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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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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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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Marzano sworn in as NRC commissioner
Marzano
Matthew Marzano became the newest member of the Nuclear Regulatory Commission when he was officially sworn into office by chair Christopher Hanson this week.
The nuclear engineer and former reactor operator was confirmed last month in a 50–45 vote in the U.S. Senate. Last July, President Biden nominated Marzano to serve on the commission, which is tasked with formulating policies, developing regulations, issuing orders, and resolving legal matters.
Marzano’s term expires June 30, 2028.
Frank J. Rahn, Jan Collén, Anthony L. Wright
Nuclear Technology | Volume 81 | Number 2 | May 1988 | Pages 158-182
Technical Paper | Nuclear Aerosol Science / Nuclear Safety | doi.org/10.13182/NT88-A34090
Articles are hosted by Taylor and Francis Online.
The results of three experimental programs relevant to the behavior of aerosols in the primary systems of light water reactors (LWRs) are presented. These are the Large-Scale Aerosol Transport Test programs performed at the Marviken test facility in Sweden, parts of the LWR Aerosol Containment Experiments (LACE) performed at the Hanford Engineering Development Laboratory, and the TRAP-MELT validation project performed at Oak Ridge National Laboratory. The Marviken experiments focused on the behavior of aerosols released from fuel and structural materials in a damaged core. Data on the transport of these aerosols and their physical characteristics were obtained in five experiments that simulated LWR primary systems. The LACE program data include results from the containment bypass accident tests, which focused on aerosol transport in pipes. The TRAP-MELT validation project data include results from two types of experiments: (a) aerosol transport tests to investigate aerosol wall plateout in a vertical pipe geometry and (b) aerosol resuspension tests to provide a data base from which analytical models can be developed. Typical results from these programs are presented and discussed.