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Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
Meeting Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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
Report: New York state adding 1 GW of nuclear to fleet
New York Gov. Kathy Hochul has instructed the state’s public electric utility to add at least 1 gigawatt of new nuclear by building a large-scale nuclear plant or a collection of smaller modular reactors, according to the Wall Street Journal.
Kyung Mo Kim, In Guk Kim, Yeong Shin Jeong, In Cheol Bang (UNIST)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 1161-1167
Guarantee of the diversity by installation of additional safety system, having different working principle from the existing systems, could mitigate the suggested issues on the passive safety systems. Hybrid control rod-heat pipe, which is a passive decay heat removal device combining the functions of heat pipe and control rod, was proposed by UNIST in Republic of Korea as a passive safety system improving the diversity of passive safety in small modular reactors. It was designed to perform both functions of decay heat removal and reactivity control simultaneously. From the performance analysis, it was found that the designed hybrid control rod has sufficient decay heat removal capacity and reactivity worth. Additionally, hydraulic control rod drive mechanism, which controls the movement of control rod by hydraulic resistance, was designed to achieve fully-passive operation of the hybrid control rods eliminating the malfunction of CRDM owing to electromagnetic signal error. Based on the feasibility study for the concept of hybrid control rod and hydraulic control rod drive mechanism, detailed design of passive in-core cooling system (PINCs) for SMR consisting of hybrid control rods, hydraulic control rod drive mechanism, and heat sinks, was constructed considering the operations of PINCs during normal and accident conditions of reactor.
