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
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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
Sep 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
October 2025
Nuclear Technology
September 2025
Fusion Science and Technology
Latest News
NNSA awards BWXT $1.5B defense fuels contract
The Department of Energy’s National Nuclear Security Administration has awarded BWX Technologies a contract valued at $1.5 billion to build a Domestic Uranium Enrichment Centrifuge Experiment (DUECE) pilot plant in Tennessee in support of the administration’s efforts to build out a domestic supply of unobligated enriched uranium for defense-related nuclear fuel.
Zhengming Zhang, Shuyan He
Nuclear Technology | Volume 160 | Number 2 | November 2007 | Pages 170-177
Technical Paper | Fission Reactors | doi.org/10.13182/NT07-A3890
Articles are hosted by Taylor and Francis Online.
Leak-before-break analysis of pressurized vessels and pipes is an important technique to guarantee the safety of reactor pressurized components. This analytical method involves many technical problems that need intensive study. Among these problems, the leak rate of the coolant is far from being well understood. The results of the current leak-rate models may have large errors. Little study has been carried out on the leak rate of gas coolant used in a high-temperature gas-cooled reactor (HTGR). This paper introduces experimental and theoretical studies on the leak rate of a gas medium. The focus is on the results of the experimental studies. A series of experiments for the leak rate of a gas medium were conducted based on preliminary simulation of the penetrated crack. Systematic data were obtained. The laws of a gas medium flowing through a narrow slit are summarized.