# keywords[]
4019 Resources Engineering And Extractive Metallurgy

# keywords[]
4019 Resources Engineering And Extractive Metallurgy

# keywords[]
4019 Resources Engineering And Extractive Metallurgy

# keywords[]
4009 Electronics, Sensors And Digital Hardware

# keywords[]
4007 Control Engineering, Mechatronics And Robotics

# keywords[]
4019 Resources Engineering And Extractive Metallurgy

# educationAndTraining[].organization.label
University of Notre Dame - (Notre Dame, Indiana, United States)

# educationAndTraining[].organization.label
University of Illinois at Urbana Champaign - (Urbana, Illinois, United States)

# educationAndTraining[].organization.label
University of Illinois at Urbana Champaign - (Urbana, Illinois, United States)

# publications[].label
ANALYTICAL AND EXPERIMENTAL PERFORMANCE OF SPHERE-PAC NUCLEAR-FUELS

# publications[].label
Performance modeling for weapons MOX fuel ln light water reactors

# publications[].label
Advanced thermionic reactors for surface nuclear power applications

# publications[].publisher
American Institute of Aeronautics and Astronautics (AIAA)

# publications[].label
THERMOPLASTIC ANALYSIS OF A SPHERE-PAC FUEL PIN

# publications[].label
Reactor physics feasibility analysis of long-lived star-h2 system

# publications[].label
MATERIAL PROPERTY CORRELATIONS FOR URANIUM MONONITRIDE .3. TRANSPORT-PROPERTIES

# publications[].label
Appendix: Internet Sites on Nuclear Materials Safety Management, Environmental Safety and Health, Arms Control and Disarmament, Performance-Based Management, and Lessons Learned

# publications[].label
Effective thermal conductivity in multi-fraction reactor fuels.

# publications[].label
The systems engineering initiative - An innovative approach to experiential learning

# publications[].label
ELASTIC STRESS-STRAIN RELATION FOR RESTRUCTURING SPHERE-PAC FUEL.

# publications[].label
Sustainable nuclear power - The human dimension

# publications[].label
A MODEL FOR THE THERMAL-MECHANICAL BEHAVIOR OF MIXED-CARBIDE SPHERE-PAC FUEL-PINS

# publications[].label
Analysis of the modular helium reactor for a hydrogen production plant

# publications[].label
Gain-Scheduled Controller Design for Load-Following in Static Space Nuclear Power Systems

# publications[].label
A Model for Effective Thermal Conductivity of Unrestructured Sphere-Pac Fuel

# publications[].label
STATISTICAL SAMPLING OF RESPONSE SURFACES FOR DNBR ASSESSMENT.

# publications[].label
Outreach to stimulate interest in STEM education

# publications[].label
Summary of nuclear materials safety ARW in Amarillo and its relationship to this Workshop

# publications[].label
Fault-Tolerant Adaptive Control for Load-Following in Static Space Nuclear Power Systems

# publications[].label
MATERIAL PROPERTY CORRELATIONS FOR URANIUM MONONITRIDE .4. THERMODYNAMIC PROPERTIES

# publications[].label
The Master of Science Graduate Program in Nuclear Material Safe Management

# publications[].label
THE EFFECT OF ECCENTRICITY ON FISSION-GAS RELEASE IN SP-100 FUEL-PINS

# publications[].label
ICONE19-44136 REBIRTH OF AGN-201M : PRACTICAL WAYS OF USING THE PROVEN TRAINING REACTOR

# publications[].label
REVIEW OF THE EFFECTIVE THERMAL CONDUCTIVITY IN MULTI-FRACTION REACTOR FUELS.

# publications[].label
THE AXIAL SLIP BEHAVIOR OF A PARTICLE BED IN A CLAD TUBE

# publications[].label
Heat conduction in spheres packed in an infinite regular cubical array

# publications[].label
Design of an alternative coolant Inlet flow configuration for the modular helium reactor

# publications[].label
The Quality of Science and Engineering at the NNSA National Security Laboratories Introduction

# publications[].label
MATERIAL PROPERTY CORRELATIONS FOR URANIUM MONONITRIDE .2. MECHANICAL-PROPERTIES

# publications[].label
ELASTIC STRESS-STRAIN RELATION FOR SPHERE ARRAYS UNDERGOING INITIAL STAGE SINTERING.

# publications[].label
TRANSIENT FUEL PIN TEMPERATURE CALCULATIONS USING DESCRIBING FUNCTIONS.

# publications[].label
Radiation response of FeCrAl-coated Zircaloy-4

# publications[].label
Ion cutting of amorphous metals by using helium ion implantation

# publications[].label
Protocol of the Nato Advanced Research Workshop on Nuclear Materials Safety Management

# publications[].label
The Effect of Internal Free Surfaces on Void Swelling of Irradiated Pure Iron Containing Subsurface Trenches

# publications[].label
Re-Assessment of Nitride Fuel Potential in the Current Context of the Nuclear Industry

# publications[].label
RESEARCH IN NUCLEAR-POWER - WORKSHOP ON THE NEEDS OF THE NEXT GENERATION OF NUCLEAR-POWER TECHNOLOGY - EXECUTIVE SUMMARY

# publications[].label
THE STEADY-STATE SELF-INITIALIZATION CAPABILITY OF THE FREY TRANSIENT FUEL CODE

# publications[].label
THERMOPHYSICAL PROPERTY CORRELATIONS FOR THE NIOBIUM-1-PERCENT ZIRCONIUM ALLOY

# publications[].label
CHARACTERISTICS OF SOLID LIQUID FLOW IN A 2-IN PIPE

# publications[].label
Utilization of Plutonium and Higher Actinides in the HTGR as Possibility to Maintain Long-Term Operation on One Fuel Loading

# publications[].label
Reducing nuclear danger through intergovernmental technical exchanges on nuclear materials safety management

# publications[].label
NUCLEAR-FUELS AND MATERIALS AT TEXAS-A+M, OR AGGIES - FISSILE, FERTILE, AND FUTILE

# publications[].label
ICONE11-36576 STAR-H2 : A 400 MWTH LEAD-COOLED, LONG REFUELING INTERVAL REACTOR FOR HYDROGEN PRODUCTION

# publications[].label
Fault-tolerant adaptive control for load-following in static space nuclear power systems

# publications[].label
STAR-H2: The Secure Transportable Autonomous Reactor for Hydrogen Production and Desalinization

# publications[].label
NASA UNIVERSITIES ADVANCED NUCLEAR DESIGN PROJECT STUDIES

# publications[].label
DEVELOPMENT OF A CREEP RATE POROSITY CORRECTION FACTOR

# publications[].label
EFFECTS OF HYDROGEN ON THE FRACTURE MORPHOLOGY OF INCONEL 718

# publications[].label
PERFORMANCE IMPLICATIONS OF PARTICLE SIZES FOR SPHERE-PAC NUCLEAR-FUELS

# publications[].label
Helium retention, bubble superlattice formation and surface blistering in helium-irradiated tungsten

# publications[].label
New ways of implementing the AGN-201M training nuclear reactor in nuclear engineering curricula

# publications[].label
A PRELIMINARY FEASIBILITY STUDY OF PASSIVE IN-CORE THERMIONIC REACTORS FOR HIGHLY COMPACT SPACE NUCLEAR-POWER SYSTEMS

# publications[].label
TRANSIENT FUEL PIN TEMPERATURE CALCULATIONS USING DESCRIBING FUNCTIONS.

# publications[].label
Power Engineering Technology: A New Program Targeted At The Nuclear Power Industry

# publications[].publisher
American Society for Engineering Education

# publications[].label
STAR-H2: Materials, safety, non-proliferation and ultra long operation

# publications[].label
APPLICATION OF THE FREY TRANSIENT FUEL CODE FOR DESIGN-BASIS EVENTS

# publications[].label
MATERIAL PROPERTY CORRELATIONS FOR URANIUM MONONITRIDE .1. PHYSICAL-PROPERTIES

# publications[].label
CURRENT TRENDS IN FUEL DEVELOPMENT AND FUTURE-NEEDS IN EXTENDED BURNUP

# publications[].label
AN ELASTIC STRESS-STRAIN RELATION FOR SPHERE ARRAYS UNDERGOING INITIAL-STAGE SINTERING

# publications[].label
Workshop Summary and Wrap-Up: Panel and Participant Discussions

# publications[].label
HIGH-FIBER VOLUME FRACTION METAL-MATRIX COMPOSITES CAST UNDER BI-DIMENSIONAL COMPRESSION

# publications[].label
GENERATION OF TIME-DEPENDENT NEUTRON-TRANSPORT SOLUTIONS IN INFINITE MEDIA

# publications[].label
Thermal Performance Modeling of Sphere-Pac Mixed Carbide Fast Reactor Fuel

# publications[].label
Autonomous multi-purpose floating power system with a compact static pebble bed reactor

# publications[].label
VALIDATION OF FREY FOR THE SAFETY ANALYSIS OF LWR FUEL USING TRANSIENT FUEL-ROD EXPERIMENTS

# publications[].label
3.8 Statistical Sampling of Response Surfaces for DNBR Assessment

# publications[].label
Analysis of new challenges in non-proliferation education

# publications[].label
ANALYTICAL STUDY OF HEAT CONDUCTION IN FUEL PINS WITH AN ECCENTRICALLY PLACED PELLET.

# publications[].label
PREDICTION OF TRANSIENT FUEL BEHAVIOR WITH THE FREY CODE

# publications[].label
ASSESSMENT OF FREY CODE PREDICTIONS OF STEADY-STATE PIN DEFORMATION

# publications[].label
The Quality of Science and Engineering at the NNSA National Security Laboratories Summary

# publications[].label
Effective Thermal Conductivity of Sphere-Pac Fuel During Restructuring

# publications[].label
FUEL CLADDING THERMAL CONDUCTANCE FOR SPHERE-PAC MIXED CARBIDE FUEL

# publications[].label
TRANSPORT PROPERTY CORRELATIONS FOR THE NIOBIUM-1-PERCENT ZIRCONIUM ALLOY

# publications[].label
An Improved Finite Difference Method to Evaluate Heat Transfer in Fuel Pins with Eccentrically Placed Pellets

# publications[].label
Educating the nuclear workforce of the future in Texas

# publications[].label
Experiences with International Collaborations in Nuclear Engineering Research and Educational Exchanges-Panel

# publications[].label
The Nuclear Power Institute Programs for Human Resource Development for the Nuclear Industry

# streetAddress
Texas A&M University; Nuclear Engineering; 3475 TAMU