Savannah River Site High Level Radioactive Waste Tank Sample Thermolytic Hydrogen Generation - 20346
- Savannah River National Laboratory, Savannah River Nuclear Solutions, Aiken, SC 29808 (United States)
To support the revision of flammability calculations and controls for the Savannah River Site (SRS) High-Level Radioactive Waste (HLW) tanks, Savannah River National Laboratory (SRNL) conducted laboratory measurements with the goal of quantifying hydrogen produced in HLW by non-radiolytic chemical reactions (i.e., thermolysis). Testing was performed with HLW tank supernate samples that represented a cross section of types of waste at SRS, including tanks that store typical evaporator concentrate, dissolved salt-cake, dilute recycle stream from the Defense Waste Processing Facility (DWPF), evaporator concentrate of the recycle stream from DWPF, fresh waste from the canyon separations facility, and waste that has been through salt processing cesium removal. Non-radioactive simulant testing included the classes of organic compounds historically introduced into the HLW tanks that were recently shown to be the most active toward the thermolytic generation of hydrogen. The reaction rate equations developed for thermolytic hydrogen generation from each class of organic compound showed direct proportionality to organic compound concentration and hydroxide concentration. Simulant testing identified that highly concentrated waste with high hydroxide concentration had the highest rates of thermolytic hydrogen generation. Using the radioactive tank sample thermolysis measurements at high temperatures and the mechanistic salt dependence of the simulant models, a global model was developed for tank waste thermolytic hydrogen generation as a function of total organic carbon content of SRS HLW. Through the primary functionality of the global model (organic carbon and free hydroxide concentration), the relative reactivity of the organic carbon in the waste was quantified. (authors)
- Research Organization:
- WM Symposia, Inc., PO Box 27646, 85285-7646 Tempe, AZ (United States)
- OSTI ID:
- 23030508
- Report Number(s):
- INIS-US-21-WM-20346; TRN: US21V1824070860
- Resource Relation:
- Conference: WM2020: 46. Annual Waste Management Conference, Phoenix, AZ (United States), 8-12 Mar 2020; Other Information: Country of input: France; 9 refs.; available online at: https://www.xcdsystem.com/wmsym/2020/index.html
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
CARBON
CESIUM
EVAPORATORS
FLAMMABILITY
HIGH-LEVEL RADIOACTIVE WASTES
HYDROGEN
HYDROXIDES
INTERSTITIAL HYDROGEN GENERATION
ORGANIC COMPOUNDS
RADIOACTIVE WASTE PROCESSING
RADIOLYSIS
REACTION KINETICS
REACTIVITY
SALTS
SAVANNAH RIVER PLANT
TANKS
TESTING