Radionuclide Characterization of Reactor Decommissioning Waste and Spent Fuel Assembly Flardware

Technical Report · Mon Dec 31 23:00:00 EST 1990

DOI:https://doi.org/10.2172/6340508· OSTI ID:6340508

Robertson, D. E. ^[1]; Thomas, C. W. ^[1]; Wynhoff, N. L. ^[1]; Hetzer, D. C. ^[1]

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1. Pacific Northwest National Laboratory (PNNL), Richland, WA (United States)

This study is providing the NRC and licensees with a more comprehensive and defensible data base and 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 a two-phase sampling, measurement, and assessment program involving the actual decommissioning of Shippingport Station and the detailed analysis of neutron-activated materials from commercial reactors. Radiological characterization studies at Shippingport have shown that neutron activation products, dominated by ⁶⁰Co, comprised the residual radionuclide inventory. Fission products and transuranic radionuclides were essentially absent. Waste classification assessments have shown that all decommissioning materials (except reactor pressure vessel internals) could be disposed of as Class A waste. Measurements and assessments of spent fuel assembly hardware have shown that ⁶³Ni, ⁵⁹Ni, and ⁹⁴Nb sometimes greatly exceed the 10CFR61 Class C limit for some components, and thus would require disposal in a high level waste repository. These measurements are providing the basis for an assessment of the disposal options for these types of highly radioactive materials. Comparisons of predicted (calculated) activation product concentrations with the empirical data are providing as assessment of the accuracy of calculational methods. Work is continuing on radiological characterization of spent PWR and BWR control rod assemblies. Additional work is planned on current issues/problems relating to reactor decommissioning. These efforts will be reported on in future supplements to this report.

• Research Organization: US Nuclear Regulatory Commission (NRC), Washington, DC (United States). Office of Nuclear Regulatory Research; Pacific Northwest National Laboratory (PNNL), Richland, WA (United States)
• Sponsoring Organization: USNRC; USDOE
• DOE Contract Number: AC06-76RL01830
• OSTI ID: 6340508
• Report Number(s): NUREG/CR--5343; PNL--6806; ON: TI91007071
• Country of Publication: United States
• Language: English

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