Waste management implications of irradiated nuclear fuel storage
- 1. United Nuclear Industries, Inc., Richland, Wash. (USA)
Description
Irradiated nuclear fuel is stored underwater in large recirculating basins prior to reprocessing in chemical separations plants. A small number of the fuel rods contain minor defects which allow fission products to seep into the basin water. The predominant radionuclides leached into the water are dependent upon the decay time after removal from the reactor. Freshly discharged fuel releases short half-lived radioiodine which presents exposure and airborne release problems on a short-term basis but does not impose significant long-term waste management problems. After a reasonable decay period, the major radionuclides present are 137Cs, 144Ce, 90Sr, 3H, and 239/240 Pu. Each of the radionuclides imposes specific waste management problems which require individual consideration in their control, packaging and shipment, and permanent disposal. These considerations are reviewed in this paper for general industry practices and specific illustrative examples are presented. Control of radionuclide concentrations and water purity are normally achieved by filtration and ion exchange treatment. Cartridge-type filters are the most common but improved filtration techniques that minimize personnel exposure, particularly during filter replacements, are now being adopted. Mixed bed ion exchange resins are most commonly utilized for soluble radionuclide removal, particularly for basins filled with demineralized water. Cesium-specific exchange media are employed at basins where demineralized water is not employed; these media operate for very long periods of time since they are not depleted by the normal dissolved non-radioactive water impurities. The resins are either buried when depleted or regenerated and the regeneration solutions concentrated for burial. Resin run lengths are usually determined by ionic or radiochemical depletion of the resin or in some cases by limiting radionuclide concentrations specified by shipping regulations or established ion column dose rates. While not commonly recognized, it is possible to exceed 10 nanocuries total plutonium per gram which by regulation would require retrievable storage at the burial site
Availability note (English)
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8303833.pdf
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Additional details
Additional titles
- Augmented title (English)
- Sources and amounts of radioactivity in spent-fuel storage basins, current methods of controlling the activity at manageable levels and the amounts of waste generated
Publishing Information
- Imprint Pagination
- 8 p.
- Report number
- IAEA-CN--36/23
Conference
- Title
- International conference on nuclear power and its fuel cycles.
- Dates
- 2 - 13 May 1977.
- Place
- Salzburg, Austria.
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 8303833
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FILTRATION; ION EXCHANGE; RADIOACTIVE WASTES; RADIOACTIVITY; SPENT FUEL STORAGE; WASTE MANAGEMENT
- Descriptors DEC
- MANAGEMENT; RADIOACTIVE MATERIALS; SEPARATION PROCESSES; STORAGE; WASTES
Optional Information
- Notes
- 3.2.-.T.2./06 3 tables, 1 fig.