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Our industry is going through a time of transition with a generation of plant personnel retiring and new professionals entering the workforce.

With AREVA's training portfolio, we are working to foster operational excellence, to facilitate knowledge transfer and to provide utility employees with the information and skills they need to continue operating nuclear energy facilities safely and at optimal performance.

To open and close the course descriptions, click the Training Course name headers.

  • Fuels Integrated Training

    In order to help our customers maintain required certifications and operate nuclear energy facilities safely and at optimal performance, AREVA has worked diligently to bring our customers' training needs to the forefront of our priorities. AREVA has created a Fuels Integrated Training Program (FIT) fostering Operational Excellence and the knowledge to operate plants with AREVA’s fuel in the safest most efficient manner — helping satisfy our customers' engineering training requirements and needs, resulting in higher levels of customer satisfaction.

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    TRAINING COURSE DESCRIPTIONS

    Training contact: fueltrainingNA@areva.com

    AREVA Fuels has developed a series of in-depth technical training courses covering fuels-related analyses. These courses implement modern instructional techniques geared to engage the audience by simultaneously targeting multiple learning styles.

    Features of the training include:

    Instructor-led PowerPoint Presentations     Microsoft OneNote Companion Notebooks  
                 
    Hands-on Example Problems     Interactive Exercises  
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    TH Reload Process Overview for CE and Westinghouse Plants

    TH Reload Process Overview for CE and Westinghouse Plants

    Course Dates: May 1, 2017; July 31, 2017

    Registration Ends: April 1, 2017; June 30, 2017

    Course Number: 1400

    Course Location: AREVA Operational Center of Excellence, 3315 Old Forest Road, Lynchburg Virginia.

    Course Hours: 8

    Course Cost: $2,000.00 per student per day

    Plants: Westinghouse and CE

    Training Tier: 2

    This full-day course provides an overview of the thermal hydraulic reload analysis process performed for CE and Westinghouse Plants. The reload process is that consistent with the EMF-2310, EMF-1961, and EMF-92-081 methodologies utilizing XCOBRA-IIIC.

    The course follows the FIT training style of maximizing student engagement through the use of visually impactful training presentations, 7 interactive exercises, and 5 optional example problems*. The exercises and example problems reinforce key concepts and maintain student attention more effectively than traditional lecture-focused training. The training is packaged within an electronic OneNote companion notebook, which contains all training materials facilitating the interactive training experience.

    The introduction to this 5 module course begins with a general map of the TH reload process. Each module then provides a more detailed summary of a particular technical topic. The content includes the following:

    • Module 1 includes a description of the CE and W plant layouts and trips; a description of the analysis process; and a brief background on Critical Heat Flux (CHF) and statistics.
    • Module 2 describes the development of the three primary XCOBRA-IIIC models with the methodology. These include (1) the two-pass model used for Non-LOCA transient event evaluations, (2) the simplified one-pass model used for setpoint calculations, and (3) the event-specific post-SCRAM MSLB model.
    • Module 3 includes a description of the analyses typically performed as part of a TH Compatibility assessment. These include Guidetube Boiling, Rod Bow, and Mixed-Core Assessments of pressure, flow, and CHF.
    • Module 4 covers the Departure from Nucleate Boiling (DNB) and Fuel Centerline Melt (FCM) calculations performed as part of the evaluation of the Non-LOCA transient events. In addition to margin calculations, this module also covers development of the Limiting Axial, calculation of the FCM Limit, and discussion of the Boron Dilution analysis.
    • Module 5 cover the setpoints analyses performed for both the CE and Westinghouse plants. For CE plants these include Local Power Density (LPD) Limiting Safety System Settings (LSSS), LPD Limiting Condition of Operation (LCO), DNB LCO, Thermal Margin / Low Pressure (TM/LP), and Thermal Margin Limit Lines (TMLL). For Westinghouse plants these include Over-Temperature Delta Temperature (OTΔT), Over Pressure Delta Temperature (OPΔT), and Core Safety Limit Lines (CSLL).

    *Example Problems require access to AREVA analysis codes.

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    XCOBRA-IIIC Model Development

    XCOBRA-IIIC Model Development

    Course Dates: May 4-5, 2017; August 1-2, 2017

    Registration Ends: April 6, 2017; July 1, 2017

    Course Number: 1401

    Course Location: AREVA Operational Center of Excellence, 3315 Old Forest Road, Lynchburg Virginia.

    Course Hours: 16

    Course Cost: $2,000.00 per student per day

    Plants: CE & Westinghouse

    Training Tier: 3

    This two-day course covers the development of XCOBRA-IIIC models for use with the EMF-2310 and EMF-1961 Methodologies, including the full core two-pass model, the one-pass setpoints models, and the main steam line break model.

    The course follows the FIT training style of maximizing student engagement through the use of visually impactful training presentations, 12 interactive exercises, and 3 example problems*. The exercises and example problems reinforce key concepts and maintain student attention more effectively than traditional lecture-focused training. The training is packaged within an electronic OneNote companion notebook, which contains all training materials facilitating the interactive training experience.

    The training describes the model types required to perform reload analysis.

    • The two-pass model is used in the DNB evaluation for non-LOCA safety analysis transients. In pass one, each assembly is modeled to calculate core conditions needed for pass two. In pass 2 the limiting assembly is modeled on a subchannel-by-subchannel basis.
    • The one-pass model is a simplified model used in setpoint analysis. The training includes discussion on the benchmarking process used to show that the one-pass model is conservative relative to the two-pass model.
    • The main steam line break (MSLB) model in an event-specific model used to account for the asymmetric core conditions that occur during the post-SCRAM MSLB event.

    For each model type, the course covers applicable acceptance criteria and licensing requirements; how each model fits into the reload process; card-by-card descriptions of the model development process; review of code output and common consistency checks; and an example problem.

    In addition, the introduction to this course includes a discussion of the history of XCOBRA-IIIC and the basic theory of DNB and subchannel modeling.

    *Example Problems require access to AREVA analysis codes.

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    Fuel Centerline Melt Limit and Limiting Axial Analysis

    Fuel Centerline Melt Limit and Limiting Axial Analysis

    Course Dates: May 8, 2017; August 3, 2017

    Registration Ends: April 10, 2017; July 3, 2017

    Course Number: 1402

    Course Location: AREVA Operational Center of Excellence, 3315 Old Forest Road, Lynchburg Virginia.

    Course Hours: 4

    Course Cost: $2,000.00 per student per day

    Plants: Westinghouse and CE

    Training Tier: 3

    This half-day course covers the calculation of the fuel centerline melt limit and limiting axial analyses. The results of these analyses feed downstream setpoint and Chapter 15 DNB and FCM analyses. This course covers analyses consistent with the EMF-2310 and EMF-1961 methodologies.

    The course follows the FIT training style of maximizing student engagement through the use of visually impactful training presentations, 5 interactive exercises, and 2 example problems*. The exercises and example problems reinforce key concepts and maintain student attention more effectively than traditional lecture-focused training. The training is packaged within an electronic OneNote companion notebook, which contains all training materials facilitating the interactive training experience.

    The course provides detailed discussion of two analyses in the thermal hydraulic reload process. The first analysis is the calculation of the cycle specific fuel centerline melt (FCM) limit. The FCM Limit module includes discussion of licensing requirements; the basis for when an FCM limit calculation is required; a detailed discussion of the calculation performed in RODEX2 to correlate LHGR to rod melt; a detailed discussion of the calculation performed in MELTLIM to calculate a UO2 LHGR limit that precludes melt in all rod types; a description of analysis inputs; and execution of the analysis code and review of output.

    The second analysis is the Limiting Axial analysis which defines the axial power shape(s) use in downstream DNB calculations. The Limiting Axial module includes the basis for using the limiting axial in DNB analysis; a discussion of the difference between the ‘design’ limiting axial, and the ‘cycle-specific’ limiting axial;  a step-by-step walkthrough of the limiting axial analysis process; a description of the power and ASI input ranges and how they are determined; and execution of the analysis code and review of output.

    *Example Problems require access to AREVA analysis codes.

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    Departure from Nucleate Boiling and Fuel Centerline Melt Analysis

    Departure from Nucleate Boiling and Fuel Centerline Melt Analysis

    Course Dates: May 8, 2017; August 3, 2017

    Registration Ends: April 10, 2017, July 3, 2017

    Course Number: 1403

    Course Location: AREVA Operational Center of Excellence, 3315 Old Forest Road, Lynchburg Virginia.

    Course Hours: 4

    Course Cost: $2,000.00 per student per day

    Plants: CE & Westinghouse

    Training Tier: 3

    This half-day course covers key inputs and calculation descriptions for Chapter 15 Departure from Nucleate Boiling (DNB) and Fuel Centerline Melt (FCM) thermal hydraulic analyses. The calculations covered are based on XCOBRA-IIIC and the EMF-2310 non-LOCA methodology.

    The course follows the FIT training style of maximizing student engagement through the use of visually impactful training presentations, 6 interactive exercises, and 1 example problem*. The exercises and example problem reinforce key concepts and maintain student attention more effectively than traditional lecture-focused training. The training is packaged within an electronic OneNote companion notebook, which contains all training materials facilitating the interactive training experience.

    The training provides detailed discussion of the analyses used to evaluate DNB and FCM. It includes the thermal hydraulic evaluations, which calculate margin to failure based on inputs provided from RELAP transient analysis and PRISM neutronics analysis (the generation of these inputs is not discussed). For both criteria, the course includes discussion of the applicable acceptance criteria, licensing requirements, and NRC approved methodologies; description of the analysis process; discussion of fuel failure assessments; and margin recovery techniques. For the DNB analyses, the course also discusses the typical events specific requirements.

    This course also covers the unique calculation performed for the Post SCRAM Main Steam Line Break (MSLB) event. The MSLB section includes discussion of the iterative process between XCOBRA-IIIC and PRISM used to develop the neutronics inputs, DNB evaluation using an event specific XCOBRA-IIIC model, FCM calculation, and reactivity verification analysis.

    Recommended prerequisites:
    1401 - XCOBRA-IIIC Model Development
    1402 - Fuel Centerline Melt Limit And Limiting Axial Analysis

    *Example Problem requires access to AREVA analysis codes.

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    Statistical Setpoint Verification for CE Plants

    Statistical Setpoint Verification for CE Plants

    Course Dates: May 15-16, 2017; August 7-8, 2017

    Registration Ends: April 17, 2017; July 7, 2017

    Course Number: 1404

    Course Location: AREVA Operational Center of Excellence, 3315 Old Forest Road, Lynchburg Virginia.

    Course Hours: 16

    Course Cost: $2,000.00 per student per day

    Plants: CE

    Training Tier: 3

    This two-day course covers the statistical setpoint calculations for CE plants (EMF-1961 Methodology) that support establishment or verification of cycle specific plant protective setpoints designed to protect the fuel.

    The course follows the FIT training style of maximizing student engagement through the use of visually impactful training presentations, 17 interactive exercises, and 4 example problems*. The exercises and example problems reinforce key concepts and maintain student attention more effectively than traditional lecture-focused training. The training is packaged within an electronic OneNote companion notebook, which contains all training materials facilitating the interactive training experience.

    The course provides detailed discussion of Thermal Hydraulic (TH)-related Limiting Conditions of Operation (LCOs) and Limiting Safety System Settings (LSSS) used to protect Departure from Nucleate Boiling (DNB) and Fuel Centerline Melt (FCM) design limits. These include Local Power Density (LPD) LSSS, LPD LCO, DNB LCO, Thermal Margin / Low Pressure (TM/LP), and Thermal Margin Limit Lines (TMLL). Each module includes the basis of the analysis, specific methodology used for the verification, description of key input parameters, and explanation of how the analysis is performed, including example exercises and hands on computer code runs.

    In addition, the course provides an overview of the CE reactor protection system and a basic refresher for statistical methods relevant to the setpoints methods.

    *Example Problems require access to AREVA analysis codes.

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    Statistical Setpoint Verification for Westinghouse Plants

    Statistical Setpoint Verification for Westinghouse Plants

    Course Dates: May 22-23, 2017; August 10-11, 2017

    Registration Ends: April 24, 2017, July 10, 2017

    Course Number: 1405

    Course Location: AREVA Operational Center of Excellence, 3315 Old Forest Road, Lynchburg Virginia.

    Course Hours: 12

    Course Cost: $2,000.00 per student per day

    Plants: Westinghouse

    Training Tier: 3

    This 2-day course covers the statistical setpoint calculations for Westinghouse plants (EMF-92-081 Methodology) that support establishment or verification of cycle specific plant protective setpoints designed to protect the fuel.

    The course follows the FIT training style of maximizing student engagement through the use of visually impactful training presentations, 9 interactive exercises, and 1 example problem*. The exercises and example problem reinforce key concepts and maintain student attention more effectively than traditional lecture-focused training. The training is packaged within an electronic OneNote companion notebook, which contains all training materials facilitating the interactive training experience.

    The course provides detailed discussion of Thermal Hydraulic (TH)-related setpoint analyses used to protect Departure from Nucleate Boiling (DNB) and Fuel Centerline Melt (FCM) design limits. These include Over-Temperature Delta Temperature (OTΔT), Over Pressure Delta Temperature (OPΔT), and Core Safety Limit Lines (CSLL). Each module includes the basis of the analysis, specific methodology used for the verification, description of key input parameters, and explanation of how the analysis is performed, including example exercises and hands on computer code runs.

    In addition, the course provides an overview of the Westinghouse reactor protection system and a basic refresher for statistical methods relevant to the setpoints methods.

    *Example Problem requires access to AREVA analysis codes.

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    B&W Fuel Reload Licensing Process Overview

    B&W Fuel Reload Licensing Process Overview

    Course Dates: July 5-9, 2017; August 21-22, 2017

    Registration Ends: June 5, 2017; July 21, 2017

    Course Number: 2000

    Course Location: AREVA Operational Center of Excellence, 3315 Old Forest Road, Lynchburg Virginia.

    Course Hours: 36

    Course Cost: $2000.00 per student per day

    Plants: B&W

    Training Tier: 1

    This five-day course provides an overview of the entire fuels reload analysis and licensing process for B&W plants (BAW-10179 Methodology).  Included is a description of the mechanical fuel design methodology and all elements of the supporting reload licensing analyses spanning neutronics, thermal-hydraulics, thermo-mechanical, and safety analyses.

    The course follows the FIT training style of maximizing student engagement through the use of visually impactful training presentations. The training is packaged within an electronic OneNote companion notebook, which contains all training materials facilitating the interactive training experience.

    Course Outline

    • Fuel Assembly/Control Component Mechanical Design and Performance
    • Fuel Rod Thermal Mechanical Performance
    • Fuel Assembly Structural Analyses
    • Core Design and Fuel Cycle Analyses
    • Nuclear Analyses
    • Fuel Assembly Hydraulics and Core Thermal-Hydraulic Performance
    • Non-LOCA Safety Analyses
    • ECCS Analyses
    • Radiation Analyses
    • Core Safety and Maneuvering Analyses
    • Core Monitoring and Operation
    • Water Chemistry
    • Crud Evaluation
    • Fuel Reliability

    This training is intended as in introduction into AREVA’s B&W Plant Reload Licensing process and provides a high-level overview of all the interdisciplinary analyses that support reload licensing for a given plant cycle. 

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    Critical Heat Flux

    Critical Heat Flux (CHF)

    Course Dates: May 10, 2017; August 28, 2017

    Registration Ends: April 12, 2017; July 31, 2017

    Course Number: 3401

    Course Location: AREVA Operational Center of Excellence, 3315 Old Forest Road, Lynchburg Virginia.

    Course Hours: 4

    Course Cost: $2,000.00 per student per day

    Plants: PWRs

    Training Tier: 3

    This half-day course provides an overview of the critical heat flux (CHF) phenomena, mechanisms leading to CHF, experimental testing for CHF, and empirical models used to predict CHF.

    The course follows the FIT training style of maximizing student engagement through the use of visually impactful presentation materials and 2 exercises. Exercises and review questions reinforce key concepts and maintain student attention more effectively than traditional lecture-focused training.

    The course begins by describing the fundamental CHF phenomena and it causes, and differentiates the possible mechanisms for CHF. Next, the focus shifts to CHF from the regulatory perspective, including legal requirements and acceptance criteria. The experimental testing and correlation development process is then described, including discussion of the CHF test facilities, test configurations, and correlation considerations and limitations. The final part of the course describes specific CHF correlations and can be tailored based on class participants.

    Computer access is not required, as this course does not include a OneNote Companion.

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    Form Loss Coefficients

    Form Loss Coefficients (FLC)

    Course Dates: May 10, 2017; August 28, 2017

    Registration Ends: April 12, 2017; July 31, 2017

    Course Number: 3402

    Course Location: AREVA Operational Center of Excellence, 3315 Old Forest Road, Lynchburg Virginia.

    Course Hours: 3

    Course Cost: $2,000.00 per student per day

    Plants: Any

    Training Tier: 2

    This 3 hour course covers the fundamental physics behind the loss coefficient, how the coefficient is derived, and how it is often used in a reload analysis. (Fundamentals apply to form loss coefficients, pressure loss coefficients, and pressure drop coefficients.)

    The course follows the FIT training style of maximizing student engagement through the use of visually impactful presentation materials and 2 exercises. Exercises and review questions reinforce key concepts and maintain student attention more effectively than traditional lecture-focused training.

    The course begins by describing what the PLC represents and why basic fluid dynamics theory cannot practically represent reality. The class then covers how to convert from a measured pressure drop to a loss coefficient, including emphasis on key considerations such as the reference area, thermal expansion, and resistance. Finally, the course describes how the loss is used in a subchannel code and in a lift calculation.

    Computer access is not required, as this course does not include a OneNote Companion.

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    COBRA-FLX™

    COBRA-FLX™ Thermal Hydraulic Subchannel Code Overview

    Course Dates: May 11, 2017; August 31, 2017

    Registration Ends: April 13, 2017; July 31, 2017

    Course Number: 3403

    Course Location: AREVA Operational Center of Excellence, 3315 Old Forest Road, Lynchburg Virginia.

    Course Hours: 3

    Course Cost: $2,000.00 per student per day

    Plants: Any

    Training Tier: 2

    This 3 hour course provides an overview of how a subchannel code works and what differentiates AREVA’s fully licensed, next generation subchannel code—COBRA-FLX™—from other subchannel codes.

    The course follows the FIT training style of maximizing student engagement through the use of visually impactful presentation materials. Review questions are used to reinforce key concepts and maintain student attention.

    The course begins by providing an understanding of what the NRC requires and the situational validity of subchannel codes. The class then covers the assumptions embedded in a subchannel code, the equations solved by the code, and a brief overview of numerical calculus. Finally, the course describes how COBRA-FLX™ is different from other subchannel codes and examples of AREVA input automation tools and post-processors.

    Computer access is not required, as this course does not include a OneNote Companion.

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    Mixed Core Analysis with COBRA-FLX™

    Mixed Core Analysis with COBRA-FLX™

    Course Dates: May 11, 2017; August 31, 2017

    Registration Ends: April 13, 2017; July 31, 2017

    Course Number: 3404

    Course Location: AREVA Operational Center of Excellence, 3315 Old Forest Road, Lynchburg Virginia.

    Course Hours: 4

    Course Cost: $2,000.00 per student per day

    Plants: PWRs

    Training Tier: 3

    This half-day course provides an overview of the analyses typically performed to ensure hydraulic compatibility for lead test assemblies, VQP, or a fuel transition effort. Examples specific to a sub-channel analysis code were developed for COBRA-FLX™, AREVA’s fully licensed, next generation subchannel code.

    The course follows the FIT training style of maximizing student engagement through the use of visually impactful presentation materials and 1 exercise. The exercise and review questions reinforce key concepts and maintain student attention more effectively than traditional lecture-focused training.

    The course begins by discussing pressure loss coefficient considerations important to mixed core analysis. The classes then covers each of the typical components of a thermal hydraulic compatibility analysis: pressure drop, control rod drop time, inter-assembly crossflow velocity, DNB performance impact, RCS loop flow, and bypass flow. Finally, the course describes guide tube boiling and rod bow analysis.

    The course can be adapted to thermal hydraulic compatibility analysis using XCOBRA-IIIC, upon request.

    Computer access is not required, as this course does not include a OneNote Companion.

  • NDE Training
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    TRAINING COURSE DESCRIPTIONS

    Training contact: NDEtrainingAdmins@areva.com

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    ECT - Eddy Current Training - 100 Level

    ECT-126

    Eddy Current Familiarization

    (typically three days)

    This introductory course covers a broad range of elements related to the acquisition, analysis, management, and relevance of tubular product eddy current data and is intended for non-specialists who would benefit from a general understanding of the theoretical and applied aspects of eddy current inspections. Beginning with an overview of both the scientific basis of the phenomenon of eddy currents as well as the industry codes that govern inspections, the student is then presented with the technology and hardware that is used to record ECT data. A computer is provided to each student for instruction on signal interpretation of both calibration standard and actual in-service tubing data. The course instructor is an experienced ET Level III Examiner who will also utilize specialist speakers to cover topics such as data management and tube integrity engineering. Because class enrollment is not intended to lead directly to industry certification (there are no student examinations), there is flexibility in the presentation of topics, as course content and emphasis may be tailored to the specific needs of the student.

     

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    NDE for Engineers

    NDE for Engineers

    NDE for Engineers

    (24 hours)

    This course is designed for anyone who directly or indirectly is affected by NDE. No prior experience is needed in NDE or ASME Codes as the course dissects these Codes for the student.

    Students will learn the basic principles of several NDE methods commonly used in the nuclear industry: liquid penetrant, magnetic particle, visual weld inspection, ASME III visual inspections, and ASME XI visual inspections. In addition, the principles of the eddy current, radiography, and ultrasonic examination techniques are covered. In the end, students will spend an afternoon actually performing some of these techniques.

    The course provides an overview of why the nuclear industry does what it does in NDE terms. The material covers federal regulation, relevant ASME Section III subsections as well as ASME Section XI. This material is reviewed in detail with students to aid students in determining what NDE is required for various applications. The interrelation of these various codes is also explained in detail.

    Practical exercises are used to provide students with the opportunity to consult the various codes and determine, on their own, what NDE methods are most appropriate for the application. Actual situations from AREVA’s business are used to illustrate practical applications in the student's daily work.

    While the title states “for engineers,” this class is also beneficial for supervisors and managers of personnel. Past students have included engineers, vice presidents of organizations, foreign authorized nuclear inspectors, and personnel from subcontracted NDE companies.

  • ASME

    Training contact: Caleb Tomlin Caleb.Tomlin@areva.com

    ATC-001: Overview of Codes and Standards for Nuclear Power Plants

    This course will introduce plant personnel to the ASME Code. The course will focus on Sections III and XI, with discussion of Sections II, V, and IX and how they pertain to Section III. The Operations and Maintenance Code as well as Section VIII will also be touched on. The course will cover how the NRC invokes the ASME code, including discussion of the Code of Federal Regulation and applicable Regulatory Guides. The NQA-1 Nuclear Quality Assurance program will also be discussed.

    Course Outline

    • Module 1- Overview of ASME
      This module includes an introduction to ASME, describing the organization of ASME and its role, how Codes are developed, and the differences between Codes and Standards.

     

    • Module 2- Overview of ASME Boiler and Pressure Vessel Code
      This module will describe the purpose of the ASME B&PV Code, explain the objectives and goals of the Code, describe its scope and organization, describe the publishing schedule for Editions and Addenda, and explain the purpose of Code Cases and Interpretations.

     

    • Module 3- Section III with Discussion of Sections II, V and IX
      This module will explain the purpose of Section III, as well as describe the organization of the section and major topics in the section. The basic design philosophy of the Section will be covered, along with the differences between the Code Classes (1, 2, 3, MC, CC, supports and core supports). The section will also cover the organization and scope of Subsection NCA and NB and describe the differences between Mandatory and Non-mandatory Appendices.

      The module will also introduce and discuss the elements of Sections II, V, and IX as they relate to Section III.

     

    • Module 4- Overview of In-service Inspection and Testing
      In this module the instructors will describe the reasons for In-service Inspection and Testing, explain the process for detection of degradation, describe the different types of testing, and explain the role of In-service Inspection and Testing in design.

     

    • Module 5- Overview of Section XI
      This module will discuss In-service Inspection of nuclear power plant vessels, piping, pumps, valves, and supports using nondestructive examination and how the results are evaluated. Discussion will also include repair, replacement, modification and maintenance as well as aging management.

      The module will focus on Division 1, covering the following Subsections:

    Subsection

    Topic

    Subsection IWA

    General Requirements

    Subsection IWB

    Class 1 Components

    Subsection IWC

    Class 2 Components

    Subsection IWD

    Class 3 Components

    Subsection IWE

    Class MC Metal Containment Vessels and Containment Penetrations Not Backed by Concrete, and Liners of Class CC Containment Vessels

    Subsection IWF

    Class 1, 2, 3, and MC Component Supports

    Subsection IWG

    Core Support Structures and Reactor Vessel Internal Structures

    Subsection IWL

    Concrete Containment Vessels

    Appendices:

    Mandatory (Roman numerals)

    Non-mandatory (Letters)

    Real World Application

    At the conclusion of the material for Modules 3 and 5 an exercise will be conducted to help solidify the students understanding of the Sections, requiring that they draw upon their knowledge of the Sections and their interrelation. The exercise will focus on how the students should apply the code and what considerations should be accounted for. The student will be placed in teams to perform the exercise. The instructors will actively engage the students during this time to facilitate their understanding of the Code.

    Course Completion

    Upon completion of the course material a comprehensive examination will be administered which will be used to verify the students understanding of the material and concepts. Following successful completion of the course, including passing the exam, individuals will receive an ASME Certificate of Completion. This course also provides 2.30 Continuing Education Units (CEUs). 

  • Technical Training Center

    The AREVA Technical Training Center is an advanced training center aimed at meeting the growing nuclear site maintenance needs in the United States.

    Located in Lynchburg, Virginia, AREVA's Technical Training Center extends over 3.5 acres, with classrooms, offices, and full-size mock-ups of steam generators, reactor vessels, and other major components of nuclear power plants. Technicians receive hands-on training for plant-specific configurations and new procedures in a safe, realistic environment that is more conducive to learning and sharing information.

    The facility also boasts a reactor pit filled with water and a fuel-handling crane for pressurized water reactors (PWR) and boiling water reactors (BWR). This equipment enables operator training in handling wet fuel.

    Along with its mission to train AREVA's American outage workers and employees, the Technical Training Center also provides training in American standards for AREVA technicians from France and Germany.

    Workforce development is another goal of the facility through its association with Central Virginia Community College, aiming to create a certified training degree program.

Upcoming Courses

Upcoming FIT Course Offerings

TH Reload Process Overview for CE and Westinghouse Plants

May 1, 2017
July 31, 2017
Lynchburg, VA

XCOBRA-IIIC Model Development

May 4-5, 2017
August 1-2, 2017
Lynchburg, VA

DNB FCM Analysis

May 8, 2017
August 3, 2017
Lynchburg, VA

Fuel Centerline Melt Limit and Limiting Axial

May 8, 2017
August 3, 2017
Lynchburg, VA

Statistical Setpoint Verification for CE Plants

May 15-16, 2017
August 7-8, 2017
Lynchburg, VA

Statistical Setpoint Verification for Westinghouse Plants

May 22-23, 2017
August 10-11, 2017
Lynchburg, VA

BW Fuel Reload Licensing Process - Overview

June 5-9, 2017
August 21-22, 2017
Lynchburg, VA

Critical Heat Flux

May 10, 2017
August 28, 2017
Lynchburg, VA

Form Loss Coefficients

May 10, 2017
August 28, 2017
Lynchburg, VA

COBRA-FLX™

May 11, 2017
August 31, 2017
Lynchburg, VA

Mixed Core Analysis with COBRA-FLX™

May 11, 2017
August 31, 2017
Lynchburg, VA

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Contact Us

Contact us for more information:

Fuel Training North America

Tel: 434.832.3150