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Division Spotlight
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.
Meeting Spotlight
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
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
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.
Peter R. Nelson, Donald R. Harris
Nuclear Technology | Volume 60 | Number 2 | February 1983 | Pages 320-332
Technical Paper | Radiation Effects and Their Relationship to Geological Repository / Education | doi.org/10.13182/NT83-A33088
Articles are hosted by Taylor and Francis Online.
Since 1963, the Rensselaer Polytechnic Institute’s (RPI) critical facility has contained 6.01 kg of 235U, a load in excess of the 5-kg 235U formula quantity delimiting the stringent physical protection requirements of the Nuclear Regulatory Commission’s Category I. Because these requirements would be prohibitively expensive for RPI, a number of alternatives were examined including decommissioning. A combined experimental and analytical program has succeeded in reconfiguring the core to loading below the formula quantity. Core physics parameters are within the technical specifications as before, and the experimental utility of the core is preserved in most aspects. The analysis used conventional pressurized water reactor industry nodal methods and can be regarded as providing experimental tests on these methods.