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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
First astatine-labeled compound shipped in the U.S.
The Department of Energy’s National Isotope Development Center (NIDC) on March 31 announced the successful long-distance shipment in the United States of a biologically active compound labeled with the medical radioisotope astatine-211 (At-211). Because previous shipments have included only the “bare” isotope, the NIDC has described the development as “unleashing medical innovation.”
P.I. Petersen, DIII-D Team
Fusion Science and Technology | Volume 39 | Number 2 | March 2001 | Pages 305-314
Fusion Technology Plenary | doi.org/10.13182/FST01-A11963253
Articles are hosted by Taylor and Francis Online.
An advanced tokamak is characterized by increased confinement, stability and steady state operation. The increased confinement and stability are obtained through modifications to the shape and profiles of the plasma and through stability feedback control. These modifications have to be self-consistent. The increased confinement makes it possible to make smaller and thereby lower cost reactors for the same power output as compared to conventional tokamaks. Four potential modes for advanced tokamaks are currently being studied on DIII-D: radiative improved mode, high internal inductance ℓi mode, negative central shear (NCS) mode, and quiescent double barrier (QDB) mode.
High-density plasma are important for reactors and recent experiments in DIII–D have shown that it is possible to operate substantially above the Greenwald limit. Control of the internal transport barriers that are responsible for the increased confinement have been improved in counter injected neutral beam plasmas. One of the limiting instabilities for the performance of high bootstrap fraction negative central shear plasmas is the resistive wall mode. These modes have to a certain degree been suppressed in DIII–D by using the six-section correction coil. With a newly installed upper inner divertor in DIII–D it has been possible to obtain improved density and impurity control. An upgrade of the electron cyclotron system is being done on DIII–D. Three 1 MW gyrotrons are being added. This system has been used to completely suppress the neoclassical tearing mode by applying electron cyclotron current drive at definite positions and in very localized areas. Finally, the implication of the recent findings for fusion reactors will be discussed.
