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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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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.
Hans K. Fauske
Nuclear Science and Engineering | Volume 17 | Number 1 | September 1963 | Pages 1-7
Technical Paper | doi.org/10.13182/NSE63-A17204
Articles are hosted by Taylor and Francis Online.
Critical two-phase, steam - water flows have been measured in horizontal test sections with pipe diameters of 0.125 and 0.269 in. internal diameter (i.d.) over a range of qualities from 0.01 to 0.7, mass velocities from 500 to 4200 lb/sec-ft2, and critical pressures from 40 to 360 lb /in.2 absolute. The critical flow data and a theory for the critical flow phenomena have been discussed (1, 2). In this paper an analysis for the pressure drop data in the approach region to critical flow is presented. The flow mixture accelerates to critical flow at the end of the test sections, and thus the pressure drop data are for flow regimes in which both momentum and frictional losses are important. By utilizing the model developed for estimating critical discharge rates (1), two-phase friction factors were calculated from the experimental data. The friction factors obtained correlated well in terms of the two-phase quality and appear to be independent of flow rate, static pressure, and test geometry for the conditions examined.