EXPERIENCE
Nuclear Criticality Safety Engineer, Savannah River Nuclear Solutions
Aiken, SC
June 2010 - Present
Provide engineering support to facilities at the Savannah River Site (SRS) by performing Nuclear Criticality Safety Evaluations (NCSEs) for on-going and/or future missions for the disposition of nuclear material as it pertains to Environmental Management (EM) and Department of Energy (DOE) initiatives while ensuring compliance with DOE Orders and other applicable Federal Regulations (ie. Title 10 CFR). Conducting an NCSE requires cooperation between multiple departments, with Operations and Engineering support being the largest within the impacted facility. As a lead author, responsibilities include coordinating and leading the nuclear criticality portion of the Hazard Analysis. Gaining a better understanding of the facility and/or operation in question is an added benefit of a Hazard Analysis meeting. As the author it is my responsibility to lead the Hazard Analysis meeting in order to generate credible accident scenarios that must be analyzed and modeled further to ensure the safe handling and/or storage of nuclear material, such as spent nuclear fuel. The NCSEs require extensive computer modeling using Monte Carlo N-Particle Transport Code (MCNP), which is used to simulate nuclear processes, as well as the use of Microsoft Excel to further analyze data generated by MCNP. Presentation of results to upper management is required as concurrence/approval is needed before operations can begin. In support of our Nuclear Facility, provide required periodic assessments to ensure compliance through procedure reviews, field observations of current procedures being conducted or operating systems when available and always ensuring applicable criticality safety limits are being implemented accordingly. The assessments I conduct require review of documents applicable to current operations such as operating procedures, credited technical standards and applicable NCSEs as well as a walk-down of the system or operation in question through field observations when available. Performing at least one assessment each month is required when supporting a specific facility.
Participated in a LEAN event that was aimed at making the process of conducting an NCSE more efficient and less time consuming. The time frame began with the scope of work and ended with full management approval of the evaluation. Conducting an NCSE can range from two to ten months with potentially longer durations depending on the complexity of the project. The event resulted in a potential annual cost savings of at least $734,000 by reducing the amount of rework. The reduction was a result of taking an extra step to improve document quality to reduce revisions solely based on nontechnical comments which is a major contributor to the current review process. Findings were presented to upper management upon completion to determine viability of the proposed changes. Upon approval the findings were then presented to the Criticality Safety Department to inform them on the expectations of the updated format/process of new NCSE development.
I received a spot award for the work conducted on a new project funded by National Nuclear Security Administration (NNSA). Through explicit modeling we were able to allow the facility to safely produce more oxide to be sent to the Mixed Oxide Fuel Fabrication Facility (MOX) currently under construction to make a new form of fuel to be used to power nuclear reactors. Using MCNP it was shown that we could quadruple the original throughput to create more oxide to be shipped to MOX.
Intern, Oak Ridge National Lab, Oak Ridge, TN
Mentor: Julie Ezold
865-574-9594
Summer 2009
Provided engineering support to the optimization of processing irradiated targets and utilizing programming languages such as MCNP and ORIGEN. Work involved using these programs to simulate the use of a fission chamber detector to determine transmutated elements formed within the chamber. The detector in question was used for 23 years to assay Californium (Cf) sources created using the High Flux Isotope Reactor. The concern was that the Uranium (U) plates within the detector generated an unsafe amount of Plutonium (Pu) due to the assaying of Cf sources which emit large amounts of fast neutrons; before the detector could be dispositioned, they needed to ensure it was safe to do so. MCNP was used to generate the flux profiles of each Cf source. These fluxes along with the specific activities of each source was inserted into ORIGEN to simulate the detector being irradiated over the 23 year period to determine the mass of Pu present within the chamber due to U being bombarded by fast neutrons.
TRAINING
Nuclear Criticality Safety Engineer
Qualified Criticality Safety Engineer (CSE) per the Nuclear and Criticality Safety Program at SRS as approved by DOE; qualification included becoming an MCNP calculation specialist, conducting multiple NCSEs and completing the technical staff training comprised of a series of courses lasting approximately 3 months. During the training period I was a Co-Author for NCSEs where I was responsible for all computer modeling and completion of the document with the guidance of a qualified CSE when necessary.
Methods for Reviewing Safety Analysis Reports for Packages and Performing Confirmatory Analysis Training Course
The purpose of this course was to develop skills in reviewing Safety Analysis Reports for Packagings (SARPs) and in performing confirmatory analyses. The training course was conducted by the Packaging and Transportation Group, part of the Nuclear Fuel Cycle Program in Global Security Directorate's E Progr...
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