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2016 Winter Student Program Registration

You must first be registered for the meeting as an ANS National Student Member before registering for the Student Program

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I have read and understand the requirements of the Student Program *
Preferred Number of Work Assignments (2-3) *

Preferred Type of Work Assignment (check all that apply) *

Preferred Work Periods (check all that apply) *

Preferred Sessions (select two)

Monday, November 7, 2016

Advanced Gen IV Reactors
Student Design Competition
Overview and Purpose of the 52 Reactors that were Built at INL–Panel
Current Issues in Computational Methods–Roundtable
Nuclear Safety R&D at the Department of Energy—I
Nuclear Science User Facility: University Capabilities–Panel
Reactor Physics: General—I
Reactor Analysis Methods—I
Computational Thermal Hydraulics
In Memory of Salomon Levy on His Technical Contributions to the Advancements of Thermal Hydraulics–Panel &Technical Achievement Award Lecture–Panel
Roles of Regulatory Organizations–Panel
Yucca Mountain—Is There a Pulse–Panel
Used Fuel: Once Through or Recycle—Who is Right?–Panel

Tuesday, November 8, 2016

Intersection of Policy Development and Technical Innovation for Nuclear Nonproliferation and Security & Hybrid Energy Systems–Panel
Building a Nuclear Energy and Science Education Program: Successes and Challenges of Developing a Vision for Nuclear Energy Education–Panel
Novel Detection Methods & Accelerator Applications: General
Deterministic Transport Methods
Nuclear Safety R&D at the Department of Energy—II & Education, Training and Workforce Development
Advanced Manufacturing, Joining and Measurement Techniques & Nuclear Fuels and Materials: Modeling
Reactor Physics: General—II
Reactor Analysis Methods—II
Toward a Longer-Life Core: Thermal-Hydraulic Simulations and Experiments of Deformed Fuel Assemblies
Challenges in Computational Tools for Reactor Thermal Hydraulics–Panel
Human Factors, Instrumentation, and Controls: Instrumentation
International Activities on Used Nuclear Fuel Reprocessing Regulatory Framework–Panel
Used Nuclear Fuel Dry Storage Canister Inspection—I & Chemistry R&D in Radioactive Waste Management
Your Role in ANS National Committees–Panel & ANS Congressional Fellowship–Panel
Computational Tools for Radiation Protection and Shielding
Operations and Power: General—I
Challenges (Financial Challenge) with Current Operation Fleet–Panel
The Nuclear Energy Advanced Modeling and Simulation Program–Panel
Current Topics in Probabilistic Risk Analysis—I
Focus on Communications: Talking About Nuclear Waste—What Works and What Doesn’t—I–Panel & Focus on Communications: A Picture Really is Worth a Thousand Words—and People Pay Attention to Them—II–Panel
Reactor Physics: General—III & Reactor Analysis Methods—III
Data, Analysis and Operations in Nuclear Criticality Safety—I
Two-Phase Flows—I
General Thermal Hydraulics—I
Severe Accident Modeling and Experiments for Advanced Reactor Safety
Progress in DOE’s Fuel Cycle Technologies Program–Panel
Used Nuclear Fuel Dry Storage Canister Inspection—II
Potent Policies: Understanding ANS Position Papers–Panel
Updates from Ongoing U.S. Nuclear Decommissioning Projects: An Executive Leadership–Panel
HTR-Fuel Design and Fabrication
HTR-Materials—I
HTR-Fluid Dynamics Methods and Codes—I
HTR-Nuclear Data and Uncertainty
HTR-National Research Programs and Industrial Projects—I
HTR-Safety and Fuel Qualification
HTR-Materials—II
HTR-Fluid Dynamics Methods and Codes—II
HTR-Pebble Dynamics
HTR-National Research Programs and Industrial Projects—II
HTR-Fuel Irradiation
HTR-Materials—III
HTR-Heat Transfer Methods and Codes—I
HTR-Safety and Licensing—I
HTR-Hydrogen Production—I
HTR-Fuel Postirradiation Examination
HTR-Materials—IV
HTR-Heat Transfer Methods and Codes—II
HTR-Safety and Licensing—II
HTR-Hydrogen Production—II

Wednesday, November 9, 2016

Advanced Reactors–Panel & New Nuclear Constructions Around the World—Status Report–Panel
Nuclear Politics: Advocacy–Panel & Knowledge Transfer and Retention–Panel
Emerging Issues in Supply Chain–Panel
Computational Methods
Current Topics in Probabilistic Risk Analysis—II
Data, Analysis and Operations in Nuclear Criticality Safety–II
Reactor Physics: General—IV
Fast Reactors
Subchannel Thermal-Hydraulic Analysis—I
Large Eddy Simulation and Direct Numerical Simulation
Experimental Thermal Hydraulics—I
Advanced Aqueous Fuel Cycles—International Perspectives–Panel
Transition to a New Fuel Cycle—Needs and Challenges
Proposal Writing 101–Panel
Radiation Protection and Shielding: General
Research by U.S. DOE NEUP-Sponsored Students—I
Monte Carlo Methods
Nuclear Installations Safety: General—I
Recent Nuclear Criticality Safety Program Technical Accomplishments
Recent Physics: General—V
Reactor Analysis Methods—IV
Uncertainty, Scaling and Global Sensitivity Methods in Thermal Hydraulics
Young Professional Thermal-Hydraulics Research Competition—I
Human Factors, Instrumentation, and Controls: Human Factors, Safety, and Safety Systems
Fuel Cycle and Waste Management: General—I
Advances in Technical Nuclear Forensics: Methods and Analysis—I & Robotics and Remote Systems Topics
ANS Standards and You–Panel & Cutting Edge Technology in Education, Training and Distance Education
Operations and Power: General—II
Research by U.S. DOE NEUP-Sponsored Students—II
Decommissioning and Environmental Sciences: General
Mathematical Modeling
Nuclear Installations Safety: General—II
Critical and Subcritical Experiments
Reactor Physics: General—VI
Nuclear Fuels and Materials: Fast Reactors and Accident Tolerant Fuel
Two-Phase Flows—II
Young Professional Thermal-Hydraulics Research Competition—II
Biology and Medicine: General
Recent Development in Material Accountancy Techniques for Pyroprocessing Facilities
Advances in Technical Nuclear Forensics: Methods and Analysis—II
Student Conference Proposal Writing–Panel
HTR-Fuel PIE and Safety Testing
HTR-Materials—V
HTR-Natural and Mixed Convection—I
HTR-Reactor Physics Methods and Codes
HTR-Progress in New Generation Reactor Designs
HTR-Irradiation TRISO Microanalysis and Silver Retention
HTR-Materials—VI
HTR-Natural and Mixed Convection—II
HTR-Fuel/Core Design—I
HTR-Plant Dynamics and Control
HTR-Irradiation and PIE
HTR-Materials—VII
HTR-Structural Methods and Codes
HTR-Fuel/Core Design—II
HTR-System and Facility Design—I
HTR-Fuel Modeling and Simulation
HTR-Materials—VIII
HTR-Vessel Cooling
HTR-Transient and Accident Analysis Methods and Codes
HTR-System and Facility Design—II

Thursday, November 10, 2016

The Innovations in Fuel Cycle Research Awards Program
NRC Decommissioning Rulemaking: An Update on the Progress and Issues Coming out of the Rulemaking Process–Panel
Uncertainty Quantification and Sensitivity Analysis
Nuclear Installations Safety: General—III
ANS-8 Standards Forum & The Impact of Chemistry in Nuclear Criticality Safety Evaluations–Panel
Reactor Physics Design, Validation and Operational Experience—I
TREAT
Subchannel Thermal-Hydraulic Analysis—II & Thermal-Hydraulics of Severe Accidents
General Thermal Hydraulics—II
Experimental Thermal Hydraulics—II & Fusion Energy Technologies
Human Factors, Instrumentation, and Controls: Instrumentation and Control Systems
Fuel Cycle and Waste Management: General—II
Data Analysis and Operations in Nuclear Criticality Safety—III
Reactor Physics Design, Validation and Operational Experience—II
Radiation Protection and Shielding–Roundtable
HTR-Thermal Hydraulics of Key Components—I
HTR-Industrial Process Heat
HTR-Safety and Licensing—III
HTR-Multiphysics Methods and Codes—I
HTR-System and Facility Design—III
HTR-Thermal Hydraulics of Key Components—II
HTR-Fission and Activation Product Transport
HTR-Multiphysics Methods and Codes—II
HTR-Economic Assessment

Last updated July 28, 2016, 10:14am CDT.

 
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