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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
Norway’s Halden reactor takes first step toward decommissioning
The government of Norway has granted the transfer of the Halden research reactor from the Institute for Energy Technology (IFE) to the state agency Norwegian Nuclear Decommissioning (NND). The 25-MWt Halden boiling water reactor operated from 1958 to 2018 and was used in the research of nuclear fuel, reactor internals, plant procedures and monitoring, and human factors.
D.R. Cohn, L. Bromberg, R.J. Leclaire, R.E. Potok, D.L. Jassby
Fusion Science and Technology | Volume 10 | Number 3 | November 1986 | Pages 1111-1116
Nuclear Technology Experiments and Facilities | doi.org/10.13182/FST86-A24881
Articles are hosted by Taylor and Francis Online.
We discuss a super high field mode of tokamak operation that uses ohmic heating or near ohmic heating to ignition. This approach could also provide high values of nτe, increasing the margin of ignition in deuterium-tritium plasmas, and opening up the possibility of some type of advanced fuel operation. D-He3 operation might be possible if high enough values of β (β ≃ .09) can be obtained. The super high field mode of operation uses very high values of B2a, where B is the magnetic field and o is the minor radius (B2a > 100 T2m). We analyze copper magnet devices with major radii from 1.7 to 3.0 meters. Minimizing or eliminating the need for auxiliary heating has the potential advantages of reducing uncertainty in extrapolating the energy confinement time of current tokamak devices, and reducing engineering problems associated with large auxiliary heating requirements. It may be possible to heat relatively short pulse, inertially cooled tokamaks to ignition with ohmic power alone. However, there may be advantages in using a very small amount of auxiliary power (less than the ohmic heating power) to boost the ohmic heating and provide a faster start-up, especially in relatively compact devices.