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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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!
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Nuclear Science and Engineering
August 2024
Nuclear Technology
July 2024
Fusion Science and Technology
Latest News
NRC engineers share their expertise at the University of Puerto Rico
Robert Roche-Rivera and Marcos Rolón-Acevedo are licensed professional engineers who work at the U.S. Nuclear Regulatory Commission. They are also alumni of the University of Puerto Rico–Mayagüez (UPRM) and have been sharing their knowledge and experience with students at their alma mater since last year, serving as adjunct professors in the university’s Department of Mechanical Engineering. During the 2023–2024 school year, they each taught two courses: Fundamentals of Nuclear Science and Engineering, and Nuclear Power Plant Engineering.
Technical Session|New and Advanced Reactors
Wednesday, August 23, 2023|10:45AM–12:25PM EDT|Gunston East/West
Session Chair:
Jun Liao (Westinghouse Electric Co.)
Alternate Chair:
Piyush Sabharwall
Session Organizer:
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Investigation of Hybrid Heat Pipe Shutdown Rod Concept of Microreactor as a Passive Safety System
10:45–11:05AM EDT
Dong Hun Lee (Ulsan Nat'l Institute Science and Technology), In Cheol Bang (Ulsan Nat'l Institute Science and Technology)
Paper
Thermal Stress Analysis for Heat Pipe Cooled Microreactor Core Varying Condenser Temperature
11:05–11:25AM EDT
Myung Jin Jeong (Seoul Nat'l Univ.), San Lee (Seoul Nat'l Univ.), Jaeuk Im (Seoul Nat'l Univ.), Hyoung Kyu Cho (Seoul Nat'l Univ.)
Experimental Study on the Start-up Characteristics and Performance of a Ten Sodium Heat Pipe Bundle Array
11:25–11:45AM EDT
Pei-Hsun Huang (Univ. Michigan), Taehwan Ahn (Univ. Michigan), Annalisa Manera (Univ. Michigan), Victor Petrov (Univ. Michigan)
Nuclear Spaceship for Interplanetary Cruise Using a Micro Fast Reactor
11:45AM–12:05PM EDT
Tadashi Narabayashi (Tokyo Institute of Technology)
Study on Startup Characteristic of a Supercritical Carbon Dioxide Brayton Cycle Coupled with Heat Pipe Cooled Reactor
12:05–12:25PM EDT
Zheng Wang (Xi’an Jiaotong Univ.), Minghui Zhang (Xi’an Jiaotong Univ.), Shihao Xu (Xi’an Jiaotong Univ.), Junli Gou (Xi’an Jiaotong Univ.), Jianqiang Shan (Xi’an Jiaotong Univ.)
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