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Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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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Latest News
DOE-EM finishes cleanup of legacy Oak Ridge reactor lab site
The Department of Energy’s Office of Environmental Management announced that the 30-foot-long, 37,600-pound reactor vessel from Oak Ridge National Laboratory’s Low Intensity Test Reactor was shipped to EnergySolutions’ low-level radioactive waste facility in Clive, Utah, in late April.
Andreas Schaffrath, E. F. Hicken, H. Jaegers, H.-M. Prasser
Nuclear Technology | Volume 126 | Number 2 | May 1999 | Pages 123-142
Technical Paper | Fission Reactors | doi.org/10.13182/NT99-A2962
Articles are hosted by Taylor and Francis Online.
Siemens AG is developing the new innovative boiling water reactor concept SWR1000. New features are passive safety systems, such as emergency condensers, building condensers, passive pressure pulse transmitters, and gravity-driven core flood lines.For experimental investigation of emergency condenser effectiveness, the NOKO test facility has been constructed at Forschungszentrum Jülich in cooperation with Siemens. This test facility has an operating pressure of 10 MPa and a maximum power of 4 MW for steam production. The emergency condenser bundle consists of eight tubes and is fabricated with planned geometry and material of the SWR1000. In more than 200 experiments, the emergency condenser power was determined as a function of pressure, water level, and concentration of noncondensables in the pressure vessel as well of pressure, water level, and temperature in the condenser.Posttest calculations of NOKO experiments were performed with an improved version of ATHLET. To calculate the heat transfer coefficients during condensation in horizontal tubes, it was necessary to develop the KONWAR module and to implement it in ATHLET. KONWAR is based on the flow regime map of Tandon and includes several semiempirical correlations for the determination of the heat transfer coefficients. The comparison between calculations and experiments shows good agreement.