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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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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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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Colin Judge: Testing structural materials in Idaho’s newest hot cell facility
Idaho National Laboratory’s newest facility—the Sample Preparation Laboratory (SPL)—sits across the road from the Hot Fuel Examination Facility (HFEF), which started operating in 1975. SPL will host the first new hot cells at INL’s Materials and Fuels Complex (MFC) in 50 years, giving INL researchers and partners new flexibility to test the structural properties of irradiated materials fresh from the Advanced Test Reactor (ATR) or from a partner’s facility.
Materials meant to withstand extreme conditions in fission or fusion power plants must be tested under similar conditions and pushed past their breaking points so performance and limitations can be understood and improved. Once irradiated, materials samples can be cut down to size in SPL and packaged for testing in other facilities at INL or other national laboratories, commercial labs, or universities. But they can also be subjected to extreme thermal or corrosive conditions and mechanical testing right in SPL, explains Colin Judge, who, as INL’s division director for nuclear materials performance, oversees SPL and other facilities at the MFC.
SPL won’t go “hot” until January 2026, but Judge spoke with NN staff writer Susan Gallier about its capabilities as his team was moving instruments into the new facility.
Kunihiko Takeda, Hatsuki Onitsuka, Heiichiro Obanawa, Shin Saito
Nuclear Technology | Volume 81 | Number 3 | June 1988 | Pages 421-428
Technical Paper | Radioisotopes and Isotope Separation | doi.org/10.13182/NT88-A16063
Articles are hosted by Taylor and Francis Online.
Process energy of the chemical uranium enrichment process is discussed using the dynamic enrichment factor, avoiding a cluster of commonly used equations that correlate relevant engineering parameters. An advanced process, whose process energy was found to be much smaller than in the original process in both laboratory and bench tests, has been recently developed and applied to a pilot plant. The basic principle underlying the improvement is an inverse redox reaction induced by the increased sorbability of multicoordinated metal-complex ions onto an ion-exchange resin. The energy requirement for the advanced process will be reduced to <100 kW·h/kg·separative work unit.
