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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
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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Latest News
Wyoming OKs construction of TerraPower’s Natrium plant
Progress continues for TerraPower’s Natrium plant, with the latest win coming in the form of a state permit for construction of nonnuclear portions of the advanced reactor.
D. Y. Hsia, P. Griffith
Nuclear Science and Engineering | Volume 78 | Number 4 | August 1981 | Pages 431-437
Technical Note | doi.org/10.13182/NSE81-A21380
Articles are hosted by Taylor and Francis Online.
Steam generator pressure drop versus flow rate instability during a loss-of-coolant accident in a pressurized water reactor has been investigated. The steam generator is simulated by four tubes, each with a different height, on top of a two-dimensional quarter-circle inlet plenum. This work deals with only an adiabatic air-water system. The pressure drop was found to be practically constant in the range of 3 jg 10 m/s. Within this range, the pressure drop depends only on the liquid flow rate. The plenum details do not matter. A model using an average flow for each tube does a good job in estimating the pressure drop. The flow distribution can be conservatively estimated by the proposed model based on a single, average tube pressure drop minimum.