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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.
Mario De Salve, Giovanni Del Tin, Bruno Panella
Nuclear Technology | Volume 111 | Number 2 | August 1995 | Pages 275-282
Technical Paper | Nuclear Criticality Safety Special / Heat Transfer and Fluid Flow | doi.org/10.13182/NT95-A35137
Articles are hosted by Taylor and Francis Online.
Experimental data and an analysis of outsurge transients in a small pressurizer at constant electrical power input are discussed. The test section is a vertical cylinder that is connected at the bottom to a cylindrical horizontal section where the steam is produced by electric heaters. The range of the pressure is from 3 to 6 MPa. The fluid and outer wall temperatures are measured at several elevations, and the flashing rate and the fluid/ wall heat transfer are derived from the pressure and temperature time history data. The pressure transient is simulated by means of an extension of the Lu and Simpson prediction method.
