Subcommittee C26.13 on Spent Fuel and High Level Waste

Matching Standards Under the Jurisdiction of C26.13 by Status

C1174-20 Standard Guide for Evaluation of Long-Term Behavior of Materials Used in Engineered Barrier Systems (EBS) for Geological Disposal of High-Level Radioactive Waste
C1220-21 Standard Test Method for Static Leaching of Monolithic Waste Forms for Disposal of Radioactive Waste
C1285-21 Standard Test Methods for Determining Chemical Durability of Nuclear, Hazardous, and Mixed Waste Glasses and Multiphase Glass Ceramics: The Product Consistency Test (PCT)
C1308-21 Standard Test Method for Accelerated Leach Test for Measuring Contaminant Releases From Solidified Waste
C1431-99(2018) Standard Guide for Corrosion Testing of Aluminum-Based Spent Nuclear Fuel in Support of Repository Disposal
C1553-21 Standard Guide for Drying of Spent Nuclear Fuel
C1562-10(2018) Standard Guide for Evaluation of Materials Used in Extended Service of Interim Spent Nuclear Fuel Dry Storage Systems
-See also WK82543 proposed Revision
C1662-24e1 Standard Test Method for Measurement of the Dissolution Rate of Nuclear Waste Forms Using the Single-Pass Flow-Through Test Method
C1663-24 Standard Test Method for Measuring Waste Glass or Glass Ceramic Durability by Vapor Hydration Test
C1682-21 Standard Guide for Characterization of Spent Nuclear Fuel in Support of Interim Storage, Transportation and Geologic Repository Disposal
C1720-21 Standard Test Methods for Determining Liquidus Temperature of Waste Glasses and Simulated Waste Glasses
-See also WK90679 proposed Revision
C1733-21 Standard Test Method for Distribution Coefficients of Inorganic Species by Batch Method
C1750-21 Standard Guide for Development, Verification, Validation, and Documentation of Simulants for Hazardous Materials and Process Streams
C1751-21 Standard Guide for Sampling Radioactive Tank Waste
C1752-21 Standard Guide for Measuring Physical and Rheological Properties of Radioactive Solutions, Slurries, and Sludges
C1926-24 Standard Test Method for Measurement of Glass Dissolution Rate Using Stirred Dilute Reactor Conditions on Monolithic Samples
E2230-22 Standard Practice for Thermal Qualification of Type B Packages for Radioactive Material

WK73487 the Support Waste from Lysimeter Testing
WK76034 the recommendation of specific test methods and conditions to support application of C1174 approach for glass/glass-ceramic waste form materials
WK91221 Measurement of Viscosity of a Molten Salt using a Rotational Viscometer
WK81783 Nuclear Waste Glass Static Dissolution Testing to Determine Stage III Rates
WK90455 Identifying Tests (and Test Variants) to Study Multiphase Waste Forms

Subcommittee C26.13 on Spent Fuel and High Level Waste

Matching Standards Under the Jurisdiction of C26.13 by Status

Active17 matching standards

Proposed New5 matching standards

Withdrawn, Replaced6 matching standards

Matching Standards Under the Jurisdiction of C26.13 by Status

Active17 matching standards

Proposed New5 matching standards

Withdrawn, Replaced6 matching standards