Published 1977 | Version v1
Report Open

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)

MF available from INIS under the Report Number.

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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.