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Conference 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
DOE on track to deliver high-burnup SNF to Idaho by 2027
The Department of Energy said it anticipated delivering a research cask of high-burnup spent nuclear fuel from Dominion Energy’s North Anna nuclear power plant in Virginia to Idaho National Laboratory by fall 2027. The planned shipment is part of the High Burnup Dry Storage Research Project being conducted by the DOE with the Electric Power Research Institute.
As preparations continue, the DOE said it is working closely with federal agencies as well as tribal and state governments along potential transportation routes to ensure safety, transparency, and readiness every step of the way.
Watch the DOE’s latest video outlining the project here.
T.A. Khan, D. Tom, R.T. Watts
Fusion Science and Technology | Volume 8 | Number 1 | July 1985 | Pages 898-903
Tritium | Proceedings of the Sixth Topical Meeting on the Technology of Fusion Energy (San Francisco, California, March 3-7, 1985) | doi.org/10.13182/FST85-A40148
Articles are hosted by Taylor and Francis Online.
In the design of facilities which handle tritium, radiation safety assessments for various operational parameters and conditions are required. A computer-based system, entitled RAPTIAH, has been developed which performs the analyses and provides the fundamental information required for such assessment. RAPTIAH starts by estimating fluid leak rates from individual components. From the leak rates it derives the rate of tritium release in each area of the facility. Next, the airborne tritium concentrations in areas of the facility and the release of tritium to the environment are obtained. Finally, using component reliability data and the pattern of maintenance, the potential tritium exposure to occupational individuals is estimated. RAPTIAH may be used to identify design measures which would enhance radiation protection in tritium handling facilities.