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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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
House E&C members question the DOE
As work progresses on the Department of Energy’s Nuclear Reactor Pilot Program, which will progress through DOE authorization rather than Nuclear Regulatory Commission licensing, three members of the House Committee on Energy and Commerce have sent a critical letter to Energy Secretary Chris Wright.
The letter demands “information about the DOE and its employees’ dealings with the NRC and its staff” and expresses concern that DOE staff has “broken the firewall” between the departments.
Takashi Kodama, Hiroshi Kinuhata, Mikio Kumagai, Kazunori Suzuki, Shin-Itiro Hayashi, Shingo Matsuoka
Nuclear Technology | Volume 210 | Number 6 | June 2024 | Pages 958-984
Research Article | doi.org/10.1080/00295450.2023.2273550
Articles are hosted by Taylor and Francis Online.
Using the amount, composition, and decay power density of high-level liquid waste in a storage tank, the temperature change of the waste up to 600°C and the corresponding vapor and gas release rates of H2O, HNO3, NO2, NO, and O2 as a function of time after the loss of cooling function were obtained by the following method. The heat balance equations in and around the tank were derived, and the solution of the waste temperature change was numerically obtained using the vaporization rates of H2O and HNO3 and the generation rate of NOx, which were both obtained from the experiments using the simulated liquid waste. Utilizing the temperature versus time curve obtained from the equation, the release rates of the components described above were obtained as a function of time. This information on the progress of the accident can be used to study the Leak Path Factor of radioactive materials, especially of volatilized Ru, and further, it becomes basic information when considering accident management and suppressing the impact of a disaster.