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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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2027 ANS Winter Conference and Expo
October 31–November 4, 2027
Washington, DC|The Westin Washington, DC Downtown
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
Supreme Court rules against Texas in interim storage case
The Supreme Court voted 6–3 against Texas and a group of landowners today in a case involving the Nuclear Regulatory Commission’s licensing of a consolidated interim storage facility for spent nuclear fuel, reversing a decision by the 5th Circuit Court of Appeals to grant the state and landowners Fasken Land and Minerals (Fasken) standing to challenge the license.
Eberhard Schuster, Kurt A. Pflugrad
Nuclear Technology | Volume 86 | Number 2 | August 1989 | Pages 192-196
Technical Paper | Decontamination and Decommissioning / Radioactive Waste Management | doi.org/10.13182/NT89-A34270
Articles are hosted by Taylor and Francis Online.
Metal waste from nuclear power plants is normally contaminated with beta and gamma emitters mainly due to corrosion product radionuclides. Metal waste originating from reprocessing and fuel fabrication plants is contaminated only with alpha emitters (uranium). So far, only radionuclides that can be measured by gamma spectrometry can be quantified. The behavior of alpha emitters is investigated using an artificially added radionuclide in melt experiments. During its 1984–1988 program on decommissioning of nuclear installations, the Commission of the European Communities concluded a 2-yr research contract with Siemens AG, UB Kraftwerk Union on the behavior of radionuclides that are difficult to measure in the melting of steel. Investigation of the radionuclides 55Fe, 63Ni, and 90Sr began with melt experiments on 55Fe (considered an epsilon emitter) at laboratory scale, which showed that this nuclide is probably as homogeneously distributed in the melt as 60Co; thus, 60Co can be used as an isotopic indicator for 55Fe. In another melt experiment, 241Am was artificially added to metal waste and melted, showing a decontamination factor of ∼100 even with a very small quantity added (4 × 10−7 g 241Am). As of mid-1988, four melt experiments, each with different melt parameters, have been carried out. The last experiment relates to the melting of carbon steel with metallic uranium additions; although this experiment is not yet completely evaluated, problems related to the direct alpha measuring technique may arise from the disturbance of the radiochemical equilibrium of the uranium decay chain in the melt process.