Tritium waste control: October--March 1979

Technical Report · Thu Jun 07 04:00:00 EDT 1979

DOI:https://doi.org/10.2172/6206360· OSTI ID:6206360

Shumay, Jr, W C ^[1]

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1. ed.

Progress is reported in the following areas: catalytic exchange detritiation studies, electrolysis of tritiated water, effect of tritium radiation on Pt--C--Teflon catalysts, gas generation measurements on tritiated waste materials, fixation of aqueous tritiated waste in polymer impregnated concrete, and management of high specific activity liquid wastes. (DLC)

• Research Organization: Mound Facility, Miamisburg, OH (USA)
• DOE Contract Number: EY-76-C-04-0053
• OSTI ID: 6206360
• Report Number(s): MLM-2620
• Country of Publication: United States
• Language: English

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12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BUILDING MATERIALS
CATALYSTS
CHEMICAL RADIATION EFFECTS
CHEMICAL REACTIONS
CHEMISTRY
CONCRETES
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DATA FORMS
DECOMPOSITION
DEGASSING
EXPERIMENTAL DATA
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HYDROGEN COMPOUNDS
HYDROGEN ISOTOPES
IMPREGNATION
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LABELLED COMPOUNDS
LIGHT NUCLEI
LIQUID WASTES
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NUCLEI
NUMERICAL DATA
ODD-EVEN NUCLEI
OXYGEN COMPOUNDS
PHASE TRANSFORMATIONS
POLYMERS
PROCESSING
RADIATION CHEMISTRY
RADIATION EFFECTS
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RADIOISOTOPES
RADIOLYSIS
RESEARCH PROGRAMS
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WASTE MANAGEMENT
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WASTES
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