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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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!
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Latest News
Uranium spot price closes out 2024 at $72.63/lb
The uranium market closed out 2024 with a spot price of $72.63 per pound and a long-term price of $80.50 per pound, according to global uranium provider Cameco.
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.