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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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
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.”
Yun-Je Cho, Hyoung-Kyu Cho, Goon-Cherl Park
Nuclear Technology | Volume 162 | Number 1 | April 2008 | Pages 92-106
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT08-A3935
Articles are hosted by Taylor and Francis Online.
Seoul National University (SNU) proposed a new concept of a reactor cavity cooling system (RCCS), which is a critical safety feature in high-temperature gas-cooled reactors. To provide reasonable experimental data for the code assessment and evaluate the feasibility of the proposed system, performance and integrity were tested by separate-effects test apparatuses and a reduced-scale mockup facility named RCCS-SNU. Calculations were performed using the MARS-GCR code for the validation of its capability to simulate multidimensional behavior, natural convective heat transfer, radiative heat transfer, etc. This assessment showed that the MARS-GCR code reasonably predicts the characteristics of the radiative heat transfer in the cavity and the forced convective heat transfer through the air-cooling pipes. However, the study showed deviation in the simulation of heat transfers that occur inside the cavity and water pool, especially the thermal stratification phenomenon. As a result, it was concluded that applying the system code with coarse node, MARS-GCR had certain limitations in the simulation of local phenomena.