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
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
2023 ANS Winter Conference and Expo
November 12–15, 2023
Washington, D.C.|Washington Hilton
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
Sep 2023
Jan 2023
Latest Journal Issues
Nuclear Science and Engineering
October 2023
Nuclear Technology
Fusion Science and Technology
Latest News
Westinghouse, Bechtel sign consortium agreement for first nuclear plant in Poland
Westinghouse Electric Company and engineering, construction, and project management firm Bechtel on September 20 announced the signing of a consortium agreement to partner on the design and construction of Poland’s first nuclear power plant.
D. R. Mikkelsen, H. Maassberg, M. C. Zarnstorff, C. D. Beidler, W. A. Houlberg, W. Kernbichler, H. Mynick, D. A. Spong, P. Strand, V. Tribaldos
Fusion Science and Technology | Volume 51 | Number 2 | February 2007 | Pages 166-180
Technical Paper | doi.org/10.13182/FST07-A1297
Articles are hosted by Taylor and Francis Online.
We explore whether the energy confinement and planned heating in the National Compact Stellarator Experiment (NCSX) are sufficient to test magnetohydrodynamic (MHD) stability limits, and whether the configuration is sufficiently quasi-axisymmetric to reduce the neoclassical ripple transport to low levels, thereby allowing tokamak-like transport. A zero-dimensional model with fixed profile shapes is related to global energy confinement scalings for stellarators and tokamaks, neoclassical transport properties are assessed with the DKES, NEO, and NCLASS codes, and a power balance code is used to predict temperature profiles. Reaching the NCSX goal of <> = 4% at low collisionality will require HISS-95 = 3, which is higher than the best achieved in present stellarators. However, this level of confinement is actually ~10% lower than that predicted by the ITER-97P tokamak L-mode scaling. By operating near the stellarator density limit, the required HISS-95 is reduced by 35%. The high degree of quasi-axisymmetry of the configuration and the self-consistent "ambipolar" electric field reduce the neoclassical ripple transport to a small fraction of the neoclassical axisymmetric transport. A combination of neoclassical and anomalous transport models produces pressure profile shapes that are within the range of those used to study the MHD stability of NCSX. We find that <> = 4% plasmas are "neoclassically accessible" and are compatible with large levels of anomalous transport in the plasma periphery.
