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Education, Training & Workforce Development
The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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
First astatine-labeled compound shipped in the U.S.
The Department of Energy’s National Isotope Development Center (NIDC) on March 31 announced the successful long-distance shipment in the United States of a biologically active compound labeled with the medical radioisotope astatine-211 (At-211). Because previous shipments have included only the “bare” isotope, the NIDC has described the development as “unleashing medical innovation.”
Paul B. Abramson
Nuclear Science and Engineering | Volume 62 | Number 2 | February 1977 | Pages 195-214
Technical Paper | doi.org/10.13182/NSE77-A26957
Articles are hosted by Taylor and Francis Online.
Subroutine POOL was developed for the study of hypothetical core disruptive accidents in nuclear reactors and, as such, is set up for use as a subroutine in the FX-2 Dynamic Neutronics Code. This combination permits scoping studies of the total neutronic/hydrodynamic interactions and is capable of performing phenomenological investigations of hypothetical problems ranging from the high ramp disassembly calculations, performed in the past by the Lagrangian code VENUS, to the study of recriticality in boiling pools of fuel and steel. POOL specifically includes, in at least parametric fashion, the following phenomena: 1. intra- and inter-element heat transfer by diffusion, convection, and radiation for both fuel and steel inside the pool and at the boundaries 2. local vapor generation and concurrent local pressurization 3. hydrodynamic behavior using the inviscid Navier-Stokes equations in a Eulerian formulation. Sample results are shown for boil-up of an initially quiescent dense pool of fuel and steel. Subroutine POOL was modified by removing the free surface portion of the calculation and the associated expansion of the Eulerian Grid. The combined code, known as FX2-P00L, was used to perform prompt burst calculations for two comparison cases for a lOOO-MW(th) demolike reactor. Good agreement is shown between FX2-POOL and VENUS II for these two hypothetical situations, indicating that the hydrodynamic and thermodynamic assumptions made in POOL are accurate enough for prompt burst analysis and compare well with the VENUS models.