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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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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.
Martin Lochter, Reinhard Uhlemann, Jochen Linke
Fusion Science and Technology | Volume 19 | Number 4 | July 1991 | Pages 2101-2111
Technical Paper | Carbon Material Special | doi.org/10.13182/FST91-A29346
Articles are hosted by Taylor and Francis Online.
The high heat flux ion beam test facility at Forschungszentrum Jülich can produce peak power densities of 0.14 to 12 kW/cm2 for pulse lengths of 10 ms to 15 s. Longer pulses up to steady-state operation are possible with reduced power. The total ion beam power can be varied between 70 kW and 6 MW at particle energies of 10 to 60 keV. The particles are hydrogen and helium. The beam illuminates a 1300-cm2 area, which allows a large area for materials tests. The rise time of the beam pulses can be adjusted between 2 and 200 ms, and the pulse repetition rate is between 1 and 5 min. The test facility is equipped with a sample manipulator with a vacuum lock that allows a sample size of 15 × 10 cm with active or passive cooling. The extensive diagnostic system of the test stand, originally designed for developing and conditioning the neutral beam ion sources for the Tokamak Experiment for Technology Oriented Research (TEXTOR), and the diagnostic system of the sample manipulator are described. The results of a materials test series performed for the development of wall materials for the Next European Torus/International Thermonuclear Experimental Reactor (NET/ITER) are shown. Possible upgrades of the facility are also discussed.