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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
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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Nuclear Science and Engineering
August 2024
Nuclear Technology
Fusion Science and Technology
Latest News
ARPA-E announces $40 million to develop transmutation technologies for UNF
The Department of Energy’s Advanced Research Projects Agency–Energy (ARPA-E) announced $40 million in funding to develop cutting-edge technologies to enable the transmutation of used nuclear fuel into less-radioactive substances. According to ARPA-E, the new initiative addresses one of the agency’s core goals as outlined by Congress: to provide transformative solutions to improve the management, cleanup, and disposal of radioactive waste and spent nuclear fuel.
Marius Zamfirache, Anisia Bornea, Liviu Stefan, Ana George, Ovidiu Balteanu
Fusion Science and Technology | Volume 76 | Number 4 | May 2020 | Pages 488-493
Technical Paper | doi.org/10.1080/15361055.2020.1718853
Articles are hosted by Taylor and Francis Online.
The National Research and Development Institute for Cryogenics and Isotopic Technologies (ICSI Rm. Valcea) was established in 1970 as a research entity with the main goal of developing a heavy water production technology. One of the departments of the institute, entitled ICSI Nuclear, is oriented toward the development of a heavy water detritiation technology with the main beneficiary being the Cernavoda nuclear power plant. Thus, ICSI Nuclear has completed the technical project of the Cernavoda Tritium Removal Facility (CTRF). This paper focuses on the CTRF front end (water detritiation system) and will analyze achievement of the nominal regime at start-up and analysis of the transient regimes that may occur during normal operation and their impact on the water detritiation factor. Analysis results can become input for improvement of the CTRF control and instrumentation system, for subsequent operating facility procedures, and for verification of the isotopic exchange software models corresponding to these modes of operation.