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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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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Survey says . . . Emotional intelligence important in nuclear industry
The American Nuclear Society’s Diversity and Inclusion in ANS (DIA) Committee hosted a workshop social at the 2024 Winter Conference & Expo in November that brought dozens of attendees together for an engaging—and educational—twist on the game show Family Feud.
Seung Min Baek, Hee Cheon No, In Yong Park
Nuclear Technology | Volume 74 | Number 3 | September 1986 | Pages 260-266
Technical Paper | Fission Reactor | doi.org/10.13182/NT86-A33828
Articles are hosted by Taylor and Francis Online.
A nonequilibrium three-region model is developed for the accurate prediction of the pressure in the pressurizer under both transient and accident conditions. The mathematical model derived from the general conservation equations includes all of the important thermal-hydraulics processes occurring in the pressurizer: bulk flashing and condensation, wall condensation, and interfacial heat and mass transfer, etc. The Stanton number for the interfacial heat transfer coefficient is obtained by fitting the experimental results in terms of the surge rate. The bubble rising and rain-out models are developed to describe bulk flashing and condensation, respectively. To obtain the wall condensation rate, a one-dimensional heat conduction equation is solved by the pivoting method. The mathematical model is numerically solved by the back substitution and successive iteration method for fast convergence and stability. For verification, several numerical tests are done on a mild transient in the Shippingport nuclear power plant, an experimental test done at the Massachusetts Institute of Technology, and the Three Mile Island accident. It is proved that predicted results are in better agreement with experimental tests than those by previous models. Sensitivity analysis is done to see the effect of each model on the behavior of the pressurizer. Discrepancy between results predicted with the three- and the tworegion models becomes apparent in an outsurge after insurge transient. Although the interfacial heat transfer of the pressurizer can be neglected in the case of the high water level, it becomes one of the most dominant processes in the low level. The wall condensation rate becomes important with an increase in pressure due to an insurge transient.