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Division Spotlight
Robotics & Remote Systems
The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
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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State lawmakers across the country push for more nuclear
From lifting moratoriums to launching studies to labeling it as clean, state lawmakers are exploring ways to give nuclear energy a boost in 2025. Here’s a look at some of the pronuclear legislation under review.
P. Zhang (State Nuclear Power Technology R&D Center), H. J. Chang (State Nuclear Power Technology R&D Center/Tsinghua Univ),
Proceedings | Advances in Thermal Hydraulics 2018 | Orlando, FL, November 11-15, 2018 | Pages 1142-1154
Liquid entrainment at the tee junction of hot leg to ADS-4 branch (fourth-stage Automatic Depressurization System) is a high priority safety related phenomenon in Westinghouse Advanced Passive pressurized water reactor (AP1000) and Chinese Advanced Passive pressurized water reactor (CAP1400). Previous studies are mainly carried out on reduced scale experimental test facilities. To offer a better understanding of the liquid entrainment phenomenon at tee junction and evaluate the applicability of entrainment models, a full scale test facility is designed and fabricated. The maximum air and water flowrates are 12kg/s and 150kg/s respectively. 16 onset of liquid entrainment tests and 80 entrainment rate tests are carried out on this test facility. Test data is compared with previous entrainment models. Significant differences are founded. This means the applicability of liquid entrainment models in safety analysis code is questionable. Based on the flow regime transition criterion in horizontal pipe, a new onset of liquid entrainment model is proposed. The agreement of the new model to test data is better than previous models.