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Nuclear Nonproliferation Policy
The mission of the Nuclear Nonproliferation Policy Division (NNPD) is to promote the peaceful use of nuclear technology while simultaneously preventing the diversion and misuse of nuclear material and technology through appropriate safeguards and security, and promotion of nuclear nonproliferation policies. To achieve this mission, the objectives of the NNPD are to: Promote policy that discourages the proliferation of nuclear technology and material to inappropriate entities. Provide information to ANS members, the technical community at large, opinion leaders, and decision makers to improve their understanding of nuclear nonproliferation issues. Become a recognized technical resource on nuclear nonproliferation, safeguards, and security issues. Serve as the integration and coordination body for nuclear nonproliferation activities for the ANS. Work cooperatively with other ANS divisions to achieve these objective nonproliferation policies.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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
ARPA-E announces $40 million to develop transmutation technologies for UNF
The Department of Energy’s Advanced Research Projects Agency–Energy (ARPA-E) announced $40 million in funding to develop cutting-edge technologies to enable the transmutation of used nuclear fuel into less-radioactive substances. According to ARPA-E, the new initiative addresses one of the agency’s core goals as outlined by Congress: to provide transformative solutions to improve the management, cleanup, and disposal of radioactive waste and spent nuclear fuel.
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.