Aging effects on curium-doped titanate ceramic containing sodium-bearing high-level nuclear waste
Creators
- 1. Dept. of Environmental Safety Research, Japan Atomic Energy Research Inst. (Japan)
- 2. Dept. of Hot Lab., Japan Atomic Energy Research Inst. (Japan)
- 3. Advanced Materials Program, Australian Nuclear Science and Technology Organization, Lucas Heights Research Lab., Lucas Heights, N.S.W. (Australia)
- 4. Chiyoda Maintenance Ltd. (Japan)
- 5. Univ. of Queensland (Australia)
Description
This paper reports that curium-doped titanate ceramic containing sodium-rich high-level nuclear waste showed a gradual decrease in density up to a dose of 8.5 x 1017 α decays · g-1. After that, the rate of density change increased apparently because of crack formation. Optical microscopy showed cracks >0.1 mm long and >1 μm wide after a dose of 7.9 x 1017 α decays · g-1. Leach tests suggested that the dissolution-control phases for sodium and cesium changed from freudenbergite and hollandite, respectively, to intergranular phases after significant cracking. Aging also enhanced strontium losses, relative to calcium, indicating that strontium may also be partitioned to the intergranular phases. After the fresh surfaces produced by cracking were exposed to leachant, and the dissolution of soluble intergranular surfaces was complete, the leaching of nonradioactive elements from the samples having a dose of 12.3 x 1017 α decays · g-1 was limited by the following dissolution-control phases: freudenbergite (Na), hollandite (Cs and Ba), perovskite and/or zirconolite (Sr and Ca), and alloys (Mo)
Additional details
Publishing Information
- Journal Title
- Journal of the American Ceramic Society
- Journal Volume
- 75
- Journal Issue
- 2
- Series
- J. Am. Ceram. Soc.
- Journal Page Range
- 392-400
- ISSN
- 0002-7820
- CODEN
- JACTA
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 23068223
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S36: MATERIALS SCIENCE; S36: MATERIALS SCIENCE;
- Descriptors DEI
- AGING; CESIUM; CHEMICAL REACTION KINETICS; CRACK PROPAGATION; CURIUM ADDITIONS; DENSITY; DISSOLUTION; HIGH-LEVEL RADIOACTIVE WASTES; IRRADIATION; LEACHING; MATERIALS TESTING; OPTICAL MICROSCOPY; PHASE STUDIES; PHYSICAL RADIATION EFFECTS; RADIOACTIVE WASTE FACILITIES; SODIUM; TITANIUM OXIDES
- Descriptors DEC
- ALKALI METALS; CHALCOGENIDES; ELEMENTS; KINETICS; MATERIALS; METALS; MICROSCOPY; NUCLEAR FACILITIES; OXIDES; OXYGEN COMPOUNDS; PHYSICAL PROPERTIES; RADIATION EFFECTS; RADIOACTIVE MATERIALS; RADIOACTIVE WASTES; REACTION KINETICS; SEPARATION PROCESSES; TESTING; TITANIUM COMPOUNDS; TRANSITION ELEMENT COMPOUNDS; WASTES