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SCALE 6 Tutorial
Presented by Oak Ridge National Laboratory
Thursday 1:00pm-4:00pm, Reitz Union Room 349
The Triton sequence of the SCALE system combines deterministic and Monte Carlo capabilities into a multipurpose transport analysis tool. SCALE can be used to perform automated cross-section processing and execution of two-dimensional NEWT transport calculations. NEWT is an arbitrary-geometry, discrete ordinates transport solver within SCALE that can be used for eigenvalue calculations, critical buckling searches, forward and adjoint flux solutions, cross-section weighting, collapse, and homogenization, and can be used to generate few-group constants for lattice physics calculations. Coupled with ORIGEN-S via Triton , NEWT is most often used in 2-D depletion calculations. Such calculations can be used to calculate isotopic concentrations as a function of burnup, decay heat, neutron and gamma, source terms, radiotoxicity and dose estimates. Used in lattice physics calculations, Triton can be used to perform transport branch calculations at each depletion step, and to save lattice physics cross sections and other physics parameters for use in subsequent analysis. NEWT's arbitrary-geometry capability lends it to a wide variety of lattice analyses, including but not limited to PWR, BWR with control blades, VVER, and CANDU and ACR-700 designs. Experienced Keno-VI users will find that because NEWT geometry input is based on that of KENO-VI, exchanging (2-D) models between the two codes is trivial. However, for some inherently three-dimensional configurations, the 2-D solution of NEWT is inadequate; in such cases, the alternative is to use Triton with Keno V.a or Keno-VI as the transport solver, to accommodate 3-D depletion.
This workshop will provide an overview of the lattice physics capabilities of SCALE within the Triton sequence and will include hands-on exercises using SCALE on laptop computers. Laptops will also be provided, but participants are encouraged to bring their own laptops with SCALE 6 already installed.
The workshop topics will include NEWT capabilities, Triton-based depletion calculations with both NEWT and Keno-VI, and lattice physics options within Triton. Ongoing application of Triton in HTGR analysis will also be presented. The workshop will be led by Dr. Mark DeHart of Oak Ridge National Laboratory.
Students who wish to use their personal laptops for the workshop MUST obtain the SCALE 6 code in advance from RSICC or OECD/NEA.
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Nuclear Political Advocacy and Outreach
Presented by Nuclear Energy Institute
Thursday 2:00pm-4:00pm, Reitz Union Room 282
NEI and ANS policy individuals will present a workshop on nuclear advocacy, and how students can engage themselves politically in their local communities and on the national level to promote nuclear energy and use their voice democratically.
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MCNPX Burnup Tutorial
Presented by Los Alamos National Laboratory
Friday 9:00am-3:00pm, Reitz Union Room 349
The Monte Carlo burnup tutorial session lets participants set up and execute Monte Carlo-linked depletion calculations with MCNPX. It is intended for those who are familiar with MCNPX and similar codes. The tutorial is a 3-hour hands-on session using a few provided laptop computers and the participants’ personal computers. Simple problems are described that enable the user to become confident in setting up and executing depletion calculations with the MCNPX depletion capability. Topics include approaches to basic problem set-up, criticality calculations, isotope tracking, repeated structures in burnup, manual concentration changes, and transitioning burnup output for fixed source detector calculations. Previous Monte Carlo Burnup tutorials provided at the ANS 2007, ANS 2008, and ICRS 2008 meetings were popular and successful. The Monte Carlo burnup tutorial provides the opportunity to become acquainted with the Monte Carlo-linked depletion capabilities and recent MCNPX enhancements by actually setting up and running illustrative problems.
Students who wish to use their personal laptops for the workshop MUST obtain the MCNPX code in advance from RSICC or OECD/NEA.
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Workshop on Irradiation Planning and Testing
Presented by Advanced Test Reactor National Scientific User Facility
Friday 3:00pm-5:00pm, Reitz Union Room 349
A workshop on the basics, problems, and solutions of executing and planning of irradiation experiments. The workshop will provide an appreciation of the process by which irradiation experiments are planned and executed.
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Career, Intern and Fellowship Opportunities in the Naval Reactors Program
Presented by Knolls Atomic Power Laboratory, Bettis Atomic Power Laboratory and
Bechtel Plant Marchinery, Inc.
Saturday 9:00am-12:00pm, Reitz Union Room 349
A one-hour presentation detailing the types of nuclear engineering and methods development projects available for those who choose a career with the NR program.
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Design and Simulation of Advanced Fast Reactors and Fuel Recycling Technologies
Presented by Argonne National Laboratory
Saturday 1:00pm-4:00pm, Reitz Union Room 349
Argonne National Laboratory has performed cutting-edge fast reactor research for over 50 years and continues that tradition today with numerous programs, including work advancing the Advanced Fuel Cycle Initiative. The workshop will provide an introduction to fast reactor and fuel cycle technologies and the simulations methods used to support the design and safety analysis of these systems. The workshop will consist of a series of focused-topic sessions featuring lectures and discussions lead by prominent Argonne fast reactor researchers, providing workshop participants an opportunity to develop a basic understanding of fast reactors and their role in the nuclear power industry in the 21st century.
Agenda:
1:00 Motivation for Fuel Recycling and the Role of Fast Reactors
1:15 Introduction to Fuel Recycling Technology and Simulations
2:00 Introduction to Fast Reactor Design and Core Physics Simulation
2:45 Introduction to Fast Reactor Thermal Hydraulics and Safety Analysis
3:45 A Look to the Future and Wrap-Up
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