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Division Spotlight
Young Members Group
The Young Members Group works to encourage and enable all young professional members to be actively involved in the efforts and endeavors of the Society at all levels (Professional Divisions, ANS Governance, Local Sections, etc.) as they transition from the role of a student to the role of a professional. It sponsors non-technical workshops and meetings that provide professional development and networking opportunities for young professionals, collaborates with other Divisions and Groups in developing technical and non-technical content for topical and national meetings, encourages its members to participate in the activities of the Groups and Divisions that are closely related to their professional interests as well as in their local sections, introduces young members to the rules and governance structure of the Society, and nominates young professionals for awards and leadership opportunities available to members.
Meeting Spotlight
2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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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August 2024
Latest News
New laws offer nuclear industry incentives for existing power plant uprates
This year, the U.S. nuclear industry received a much-needed economic boost that could help preserve operating nuclear power plants and incentivize upgrades that extend their lifespan and power output.
Signed into law in 2022, the Inflation Reduction Act offers production tax credits (PTCs) for existing nuclear power plants and either PTCs or investment tax credits (ITCs) for new carbon-free generation. These credits could make power uprates—increasing the maximum power level at which a commercial plant may operate—a much more appealing option for utilities.
M. Khatib-Rahbar, E. Cazzoli, M. Lee, H. Nourbakhsh, R. Davis, E. Schmidt
Nuclear Science and Engineering | Volume 102 | Number 3 | July 1989 | Pages 219-259
Technical Paper | doi.org/10.13182/NSE89-A27476
Articles are hosted by Taylor and Francis Online.
A probabilistic approach to quantifying uncertainties in the progression of severe reactor accidents is formulated and applied to the Source Term Code Package. It is shown that Quantification of uncertainties at the basic level of input parameters reveals broad time-dependent uncertainties in the core melt progression, containment challenges, and fission product releases. Dominant contributors to the source term uncertainties include the core meltdown parameters, the release rate coefficients of fission products, the chemical activity coefficients during core/concrete interactions, and containment performance.
