plant Operations Review Committee to review changes. Held an active DOE-Q clearance during this assignment.

Piketon, Ohio, United States

Nuclear Criticality Safety (NCS) Engineer at the Portsmouth Gaseous Diffusion Plant. Performed NCS evaluations and calculations for operations occurring at the plant, and walkdown inspections of the operations. Took a technical leadership role in the NCS Nuclear Safety Upgrades project and won an Award of Excellence in 1997 for that role. Held an active DOE-Q clearance during this assignment.

Pittsburgh, Pennsylvania, United States

Performed core design and analysis for Callaway and San Onofre Unit 1 plants. Also performed and reviewed analyses for other 4-loop Westinghouse plants. Provided nuclear design support for fuel proposals by developing economically competitive loading patterns and performing comparison analyses between Westinghouse Integral Fuel Burnable Absorber (IFBA) and other burnable absorber technologies (gadolinia and erbia) which were published and presented at industry conferences. Supported changes and validation for the Westinghouse power distribution control code family, including validation of a new buckling search methodology for the Westinghouse APOLLO code. I also became qualified to perform nuclear criticality safety analysis on spent fuel pools and new fuel vaults during this assignment.

Seneca, South Carolina, United States

Oconee Reactor Engineering. This included monitoring reactor performance during normal operations and transients, planning power maneuvers to manage reactivity, preparing trip reports, supporting outage refueling activities such as fuel inspections and core verification, and performing physics testing. Also included staffing of Tech Support Center as needed during drills, monitoring fuel performance indicators, and tracking fuel movements in the plant.

Charlotte, North Carolina, United States

Nuclear Design/Analysis and Methods Development for Oconee units. This included creation of CASMO/PDQ7/NODE models, loading pattern development, safety parameter confirmation, maneuvering analysis to establish operating limits, performing physics parameter calculations to support plant operation, and reviewing such calculations performed by others. Also included some limited FORTRAN programming in the primary nuclear design codes (NODE and PDQ7) and more extensive programming in their supporting computer codes. This experience also included a one year rotational assignment at Catawba Nuclear Station in the Catawba Safety Review Group performing root cause analysis of NRC reportable events.

Bachelor Of Science (B.S.), Nuclear Engineering

Activities and Societies: Multiple Bands, Student Advisor, American Nuclear Society

High School

Activities and Societies: Multiple Bands, National Honors Society