ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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
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!
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Latest News
Commercial nuclear innovation "new space" age
In early 2006, a start-up company launched a small rocket from a tiny island in the Pacific. It exploded, showering the island with debris. A year later, a second launch attempt sent a rocket to space but failed to make orbit, burning up in the atmosphere. Another year brought a third attempt—and a third failure. The following month, in September 2008, the company used the last of its funds to launch a fourth rocket. It reached orbit, making history as the first privately funded liquid-fueled rocket to do so.
A. P. Grunwald
Nuclear Science and Engineering | Volume 12 | Number 3 | March 1962 | Pages 419-423
Technical Paper | doi.org/10.13182/NSE62-A28093
Articles are hosted by Taylor and Francis Online.
Helium leak detection and other nondestructive tests of closure welds proved unreliable for the EBR-II fuel rods. A system was developed which used pressure decay in a miniature pressure chamber as a measure of weld leakage. Analysis of pressure decay rate permitted determination of leak size. Spurious signals resulting from leakage of the test system produced an abnormal ultimate test chamber pressure. These were readily differentiated from fuel rod leaks. The sensitivity of the tests is approximately 5 × 10−6 standard cubic centimeters of helium per second. Higher sensitivity may be obtained by variation of the technique and of the equipment. The influence of vapor contamination of leak capillaries was investigated and correlated with surface tension phenomena. The test has been successfully applied to a variety of fuel elements and incapsulated specimens with small internal void spaces.