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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
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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Latest News
Report: New York state adding 1 GW of nuclear to fleet
New York Gov. Kathy Hochul has instructed the state’s public electric utility to add at least 1 gigawatt of new nuclear by building a large-scale nuclear plant or a collection of smaller modular reactors, according to the Wall Street Journal.
Luis Alva, Xinyu Huang (Univ of South Carolina), George Jacobsen (General Atomics)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 598-604
The nuclear fuel cladding undergoes severe thermal shock during reflooding of the nuclear core after a loss of coolant accident (LOCA). The purpose of this work is to evaluate the resistance of SiCf-SiCm composite cladding to such thermal shock events. In order to achieve this goal, a nuclear grade SiCf-SiCm composite tube, manufactured by General Atomics (GA), was quenched from an outer surface temperature of 1000 ºC into room temperature (RT) water and hot water. The composite tube was heated by a tungsten rod placed inside the tubular sample to simulate the fuel pellet. The tungsten rod was heated to a centerline temperature of 1400 ºC by an induction coil. To monitor the progressive damage of the SiCf-SiCm composite tube, the acoustic emission (AE) technique is used to acquire the acoustic signals during the test. The samples quenched into RT water showed visible cracks while the sample quenched in hot water did not. Some of the AE signals are related to cracks in the material during quenching. After quenching, the burst strength of the SiCf-SiCm composite tube is measured using a bladder technique. Results show that the SiCf-SiCm composite tube retains more than 88% of its strength after quenching.