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NDMAS_Pages_Home
Welcome to the Nuclear Data Management and Analysis System (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. To request access, click
here
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
.
See the list below for all program data currently available from NDMAS .
Accordion in HTML5
Advanced Reactor Technologies (ART) Gas Cooled Reactors (GCR) Program
Fuel Development and Qualification
Fuel Fabrication
AGR-1
AGR-2
AGR-3/4
AGR-5/6/7
Fuel Irradiation
AGR-1
AGR-2
AGR-3/4
AGR-5/6/7
Fuel Post-Irradiation Examination (PIE)
AGR-1
AGR-2
AGR-3/4
AGR-5/6/7
Graphite Technology Development
ATR Graphite R&D Program
-available without access permissions, all other data require permission.
Advanced Graphite Creep Experiments
AGC-1
Irradiation Monitoring
Exhaust Sweep Gas Cylinder Analysis
Physics Calculations
AGC-2
Irradiation Monitoring
Exhaust Sweep Gas Cylinder Analysis
Physics Calculations
AGC-3
Irradiation Monitoring
Exhaust Sweep Gas Cylinder Analysis
AGC-4
Irradiation Monitoring
HDG-1
Irradiation Monitoring
Material Properties
Baseline (Unirradiated)
AGC (Irradiated)
High Temperature Materials
Reactor Pressure Vessel
Steam Generator & Intermediate Heat Exchanger
Methods Experimental Validation
Organization for Economic Co-operation and Development, Loss of Forced Cooling tests- OECD LOFC
Natural convective shutdown heat removal test facility for reactor cavity cooling system concepts- NSTF RCCS
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
Advanced Test Reactor (ATR) Operations
U.S. High-Performance Research Reactor Fuel Qualification Program (USHPRR-FQ)
European Mini-Plate Irradiation Experiment (EMPIrE)
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