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
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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
BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
S. K. Bhattacharyya, J. A. Morman, R. G. Bucher, D. M. Smith, W. R. Robinson, E. F. Bennett
Nuclear Technology | Volume 50 | Number 3 | October 1980 | Pages 197-218
Technical Paper | Reactor | doi.org/10.13182/NT80-A32524
Articles are hosted by Taylor and Francis Online.
A possible accident scenario in a gas-cooled fast reactor (GCFR) is the leakage of secondary steam into the core. A full-scale experimental study of the physics effects of such an accidental condition has been performed on the zero power reactor (ZPR)-9 critical facility at Argonne National Laboratory. Polyethylene foam strips were used to simulate steam for these measurements. The basic neutronics parameters, namely, neutron spectrum, spectral indexes, reactivity worths, 238U Doppler effect, and B4C control rod worths, were measured in the steam-flooded GCFR critical assembly and also in the corresponding dry, reference GCFR assembly. The results of these measurements clearly show the spectrum softening effects on steam entry. For the analysis of the experiments, ENDF/B-IV-based data were used with two-dimensional diffusion theory methods. It was concluded that the values of the primary safety parameters increased upon steam entry relative to the reference dry case. Such an increase would mitigate the effects of accidental steam entry in a GCFR.