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
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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!
Latest Magazine Issues
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Nuclear Science and Engineering
August 2024
Nuclear Technology
Fusion Science and Technology
Latest News
BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
Wolfgang Kastner, Gerd J. Seeberger
Nuclear Technology | Volume 60 | Number 2 | February 1983 | Pages 268-277
Technical Paper | Radiation Effects and Their Relationship to Geological Repository / Fission Reactor | doi.org/10.13182/NT83-A33083
Articles are hosted by Taylor and Francis Online.
The impact of a loss-of-coolant accident (LOCA) on a nuclear reactor is determined in its first phase by many events, one of them being the behavior of the reactor coolant pumps. In this case, a mixture of steam and water flows through the pumps. Experiments were carried out to examine the family of characteristics of geometrically scaled pumps (scale 1:5 and 1:4) within the relevant parameter range under such conditions. The presented results of steady-state experiments are compared with results of former projects. Besides flow and speed, the most significant parameters on two-phase pump performance are void fraction and system pressure. A brief comparison between steady-state and transient results is provided. The impact of the pump’s behavior on the LOCA is demonstrated on the basis of blowdown calculations using various pump models and two-phase pump data.
