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
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
May 2024
Jan 2024
Latest Journal Issues
Nuclear Science and Engineering
June 2024
Nuclear Technology
Fusion Science and Technology
Latest News
Proving DRACO will deliver
The United States is now closer than it has been in over five decades to launching the first nuclear thermal rocket into space, thanks to DRACO—the Demonstration Rocket for Agile Cislunar Orbit.
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.