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
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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
Jul 2024
Jan 2024
Latest Journal Issues
Nuclear Science and Engineering
August 2024
Nuclear Technology
Fusion Science and Technology
Latest News
Virginia utility considers SMRs
Dominion Energy Virginia has issued a request for proposals from leading nuclear companies to study the feasibility of putting a small modular reactor at its North Anna nuclear power plant.
While the utility says it is not a commitment to build an SMR at the site, the RFP is “an important first step in evaluating the technology and the North Anna site to support Dominion Energy customers’ future energy needs consistent with the company’s most recent Integrated Resource Plan.”
Christoph Homann, Maurizio Bottoni, Burkhardt Dorr, Dankward Struwe
Nuclear Technology | Volume 91 | Number 3 | September 1990 | Pages 275-286
Technical Paper | Fission Reactor | doi.org/10.13182/NT90-A34452
Articles are hosted by Taylor and Francis Online.
The computer code BACCHUS has been developed for thermal-hydraulic calculations of coolant flows in reactor geometries with hexagonal pin arrangements. It has been used in its two-dimensional single-phase version for the interpretation of the first three experiments of the in-pile series Mol 7C in a sodium-cooled 37-pin bundle. The modeling of experimental details is described. Results for the coolant flow and temperature distributions in the blocked region are presented for selected Mol 7C cases for steady-state and transient conditions up to boiling inception. The extrapolation of the results to reactor conditions is done in several steps. First, the features that are specific for the Mol 7C experiments are removed, and then the bundle is enlarged to a size typical for reactors.
