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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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
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.
B. Zhao, S. A. Musa, S. I. Abdel-Khalik, M. Yoda
Fusion Science and Technology | Volume 72 | Number 3 | October 2017 | Pages 294-299
Technical Paper | doi.org/10.1080/15361055.2017.1333827
Articles are hosted by Taylor and Francis Online.
The helium-cooled modular divertor with multiple jets (HEMJ) can potentially accommodate the large steady-state heat fluxes expected in future long-pulse magnetic fusion reactors. This work, which is part of the joint US-Japan PHENIX collaboration, describes recent results on a single HEMJ “finger” unit obtained in a helium loop operating at prototypical pressures of ~10 MPa. A new heater was used to increase the maximum coolant inlet temperature ≤ 400°C (vs. the prototypical value of 600°C) at incident heat fluxes ≤ 4.5 MW/m2 at these elevated temperatures. The effect of varying the jet-to-impingement surface separation distance H from 0.47 mm to 1.49 mm was also studied for mass flow rates ≤ 8 g/s. Numerical simulations of this HEMJ test section were also performed to obtain local information that could not be measured in the experiments.
Varying H within this range appears to have little effect on both the dimensionless heat transfer coefficient, or Nusselt number , and the dimensionless pressure drop across the HEMJ, or loss coefficient . The experimental measurements do, however, give lower after re-calibration of the differential pressure transducer; these results are now in better agreement with numerical predictions compared with previous experimental data. The experimental results obtained at higher and for are, however, lower than those predicted by a correlation for obtained from extensive measurements taken at lower temperatures in the same facility. These initial results require further examination because they are contradicted by the numerical predictions. If these results are valid, they suggest that the maximum heat flux that can be accommodated by a divertor module may be lower than expected.