skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: TWR Bench-Scale Steam Reforming Demonstration

Abstract

The Idaho Nuclear Technology and Engineering Center (INTEC) was home to nuclear fuel reprocessing activities for decades at the Idaho National Engineering and Environmental Laboratory. As a result of the reprocessing activities, INTEC has accumulated approximately one million gallons of acidic, radioactive, sodium-bearing waste (SBW). The purpose of this demonstration was to investigate a reforming technology, offered by ThermoChem Waste Remediation, LLC, (TWR) for treatment of SBW into a "road ready" waste form that would meet the waste acceptance criteria for the Waste Isolation Pilot Plant (WIPP). TWR is the licensee of Manufacturing Technology Conservation International (MTCI) steam-reforming technology in the field of radioactive waste treatment. A non-radioactive simulated SBW was used based on the known composition of waste tank WM-180 at INTEC. Rhenium was included as a non-radioactive surrogate for technetium. Data was collected to determine the nature and characteristics of the product, the operability of the technology, the composition of the off-gases, and the fate of key radionuclides (cesium and technetium) and volatile mercury compounds. The product contained a low fraction of elemental carbon residues in the cyclone and filter vessel catches. Mercury was quantitatively stripped from the product but cesium, rhenium (Tc surrogate), and the heavy metalsmore » were retained. Nitrate residues were about 400 ppm in the product and NOx destruction exceeded 86%. The demonstration was successful.« less

Authors:
;
Publication Date:
Research Org.:
Idaho National Laboratory (INL)
Sponsoring Org.:
DOE - EM
OSTI Identifier:
911430
Report Number(s):
INEEL/EXT-03-00436
TRN: US0704565
DOE Contract Number:  
DE-AC07-99ID-13727
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
12 - MGMT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES, 37 - INORGANIC, ORGANIC, PHYSICAL AND ANALYTICAL CHEMISTRY, 42 - ENGINEERING; CARBON; CESIUM; HEAVY METALS; MANUFACTURING; MERCURY; MERCURY COMPOUNDS; NITRATES; NUCLEAR FUELS; RADIOACTIVE WASTES; RADIOISOTOPES; REPROCESSING; RESIDUES; RHENIUM; STEAM; TANKS; TECHNETIUM; WASTE FORMS; WASTES; WIPP; acidic; nuclear fuel; off-gases; radioactive; radionuclides; reprocessing; sodium-bearing waste; steam-reforming

Citation Formats

D. W. Marshall, and N. R. Soelberg. TWR Bench-Scale Steam Reforming Demonstration. United States: N. p., 2003. Web. doi:10.2172/911430.
D. W. Marshall, & N. R. Soelberg. TWR Bench-Scale Steam Reforming Demonstration. United States. doi:10.2172/911430.
D. W. Marshall, and N. R. Soelberg. Thu . "TWR Bench-Scale Steam Reforming Demonstration". United States. doi:10.2172/911430. https://www.osti.gov/servlets/purl/911430.
@article{osti_911430,
title = {TWR Bench-Scale Steam Reforming Demonstration},
author = {D. W. Marshall and N. R. Soelberg},
abstractNote = {The Idaho Nuclear Technology and Engineering Center (INTEC) was home to nuclear fuel reprocessing activities for decades at the Idaho National Engineering and Environmental Laboratory. As a result of the reprocessing activities, INTEC has accumulated approximately one million gallons of acidic, radioactive, sodium-bearing waste (SBW). The purpose of this demonstration was to investigate a reforming technology, offered by ThermoChem Waste Remediation, LLC, (TWR) for treatment of SBW into a "road ready" waste form that would meet the waste acceptance criteria for the Waste Isolation Pilot Plant (WIPP). TWR is the licensee of Manufacturing Technology Conservation International (MTCI) steam-reforming technology in the field of radioactive waste treatment. A non-radioactive simulated SBW was used based on the known composition of waste tank WM-180 at INTEC. Rhenium was included as a non-radioactive surrogate for technetium. Data was collected to determine the nature and characteristics of the product, the operability of the technology, the composition of the off-gases, and the fate of key radionuclides (cesium and technetium) and volatile mercury compounds. The product contained a low fraction of elemental carbon residues in the cyclone and filter vessel catches. Mercury was quantitatively stripped from the product but cesium, rhenium (Tc surrogate), and the heavy metals were retained. Nitrate residues were about 400 ppm in the product and NOx destruction exceeded 86%. The demonstration was successful.},
doi = {10.2172/911430},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Thu May 01 00:00:00 EDT 2003},
month = {Thu May 01 00:00:00 EDT 2003}
}

Technical Report:

Save / Share: