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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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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Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
L. Henderson, R. Stead
Nuclear Technology | Volume 29 | Number 2 | May 1976 | Pages 174-190
Reactor | doi.org/10.13182/NT76-A31577
Articles are hosted by Taylor and Francis Online.
A review of the Magnox Reactor experience shows the progressive development of the steam generator with increasing power density giving rise to more severe restrictions in fabrication of the steam generator elements into the boiler matrix. This has given rise to a steadily increasing demand for mechanized fabrication techniques to ensure adequate precision during manufacture. Successful operation of the once-through system in conjunction with the annular disposition of the boiler units in the prestressed concrete pressure vessel made the Oldbury A Magnox station a natural basis for development of the Advanced Gas Cooled Reactor (AGR) system. The principal criteria in selection of material are the higher temperature and the more aggressive CO2 coolant which contrasts with the need to avoid evaporation in austenitic material. Breakaway corrosion has limited carbon steel to a maximum of 350°C, while a minimum superheat of 50°C is considered necessary to avoid stress corrosion cracking in the austenitic section of a once-through boiler required by the AGR maximum gas temperatures of 634°C. Evidence of potential breakaway corrosion in 9% Cr—1% Mo at 550°C and above has caused concern for long-term operation at lower temperatures and has resulted in the maximum metal temperature being reduced to 450°C with resulting narrower margins on the degree of superheat. This has resulted in an extensive stress corrosion program aimed at defining the risk parameters prior to commissioning the first AGR station. Identification of fretting phenomena associated with the design of Hinkley B steam generator supports resulted in a welded support design and an extensive substantiation program on the integrity of the support system. The practical implication of the material chosen in the design and the manufacture of the steam generators for the Hinkley Point B and Hunterston B plants have emphasized the importance attached to quality control, typically during manipulation of bends.