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
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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
Jun 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
July 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
Prachai Norajitra, Widodo Widjaja Basuki, Radmir Giniyatulin, Caroline Hernandez, Vladimir Kuznetsov, Igor V. Mazoul, Marianne Richou, Luigi Spatafora
Fusion Science and Technology | Volume 67 | Number 4 | May 2015 | Pages 732-744
Technical Paper | doi.org/10.13182/FST14-832
Articles are hosted by Taylor and Francis Online.
A helium-cooled divertor concept for DEMO has been continuously developed over the past decade at the Karlsruhe Institute of Technology within the framework of the former European Fusion Power Plant Conceptual Study. Over the years, research results and progress of the divertor development with numerous earnings representations have been continually reported. This paper first gives a retrospect of the past results achieved so far and then reports on recent progress of the divertor development. In the course of developing the conceptual design with the goal of reaching a divertor heat flux performance of 10 MW/m2, the He-cooled modular divertor with jet cooling (HEMJ) was selected in the early 2000s as the reference concept out of a series of conceptual design studies. For verification of the design principle, a combined high-heat-flux (HHF) test facility with helium loop was built in 2004 at the Efremov Institute for the divertor experiments under specified DEMO conditions. There, the cooling performance of the divertor finger with helium under the heat load of 10 MW/m2 was confirmed already at an early stage. In parallel, the HEMJ divertor design was successively improved in terms of its robustness and quality of production in order to achieve a long service life against thermocyclic loading. A breakthrough was achieved in 2010 when an optimized HEMJ cooling finger survived more than 1000 HHF cycles at 10 MW/m2 without damage. In the context of long-term planning for DEMO divertor development, research and development work on the development of larger divertor components has been started, particularly focusing on certain fabrication techniques covering, e.g., high-temperature brazing and mass production of the divertor components. Recent progress—a part of this paper—was achieved in the HHF experiment of the tungsten nine-finger module in Efremov, development of nondestructive testing methods for testing multifinger modules in collaboration with CEA, and a study on the integration of multifinger modules on the target plate.