ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
NRC wants input on Hermes 2 test reactor construction permit
The Nuclear Regulatory Commission is seeking input on its draft environmental assessment and draft finding of no significant impact for Kairos Power’s application to build the Hermes 2 test reactor facility in Oak Ridge, Tenn.
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.