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.
Explore membership for yourself or for your organization.
Conference Spotlight
2026 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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
Dec 2025
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
January 2026
Nuclear Technology
December 2025
Fusion Science and Technology
November 2025
Latest News
What’s the most difficult question you’ve been asked as a maintenance instructor?
Blye Widmar
"Where are the prints?!"
This was the final question in an onslaught of verbal feedback, comments, and critiques I received from my students back in 2019. I had two years of instructor experience and was teaching a class that had been meticulously rehearsed in preparation for an accreditation visit. I knew the training material well and transferred that knowledge effectively enough for all the students to pass the class. As we wrapped up, I asked the students how they felt about my first big system-level class, and they did not hold back.
“Why was the exam from memory when we don’t work from memory in the plant?” “Why didn’t we refer to the vendor documents?” “Why didn’t we practice more on the mock-up?” And so on.
Haico V. Kok, Tim H. J. J. van der Hagen
Nuclear Technology | Volume 127 | Number 1 | July 1999 | Pages 38-48
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT99-A2982
Articles are hosted by Taylor and Francis Online.
A model is developed that enables the determination of steady-state values of all system variables of the boiling water reactor simulator loop DESIRE. The model calculates natural-circulation mass flow rate, subcooling, carry-under, and feedwater flow rate from the three independent variables: power, feedwater temperature, and the setting of a controllable friction valve. The void fraction in the assembly is calculated using the drift-flux model with Dix's correlation. A submodel for the calculation of carry-under is derived on the basis of measurements. Comparison of the model with measurements shows an excellent agreement over a wide range of operating conditions.