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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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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.
P. F. Zweifel, Joel H. Ferziger
Nuclear Science and Engineering | Volume 10 | Number 4 | August 1961 | Pages 357-361
doi.org/10.13182/NSE61-A15378
Articles are hosted by Taylor and Francis Online.
A “consistent P1” four-factor formula is derived. This formula, which contains an additional term not found in the usual four-factor formula, introduces a change in keff ∼ D2B2 where D is the thermal diffusion coefficient. The term is negative for hydrogen and positive for other moderators. The correction will be at most 1% Δk for a practical system. Since the four-factor formula is not expected to be accurate to 1%, it is proposed that this term be used mainly as a criterion for determining whether consistent P1 multigroup calculations are required, or whether simple group diffusion methods will suffice. By using the consistent P1 equations when the term D2B2 is of the order 1%, one will avoid the introduction of a consistent error into his reactor calculations. Finally, the consistent P1 multigroup equations are displayed, and it is seen that the procedure for their solution is not a great deal more difficult than for solving the usual multigroup equations.