Dan Pohl Email & Phone Number

Canada

Toronto, Ontario, Ca

Toronto, Ontario, Ca

-35 Direct Reports; including full time employees and contractors-Established Kinectrics Procurement Engineering Center of Excellence-Management oversight for all Bruce Power Permits contracted to Kinectrics-Management oversight for all Kinectrics Procurement Engineering work-Acting Section Manager, Major Component Replacement (MCR)

Toronto, Ontario, Ca

-Bruce Power Field Team Lead/Project Engineer (including small projects and forced outage support)-PHT Pump Performance Monitoring-EC Lifecycle Management Heath Report Development and Planning -Legacy TCC Removal SPOC-Unit 1 Main Output Transformer Root Cause Investigation Team Lead-Unit 3 A1831 Complex Troubleshooting Advisor

Aberdeen, Scotland, Gb

-Lead for strategically important projects within the Canadian nuclear industry.-Bid Manager and Project Manager for several high-profile projects for Bruce Power, OPG, CANDU Owner’s Group and NuScale Power.

Aberdeen, Scotland, Gb

RELAP5-3D Validation and Verification Test Suites, NuScale Power:Daniel was the project manager and primary analyst on this project, which involved the assessment of the predictive capabilities of the computer code RELAP5-3D for various test facilities. He developed several RELAP5-3D models using SNAP and successfully validated the models against experimental results in order to obtain quantitative computer code accuracy statements (i.e., bias and variation in the bias).LOF BEAU Analysis, OPG and Bruce Power:Daniel was the project manager and one of the primary analysts on this project, which involved the assessment of a heat transport pump trip LOF (Loss Of Flow) event at aged core conditions. This assessment involved using the Canadian nuclear industry guidelines for BEAU (Best Estimate Analysis and Uncertainty) methodology for licensing analysis. Daniel was responsible for SA (Sensitivity Analysis) and IUA (Integrated Uncertainty Analysis) to ensure that the analysis results remain unchanged near the 95th percentile case. The assessment included thermal-hydraulics simulations of the full Darlington system, in addition to simulation of all 120 channels in the pass of the core with the tripped pump.Preparation of the Validation and Accuracy Guidelines, CANDU Owner’s Group:Daniel was the project manager and a primary analyst on this project, which involved the assessment of best practices employed in computer code validation in Canada and in other jurisdictions (i.e., USA, EU). Daniel helped establish practical guidance for the Canadian nuclear industry in a number of key areas related to the execution of code validation which was documented with the aim of ensuring that CANDU related validation is complete, systematic, and aligned with the end use of computer codes in CANDU licensing analysis and related activities.

Aberdeen, Scotland, Gb

Next Generation Nuclear Plant Evaluation Model, United States Nuclear Regulatory Commission:Daniel was a primary analyst on this project, which involved the assessment of the predictive capabilities of the U.S. NRC computer code MELCOR for a PMR (Prismatic Modular Reactor) HTGR (High Temperature Gas Reactor) meso-scale heat transfer model. A MELCOR model was developed using SNAP and validated against the results of a benchmark FEA (Finite Element Analysis). Recommendations for MELCOR development were formally reported to the U.S. NRC and SNL and used in the development of MELCOR. This work was used by the U.S. NRC staff to develop the evaluation model that will be used to evaluate licensee calculations under normal operation and accident conditions.Preparation of the Validation and Accuracy Guidelines, CANDU Owner’s Group:Daniel was the project manager and a primary analyst on this project, which involved the assessment of best practices employed in computer code validation in Canada and in other jurisdictions (i.e., USA, EU). Daniel helped establish practical guidance for the Canadian nuclear industry in a number of key areas related to the execution of code validation which was documented with the aim of ensuring that CANDU related validation is complete, systematic, and aligned with the end use of computer codes in CANDU licensing analysis and related activities. Moreover, a simple statistically based code accuracy estimation methodology was developed and its role in supporting CANDU safety analysis was described.Rationalization of CANDU Phenomena Descriptions, CANDU Owner’s Group:Daniel was the analyst responsible for compiling and editing a 700+ page industry-wide report, which updated discipline specific phenomena descriptions to new generic phenomena descriptions. The report collected all phenomena descriptions for all physical processes relevant to CANDU nuclear power plants into a single catalogue for the first time.

Aberdeen, Scotland, Gb

Bruce A Restart - Power Block Close-out Support/DCN Close-out:Dan had three different roles on this project drafter, issues coordinator, and drafting trainer. As a drafter, Dan developed in-depth knowledge of Engineering Change Control (ECC) closeout process, Bruce Power drafting standards, drafted for hundreds of drawings. Daniel was promoted to issues coordinator by his section manager to oversee successful resolution of all issues and communicate resolution to all parties involved and acted as a liaison between engineers at Bruce Power site and the AMEC NSS drafting team. He coordinated resolution of hundreds of drafting and engineering related issues and helped design a drafting database in collaboration with IT to incorporate forum for tracking drafting issues. Dan was also a drafting trainer where he created a training package with OPG, Bruce Power, PMC and AMEC NSS drafting standards and trained/mentored 6 employees.

Aberdeen, Scotland, Gb

Quantification of Code Accuracy for Coolant Void Fraction:-Lead analyst tasked with confirming the industry standard computer code accuracy assessment methodology using a demonstration problem.-Calculated and assessed accuracy (bias and variation in bias) of thermal hydraulic computer code results relative to RD-14M neutron scatterometer void fraction data.-Prepared an industry report that substantiated the methodology that was used to quantify the code accuracy, which was issued on time and within budget and published by COG (CANDU Owners Group).Updated and Qualified the Software Inventory System:-The AMEC NSS Software Inventory System needed updating to maintain compliance with governing SQA (Software Quality Assurance) Procedures.-Prepared a detailed Work Plan for updating and qualifying the Software Inventory System.-Coordinated reviews by IT Manager and Code Development and Maintenance Manager.-Able to maintain compliance with governing Software Quality Assurance Procedures and relevant industry standards (i.e., CSA N286.7-99).RELAP5 Model Development:-Improved thermal hydraulic models for a Darlington Nuclear Generating Station (DNGS) Loss of Flow (LOF) simulation in RELAP5 (US NRC thermal hydraulic computer code).-Created a TUF and RELAP validation matrix for CAMP implementation used in the business case.-Prepared a procedure to generate a RELAP5 executable file in Windows from Linux source files.

Corvallis, Or, Us

Design Certification Application, NuScale:-Led several projects for NuScale Power including Severe Accident model updates, software configuration management, establishing and maintaining a High-Performance Computing Environment for the PRA group, and preparation/reviews of Severe Accident reports.-Accountable for all thermal hydraulic and severe accident simulations that would be used to support Chapter 19 (Probabilistic Risk Assessment and Severe Accidents) of the NuScale Design Certification Application (DCA), which was accepted by U.S. NRC for review. -One of the main authors of the NuScale Licensing Topical Report on Design-Specific Emergency Planning Zone Sizing Methodology.-Provided leadership, coaching and development for 10 staff (4 NuScale full-time staff, 3 augmented staff and 3 interns).-Developed quality processes and procedures for the Probabilistic Risk Assessment group that comply with the relevant QA standards and requirements (U.S. NRC regulations and international standards).

Pisa, Tuscany, It

Research/Study Opportunity:-Developed and applied a methodology called the Multi-step Approach to Code-coupling for Progression Induced Severe Accidents in CANDU nuclear power plants (MACPISA-CANDU).-MACPISA-CANDU was used to couple a MATLAB single fuel channel model with a primary heat transport system model developed in the U.S. NRC code MELCOR to model a small break loss of coolant accident (SBLOCA) in conjunction with a loss of emergency coolant injection (LOECI) in a CANDU 6 nuclear power plant.

Toronto, Ontario, Ca

Professional Experience Year Internship:-The first intern to be hired to the role of Program Manager at Celestica Inc.-Program Manager for the Juniper Networks new product introduction.-Main point of contact for all steps of the high-speed telecom router manufacturing process and was directly accountable for customer satisfaction.-Effective communication led to 14 consecutive months of 100% on time delivery.-Responsible for issuing status reports, both internally and externally to the company on a weekly basis.-Ensured that the financial aspects of New Product Introduction were under control; this included cost analysis and pricing issues.-Duties included quoting for prototype work done and ensuring all efforts were documented.-Able to increase the NPI revenue by 25%.

Toronto, Ontario, Ca

-Planned out and performed maintenance activities in the Unit Operations Lab, which included a two-story distillation column and large-scale leaching and heat transfer equipment.-By completing planned maintenance tasks in parallel rather than in series, able to complete the planned maintenance 1 month ahead of schedule.-Webmaster for Unit Operations Lab website.

B.A.Sc., Chemical Engineering

Marketing Specialization Cerificate, Business Foundations

M.A.Sc., Engineering Physics (Nuclear)