Originate/review design nuclear criticality safety evaluations (NCSEs) and supporting calculations concerning all processes associated with the design of the U.S. Nuclear Regulatory Commission (NRC) licensable MOX Fuel Fabrication Facility (MFFF) being constructed at the U.S. Department of Energy (DOE) operated Savannah River Site, such as plutonium oxide receipt and storage; plutonium oxide handling, milling, and sampling; aqueous polishing processes involving plutonium nitrate solutions, plutonium oxalate solutions, and plutonium water solutions; laboratory operations; calcination of polished plutonium oxide; auxiliary systems such as process off-gas, ventilation, and dust extraction; blending (dosing) of plutonium and uranium oxides; mixed oxide storage; mixed oxide fuel pellet fabrication; handling and storage of mixed oxide fuel pellets; mixed oxide rod and assembly fabrication; mixed oxide fuel assembly cleaning, manipulating, inspection, and storage; and mixed oxide assembly packaging operations. Co-authored the 5,000+ page Integrated Safety Analysis (ISA) Summary regarding all criticality safety processes and operations involved with the MFFF.

Prepare NCSEs and supporting criticality safety calculations for long-term storage and handling of HEU and weapons-grade plutonium within drums, waste boxes, over-packs, and interim storage containers. Prepare NCSEs and supporting criticality safety calculations for machine waste compaction and waste box/drum shredding. Repackaged waste drums and boxes were evaluated for acceptance with Waste Isolation Pilot Plant (WIPP) criteria. Oversee and manage development of all AMWTP criticality safety evaluations and calculations.

Prepared NCSEs and MCNP calculations involving storage and handling of HEU within drums and excavation of heavily contaminated subterranean piping and building structures. Performed independent review of uranium estimates entrained in deactivated process piping using advanced techniques.

Originated NCSEs and MCNP calculations involving WG Pu within TRU waste containers, LLW segregation, high FGE waste splitting/handling, Pu standards storage, and pipe-overpacks. Prepared CHAs incorporating criticality safety using the DOE-STD-3009-94 process.

Performed independent review of MCNP calculations involved with staging and repackaging of all commercial and DOE spent-fuel assemblies within boron-enriched staging pools and aboveground encapsulated storage. Performed independent review of MCNP4c validation involving commercial fresh and spent-fuel assemblies.

Prepared NCSEs and SCALE calculations for long term storage and handling of HEU and WGPu within storage containers and selective consolidation of targeted TRU waste recovered from trenches within the RWMC to meet WIPP criteria.

Prepared NCSEs and MCNP calculations for liquid and solid waste treatment and recovery of SEUinvolved with production of enriched CANDU reactor fuel bundles.

Prepared NCSEs and SCALE calculations for the various processes associated with the Navy Fuel Project such as storage of fissile material waste, research and development laboratory operations, shipping and receiving, solution staging in columns, and wastewater treatment.

Originated evaluations determining NCS strategies and performed reactivity calculations for the oxidation process of plutonium metal and its subsequent storage and assay for the Los Alamos designed Pit Disassembly and Conversion Facility. Forms of evaluated fissile material include plutonium metal, plutonium oxide, HEU metal, HEU oxide, plutonium-water solutions, and uranium-water solutions. Reviewed safety evaluations and verified associated reactivity calculations concerning insertion and removal of spent fuel assemblies in Oconee spent-fuel storage pool. Evaluated the credited use of boron concentration and the determination of limited crushing of assemblies. Prepared NCSEs and supporting criticality safety calculations for long term storage and handling of high enriched uranium (HEU) and weapons-grade plutonium within universal shielded over-packs and interim storage. Performed radiation shielding design evaluations and radiation dose analyses for the MFFF. Performed nuclear safety analysis of normal and off-normal plutonium inhalation dose consequence to site workers. Performed chi/q calculations resulting in off-site dose consequence analysis. Involved in Quality Assurance procedure revisions concerning the development, verification, validation, and control of nuclear safety Quality Level 1 software. Performed ALARA calculations for the fabrication of MOX fuel assemblies. Performed nuclear reactor operations post-accident analysis of criticality consequences from storage pool spent-fuel assembly drops and control room dose consequences due to steam generator tube rupture.

Developed MCNP and SCALE models of possible fissile configurations (heterogeneous conglomerations and stratifications) in unfavorable geometry spent fuel storage pools and waste storage tanks that contained cracked/broken HEU rods. Performed Hot Cell operations irradiating various items with Co-60. Materials irradiated ranged from simple electrical wires up to two ton actuators. Equipment was operated during and after irradiation periods and the degradation ofperformance was analyzed. Also performed radiation detector calibration and design and construction of neutron collimators. Assisted in calculations and measurements of neutron and photon dose rates at flight path 30-L at the Los Alamos National Laboratory Weapons Neutron Research beam, including the use of tissue equivalent proportional counters and tissue equivalent ionization chambers.