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
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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
Jul 2024
Jan 2024
Latest Journal Issues
Nuclear Science and Engineering
August 2024
Nuclear Technology
Fusion Science and Technology
Latest News
Four million nuclear jobs by 2050: Who will do them?
Industry leaders from around the globe met this month to discuss the talent development that will be necessary for the long-term success of the nuclear industry.
The International Conference on Nuclear Knowledge Management and Human Resources Development, hosted by the International Atomic Energy Agency, was held in Vienna earlier this month. Discussed there was the agency’s forecast for nuclear capacity to more than double—or hopefully triple—by 2050 and the requirement of more than four million professionals to support the industry.
William J. Garland, Simon H. Pang
Nuclear Technology | Volume 75 | Number 3 | December 1986 | Pages 239-260
Technical Paper | Fission Reactor | doi.org/10.13182/NT86-A33840
Articles are hosted by Taylor and Francis Online.
The thermohydraulic stability of the Canada deuterium uranium (CANDU)-600 heat transport system was investigated from a theoretical, numerical, and experimental point of view. Simple theoretical models, used to provide phenomenological insight as a guide to the numerical and experimental studies, showed that a major form of positive feedback existed through an interplay of circuit flow, outlet header void fraction, and outlet header pressure. The flow and pressure dynamics proved to be good indicators of system stability. System computer codes (SOPHT, FIREBIRD, and HYDNA) were used for the detailed modeling of system dynamics. These codes showed that neither Ledinegg nor parallel channel instabilities occur in CANDU-600 nuclear reactors. Loop stability was predicted under all conditions with the reactor outlet header interconnect line in service as designed. With the interconnect line disconnected, loop instability was predicted for a narrow outlet header quality range (1 to 8%). These predictions were fully confirmed by semiscale experimental loop tests and plant commissioning tests.