Nuclear Data Management and Analysis System (NDMAS)
NDMAS Portal
NDMAS comprises databases, a team of data scientists, and web-based tools for analysis and display of data from INL’s nuclear fuel and materials research programs.
Access to NDMAS from outside INL is provided on a per-project basis, by permission of the relevant managers. Click here to request access, and include in the body of the email which program data you would like access to.
If you have an NDMAS account and have forgotten your password but remember your security picture and word, you can use the INL Self Service site to reset your password.
For the NDMAS login/access procedure click here.
NDMAS Programs and Experiments Supporting
Advanced Test Reactor (ATR)
Operational Data
Power
- Lobe
- Quadrant
- Core
Positions
- Control Rod Depth
- Control Cylinder
- Shims
Advanced Reactor Technologies - Gas Cooled Reactors (ART-GCR)
AGR TRISO Fuel Qualification
Advanced Gas Reactor (AGR) Tristructural isotropic (TRISO) Fuel Development and Qualification Program (currently with AFC)
Experiments
- AGR-1
- AGR-2
- AGR-2/4
- AGR-5/6/7
Data
- Fuel Fabrication
- Irradiation monitoring
- Post-irradiation examination (PIE) and Safety Tests
Graphite Technology Development
Experiments
- Baseline
- AGC-1
- AGC-2
- AGC-3
- AGC-4
- HDG-1
Data
- As-fabricated
- Irradiation monitoring (near real-time for HDG-1)
- Post-irradiation examination (PIE)
- Characterization
High Temperature Metals
- A508/A533 Steels
- Inconel 617
- Alloy 800H
- Alloy 709
Design, Methods, and Validation
- Organization for Economic Co-operation and Development, Loss of Forced Cooling tests, performed at Japan Atomic Energy Agency High Temperature Test Reactor (OECD LOFC at HTTR)
- Argonne National Laboratory Natural convective Shutdown heat removal Test Facility for Reactor Cavity Cooling System concepts (NSTF RCCS)
Advanced Fuels Campaign (AFC)
Accident Tolerant Fuels (ATF)
Experiments and Sub-programs
- ATF-1
- ATF-2
- Westinghouse
- GE
- Framatome
- Byron Fuel Shipment
Data
- As-built fuel pin dimensions
- Power histories
- Post-irradiation examination (PIE) and Safety Tests
- Water Loop Cycle data
Next Generation Fuels (NGF)
Advanced Gas Reactor (AGR) Tristructural isotropic (TRISO) Fuel Development and Qualification Program (previously with ART-GCR)
Experiments
- AGR-1
- AGR-2
- AGR-2/4
- AGR-5/6/7
Data
- Fuel Fabrication
- Irradiation monitoring
- Post-irradiation examination (PIE) and Safety Tests
Metallic Fuel Research and Development
National Nuclear Security Administration Tritium Readiness Subprogram
Tritium Technology Program
Tritium-producing burnable absorber rod (TPBAR) Materials Irradiation Separate effects Test (TMIST)
- TMIST-3A
- TMIST-3B
Additional Programs
- US High-Performance Research Reactor Fuel Qualification Program (US HPRR-FQ)
- European Mini-plate Irradiation Experiment (EMPIRE)
- Molten Chloride Reactor Experiment (MCRE)
- X-Energy Pebble Reactor Test (XPeRT)
- BWXT Advanced Nuclear Reactor (BANR) Experiment
Contact Information
Nuclear Data Management and Analysis System
