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Division Spotlight
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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2023 ANS Winter Conference and Expo
November 12–15, 2023
Washington, D.C.|Washington Hilton
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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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October 2023
Nuclear Technology
Fusion Science and Technology
Latest News
Environmental regulator gives nod to plans for first Polish nuclear plant
Poland’s General Directorate for Environmental Protection (GDOŚ) has given its imprimatur to the Central European nation’s plan to build and operate its first nuclear power facility, state-owned utility Polskie Elektrownie Jądrowe announced last Friday.
PEJ, which submitted its environmental impact report for the proposed project to GDOŚ in March 2022, called the decision “a key permit obtained in the investment process, because subsequent administrative approvals, including the decision to determine the location of the investment and the building permit, must comply with the arrangements and conditions contained in the decision on environmental conditions.”
M. Yoda, S. I. Abdel-Khalik
Fusion Science and Technology | Volume 72 | Number 3 | October 2017 | Pages 285-293
Technical Paper | doi.org/10.1080/15361055.2017.1333825
Articles are hosted by Taylor and Francis Online.
Developing ways to effectively remove the extremely high heat fluxes incident on the plasma-facing components is an important challenge for magnetic fusion energy (MFE). In most cases, the target plates of the divertor, which removes helium ash and other impurities from the core plasma, are subject to the most extreme conditions, with steady-state incident heat fluxes of at least 10 MW/m2. Starting from the early 1990s, a variety of divertor designs with target plates of tungsten (W), cooled for the most part by impinging jets of helium (He), have been investigated.
This paper reviews and discusses a number of these impinging-jet concepts, including the modular He-cooled finger-type configurations developed by the Karlsruhe Institute of Technology (KIT), as well as the T-tube divertor, the helium-cooled flat-plate (HCFP) divertor, and the combined plate/finger divertor, all evaluated as part of the ARIES studies. Over the last 15 years, a number of studies have shown that the steady-state thermal and structural performance of single units of a number of these divertor designs can be evaluated with reasonable accuracy under prototypical conditions using a combination of numerical simulations and experimental studies. The helium-cooled modular jet (HEMJ) design has been successfully tested at incident heat fluxes as great as 13 MW/m2 at prototypical conditions. Although it remains unclear how much neutron irradiation damage will affect W, or other armor materials, He jet-impingement cooling is a leading candidate for resolving power exhaust heat removal issues in plasma-material interactions.
