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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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
Four million nuclear jobs by 2050: Who will do them?
Industry leaders from around the globe met this month to discuss the talent development that will be necessary for the long-term success of the nuclear industry.
The International Conference on Nuclear Knowledge Management and Human Resources Development, hosted by the International Atomic Energy Agency, was held in Vienna earlier this month. Discussed there was the agency’s forecast for nuclear capacity to more than double—or hopefully triple—by 2050 and the requirement of more than four million professionals to support the industry.
Clay M. Davis
Nuclear Technology | Volume 87 | Number 4 | December 1989 | Pages 778-785
Technical Paper | TMI-2: Decontamination and Waste Management / Nuclear Safety | doi.org/10.13182/NT89-A27671
Articles are hosted by Taylor and Francis Online.
The March 28, 1979, loss-of-coolant accident at Three Mile Island Unit 2 resulted in the exposure of ∼3000 m2 of reactor building (RB) internal concrete surfaces to both liquid- and vapor-borne contaminants. The period of contact between these surfaces and aqueous solutions of mixed fission products ranged from a few days to several years. At the completion of gross decontamination of the accessible elevations of the RB in 1982 by water flushing, high-pressure spraying, strippable coating application, and hands-on wiping, dose rates remained above expected levels. Surveys and limited surface sampling indicated that contaminants had penetrated the protective coatings on the structural concrete, creating a substantial fixed source. To assess the depth of contaminant penetration into the concrete, a sampling program was conducted in September 1983. Based on the results of this program, it was determined that where coatings were intact, penetration past the matrix of the coating was insignificant. Where the coatings had been damaged prior to the accident, however, penetrations into the concrete were observed up to 20 mm. Subsequent modeling using the ISOSHLD II code using these values indicated that between 23 and 40% of the 1983 observed dose rates could be attributed to this source. Coatings removal tests conducted on the samples demonstrated that removal of the coatings could result in the removal of between 50 and 98% of the activity. Subsequent to this work, coatings and concrete removal on the accessible upper elevations of the RB resulted in dose reductions of 15 to 38%. These data, and that of subsequent work in the RB basement, indicate that protective coatings applied to structural concrete substantially reduce the degree to which the substrate will be penetrated by aqueous contaminant solutions. Relative to the ability to successfully remove absorbed contamination, the coating matrix containing the major fraction of the radionuclide load may be removed with less aggressive effort than that required to remove a potentially larger volume of contaminated concrete.