Jonathon Walker Email & Phone Number

Las Vegas, NV, US

Lynchburg, Virginia, US

Criticality safety and radiological engineering for next-generation micro-nuclear reactors. Skills include nuclear code validation (SCALE and MCNP) per ANSI/ANS-8.24-2017 and NUREG-6698, criticality safety evaluation, dose field mapping, and shielding design.

Bellevue, WA, US

Nuclear safety engineering support for the design of the Molten Chloride Reactor Experiment (MCRE) and the Natrium sodium fast reactor demonstration project. Specific emphasis includes source term calculations, tritium permeation and release modeling, MACCS X/Q and RADTRAD modeling to support the design, construction and commissioning of these reactor.

Chicago, Illinois, US

Radiological engineering support for the commissioning of the Waste Treatment Plant vitrification facility at Hanford. Specific emphasis includes shielding evaluation and design using MCNP and Attila computer codes. Duties also include ALARA walkdown evaluations for facility systems and processes in accordance with 10 CFR 835.

Chicago, Illinois, US

Accident analysis support for the commissioning of the Waste Treatment Plant vitrification facility at Hanford. Specific emphasis included nuclear safety, hazards analysis and evaluation, and accident analysis in accordance with 10 CFR 830 and DOE-STD-3009-94.Winning accomplishments include the ongoing development and maintenance of the Safety Analysis.

Nuclear safety analysis support on contract for nuclear facility safety basis implementation in accordance with DOE O 425.1D. Site locations included Argonne National Laboratory (ANL) and the Portsmouth Gaseous Diffusion Plant (PORTS) Department of Energy (DOE) sites. Specific emphasis included nuclear safety, criticality safety, and USQ process support in.

Radiological nuclear safety analysis in support of GE Hitachi new fuel introduction and transportation cask shielding analysis. Specific emphasis includes radiation shielding and criticality safety analysis using MCNP code.Winning accomplishments included criticality safety analysis procedures to incorporate recent changes in NRC accepted methodology in.

Administration and development of the USQ process at the Advanced Mixed Waste Treatment Project in accordance with 10 CFR 830, Subpart B, DOE O 420.1C and DOE-STD-1186. Specific emphasis includes USQ process and procedure development, USQ evaluator training, project-wide USQ process application guidance, safety analysis, and dose consequence analysis.

Idaho Falls, ID, US

Facility safety basis and technical safety requirements development fulfilling the requirements of 10 CFR 830, Subpart B, DOE O 420.1C and DOE-STD-1186. Specific emphasis includes nuclear criticality, radiological, and chemical hazards safety analysis for DOE nuclear facilities, radiological dose consequence calculation using RSAC 6.0 and MicroShield 5.05.

Radiological analysis of environmental samples using alpha and gamma spectroscopy, proportional counting, and liquid scintillation counting techniques. Demonstrable proficiency related to nuclear instrumentation calibration, troubleshooting, and statistical data analysis.

Aided in the set up and installation of a fast-pulsed 10-MeV linear accelerator. Extensive experience in radiation safety, nuclear instrumentation, experimental hardware fabrication, soldering, and welding.

Provided emergency field medical care and support for the HHC 2/116 Armored Cavalry Division.

Master Of Science (Ms), Mechanical Engineering

Graduate Studies Toward M.S (All But Thesis), Physics With An Emphasis In Health Physics

B.S., Physics With An Emphasis In Health Physics

A.S, Physics Degree

Nano-Degree, Artificial Intelligence For Trading