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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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Latest News
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.
Ana Da Silva, Pradip Saha, Eric P. Loewen
Nuclear Technology | Volume 196 | Number 1 | October 2016 | Pages 74-88
Technical Paper | doi.org/10.13182/NT16-55
Articles are hosted by Taylor and Francis Online.
The legacy electromagnetic (EM) pump analysis tool MATRIX has been improved by the addition of a thermal analysis module. Although the module is patterned after the general-purpose Advanced General Electric Network Analyzer (AGENA) code, it is developed from a more fundamental approach to provide a better understanding and control of the thermal analysis of the EM pump. The MATRIX results are verified against the AGENA results and the test data from the 160 m3/min large EM pump tests, which provided a good estimate of the thermal conductance between the lamination and the inner duct wall. Full and good contact between the lamination and the inner duct wall is necessary to keep the copper conductor temperatures low. Parametric studies, as expected, confirmed the correct trend of increasing copper conductor temperatures with increasing frequency. The MATRIX results show that a new proposed insulation material for the future EM pumps is beneficial since it could reduce the copper block temperature by ~20°C. Such analysis can help develop a better EM pump with a more compact design and better insulation material.
