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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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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
IAEA report confirms safety of discharged Fukushima water
An International Atomic Energy Agency task force has confirmed that the discharge of treated water from Japan’s Fukushima Daiichi nuclear power plant is proceeding in line with international safety standards. The task force’s findings were published in the agency’s fourth report since Tokyo Electric Power Company began discharging Fukushima’s treated and diluted water in August 2023.
More information can be found on the IAEA’s Fukushima Daiichi ALPS Treated Water Discharge web page.
E. E. Anderson, S. Langer, N. L. Baldwin, F. E. Vanslager
Nuclear Technology | Volume 11 | Number 2 | June 1971 | Pages 259-265
Technical Paper | Technique | doi.org/10.13182/NT71-A30890
Articles are hosted by Taylor and Francis Online.
The design and application of high-temperature in-core furnace equipment for use in a TRIGA research reactor facility is described in this paper. Investigations of the in-pile behavior of high-temperature gas-cooled reactor fuels at temperatures to 1800°C in a variable neutron flux can be conducted using the TRIGA King Furnace (TKF). The TKF consists of an electrically heated graphite tube and an aluminum containment vessel designed to fit an in-core TRIGA fuel element position. The furnace is associated with a gas control and trapping system used to trap contaminants and fission gases from the fuel specimen under investigation. The TRIGA King Furnace Facility (TKFF) has been used for numerous studies, including fission gas and iodine release from various reactor fuels. In addition, neutron-pulsing experiments on pyrolytic-carbon-coated fuel particles have been conducted using the TKFF.
