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
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
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!
Latest Magazine Issues
May 2024
Jan 2024
Latest Journal Issues
Nuclear Science and Engineering
June 2024
Nuclear Technology
Fusion Science and Technology
Latest News
Steam is a sign of cooling system function . . . at ITER
Steam from one of ITER’s ten induced-draft cooling cells offers visual confirmation of a successful cooling system test, the ITER organization announced April 30. ITER’s cooling system features 60 kilometers of piping with pumps, filters, and heat exchangers that can pull water through at up to 14 cubic meters per second. Once fully operational, two cooling loops—one to remove the heat generated by the plasma in the ITER tokamak and one for its supporting infrastructure—will be capable of extracting up to 1,200 MW of heat.
M. Yoda, S. I. Abdel-Khalik, D. L. Sadowski, B. H. Mills, J. D. Rader
Fusion Science and Technology | Volume 67 | Number 1 | January 2015 | Pages 142-157
Technical Paper | doi.org/10.13182/FST14-792
Articles are hosted by Taylor and Francis Online.
Current predictions suggest that the target plate of a divertor, as one of the few solid surfaces directly exposed to the plasma of a magnetic fusion energy reactor, will be subject to steady-state heat fluxes as great as 10 MW/m2. Developing appropriate methods for cooling these divertors with helium is therefore a major technological challenge for plasma-facing components. This paper reviews dynamically similar experimental studies and numerical simulations of the thermal-hydraulic performance of two helium-cooled divertor concepts, the helium-cooled divertor with multiple-jet cooling (HEMJ) and the helium-cooled flat plate divertor, as well as a variant of the HEMJ, the so-called finger-type divertor, performed as part of the ARIES study. The results from these studies are extrapolated to prototypical conditions and used to predict the maximum average heat flux and coolant pumping power requirements for these divertor concepts. These extrapolations can be used to estimate how changes in the operating conditions, such as the helium inlet temperature and the maximum temperature of the divertor pressure boundary, affect thermal performance. Finally, the correlations from these extrapolations are used in the system code developed by the ARIES study.