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
Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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
Apr 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
May 2025
Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Zhengming Zhang, Shuyan He
Nuclear Technology | Volume 160 | Number 2 | November 2007 | Pages 178-186
Technical Paper | Fission Reactors | doi.org/10.13182/NT07-A3891
Articles are hosted by Taylor and Francis Online.
This paper studies one of the key aspects in the leak-before-break technique: the leak rate of a gas medium through penetrated cracks. The focus is on the results of theoretical studies. Based on the need for easy use in engineering calculation, two analytical models have been developed for the calculation of the leak rate of a gas medium. The first model is the isentropic flow model, which supposes that the gas flowing through the penetrated crack can be treated as isentropic flow. This model has theoretical solutions and can be applied easily, but it will overpredict the leak rate of a gas medium because it does not take the friction and other disturbances into consideration. The second model is the transient flow model, which only supposes that the gas flowing through the penetrated crack can be simplified as one-dimensional flow. This model can take the most influential factors of the gas flow into consideration. These factors include the variation of upstream pressure, various kinds of pressure losses during gas flow, and the heat exchange between the gas and the outside structures. The results of numerical simulations show that the transient flow model is suitable for engineering practices.