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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
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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