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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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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.
H. Y. Khater
Fusion Science and Technology | Volume 34 | Number 3 | November 1998 | Pages 614-618
Safety and Environment (Poster Session) | doi.org/10.13182/FST98-A11963682
Articles are hosted by Taylor and Francis Online.
Activation and Safety analyses were performed for the ARIES-ST design. The ARIES-ST power plant includes a water cooled copper center post and uses a SiC/LiPb blanket. The first wall and shield are made of low activation ferritic steel and cooled with helium. The center post, first wall, inboard shield and blanket were assumed to survive for 2.6 full power years (FPY). On the other hand, the outboard shield and vacuum vessel were assumed to stay in place for 40 FPY. Neutron transmutation of copper resulted in the production of several nickel, cobalt and zinc isotopes. The production of these isotopes resulted an increase of the time-space average resistivity of the center post by about 6% after 2.6 FPY. All of the plant components met the limits for disposal as Class C low level waste (LLW). The off-site doses produced at the onset of an accident are caused by the mobilization of the radioactive inventory present in the plant. Analysis of a Loss of Coolant Accident (LOCA) indicated that the first wall and shield would reach a maximum temperature of less than 700°C during the accident. The calculated temperature profiles and available oxidation-driven volatility experimental data were used to calculate the dose at the site boundary under conservative release conditions. The current design produces an effective whole body early dose of 1.77 mSv at the site boundary.