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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.
Young Su Na, Song-Won Cho, Kwang Soon Ha
Nuclear Technology | Volume 195 | Number 3 | September 2016 | Pages 329-334
Technical Paper | doi.org/10.13182/NT15-160
Articles are hosted by Taylor and Francis Online.
This study evaluated the hydrogen issue in the initial operation of a filtered containment venting system (FCVS). We calculated the volumetric concentration of hydrogen, steam, and air in the postulated FCVS connected with the OPR 1000, as a target nuclear power plant, under a station blackout using the MELCOR computer code (version 1.8.6). A large amount of steam and a flammable mixture generated during a severe accident are immediately released from the containment building to the FCVS when the pressure in the containment building approaches a set value. The constituent ratio of the flammable mixture of hydrogen, steam, and air can change due to the different thermal-hydraulic conditions between those due to a severe accident in the containment building and the initial condition in the FCVS. The volumetric concentration of hydrogen was 6% in the containment building just before the operation of the FCVS. It increased up to 9% in the FCVS vessel during the early operation, and steam condensation occurred simultaneously. The atmospheric condition including steam, hydrogen, and air in the FCVS can enter the combustion zone in the Shapiro diagram.