Applications

• Reactor Physics and Fuel Cycle Analysis
• Reactor Physics and Fuel Cycle Analysis codes

Capabilities

• Advanced Reactor Development
• Argonne Nuclear Data Program
  We contribute to the development of comprehensive nuclear reactions and nuclear structure databases, including nuclear data measurement, analysis, modeling and evaluation methodologies, that are implemented in basic science research and advanced nuclear technologies.
• Risk Methodology and Evaluation
• Facility Safety Assessment
• Nuclear Criticality Safety
• Nuclear Plant Dynamics and Safety
• Reactor Physics and Fuel Cycle Analysis

Programs

• Advanced Fuel Cycle Initiative (AFCI)
• Generation IV (Gen IV) Nuclear Energy Program
• Global Nuclear Energy Partnership (GNEP)
• Reduced Enrichment for Research and Test Reactors (RERTR)
• Materials Disposition (MD)
• Nuclear Criticality Safety

Facilities

• Computer Facilities (CF)

Other Resources / News Items

Publications

• Nuclear Data Measurement Reports series

Fact Sheets

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• Generation IV (Gen IV) Program  - Fact Sheet
  [  PDF, 74 KB]
• Nuclear Criticality Safety  - Fact Sheet
  [  PDF, 98 KB]
• Research and Test Reactor Conversion
  [  PDF, 94 KB]