Radionuclide characterization of reactor decommissioning waste and neutron-activated metals
This study is providing the NRC and licensees with a more comprehensive data base for regulatory assessment of the radiological factors associated with reactor decommissioning and disposal of wastes generated during these activities. The objectives of this study are being accomplished during the actual decommissioning of Shippingport Station and the detailed analysis of neutron-activated materials from commercial reactors. The radiological characterization studies of Shippingport decommissioning materials have now been completed, and analyses of dismantled piping and scabbled concrete have shown that neutron activation products, dominated by {sup 60}Co, comprised the residual radionuclide inventory. Waste classification assessment have shown that all decommissioning materials (except reactor pressure vessel internals) could be disposed of as Class A waste. Spent fuel disassembly hardware from the Shippingport Core-3 was analyzed for long-lived activation products. {sup 94}Nb and {sup 63}Ni concentrations in Inconel-X750 and stainless steel components exceeded their Class C limits. Measurements and assessments of {sup 14}C in spent fuel disassembly hardware from three commercial nuclear power stations showed that this radionuclide never exceeded the Class C limit for all components. However, the {sup 63}Ni and {sup 94}Nb concentrations in some of these materials did exceed the Class C limits. These measurements are providing the basis for an assessment of the disposal options for these types of highly radioactive materials. Work is continuing on radiological characterization of spent PWR and BWR control rod assemblies. Three control rods, including a BWR cruciform control rod blade, a PWR control rod cluster assembly, and a PWR burnable poison rod assembly, have been characterized for their long-lived activation product concentrations and distribution by direct assay methods. These spent control rods could all be classified as Class C low-level waste.
- Research Organization:
- Pacific Northwest Lab., Richland, WA (United States)
- Sponsoring Organization:
- Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- AC06-76RL01830
- OSTI ID:
- 10170334
- Report Number(s):
- NUREG/CR-5894; PNL-8106; ON: TI93016280; TRN: 93:016535
- Resource Relation:
- Other Information: PBD: Jun 1993
- Country of Publication:
- United States
- Language:
- English
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Radionuclide characterization of reactor decommissioning waste and spent fuel assembly hardware
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
SHIPPINGPORT REACTOR
DECOMMISSIONING
PWR TYPE REACTORS
BWR TYPE REACTORS
LWBR TYPE REACTORS
RADIOACTIVE WASTE DISPOSAL
PLANNING
RADIOACTIVE WASTES
RADIOASSAY
COBALT 60
SPENT FUELS
NIOBIUM 94
NICKEL 63
CARBON 14
CONTROL ELEMENTS
LOW-LEVEL RADIOACTIVE WASTES
CONCRETES
INCONEL ALLOYS
STAINLESS STEELS
PIPES
CONTAMINATION REGULATIONS
US NRC
SAMPLING
QUALITATIVE CHEMICAL ANALYSIS
GAMMA SPECTROSCOPY
COOPER REACTOR
POINT BEACH-1 REACTOR
CALVERT CLIFFS-1 REACTOR
IRON 53
SILVER 108
SILVER 110
EXPERIMENTAL DATA
220900
210100
210200
210500
052002
REACTOR SAFETY
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
BOILING WATER COOLED
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED
POWER REACTORS
BREEDING
WASTE DISPOSAL AND STORAGE