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Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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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Hash Hashemian: Visionary leadership
As Dr. Hashem M. “Hash” Hashemian prepares to step into his term as President of the American Nuclear Society, he is clear that he wants to make the most of this unique moment.
A groundswell in public approval of nuclear is finding a home in growing governmental support that is backed by a tailwind of technological innovation. “Now is a good time to be in nuclear,” Hashemian said, as he explained the criticality of this moment and what he hoped to accomplish as president.
Sang Ji Kim, Yonghee Kim, Sergi Hong, Chung Ho Cho, Jae-Hyuk Eoh, Jong Bum Kim, Myung Hwan Wi, Kwi Seok Ha, Eui Kwang Kim
Nuclear Technology | Volume 170 | Number 1 | April 2010 | Pages 148-158
Technical Paper | Special Issue on the 2008 International Congress on Advances in Nuclear Power Plants / Fission Reactors | doi.org/10.13182/NT10-A9453
Articles are hosted by Taylor and Francis Online.
The conceptual design of a 900-MW(thermal) lead-cooled fast reactor (LFR) system for transuranic element (TRU) burning is developed and analyzed using TRU-U-Zr metallic alloy fuel. The design and analysis areas covered are neutronics design, thermal-hydraulic analysis, thermal system design, system mechanical design and analysis, system arrangement, passive decay heat removal system evaluation, and safety analysis for anticipated transient without scram (ATWS) events. Design challenges, solutions, and further research and development items during the conceptual design are described in this paper. Large burnup reactivity swing inherent in the transmutation reactor and irradiation damage to the cladding by high fast neutron fluence are overcome by filling in boron carbide within the tie rods with axial cutbacks. The lead coolant in the reactor pool was estimated to lead to a maximum stress of 125 MPa in the containment vessel. For the long-term cooling behavior upon the concurrent occurrences of a loss of heat sink and a loss of flow, the hot pool temperature is maintained below the design limit of 650°C, which is achieved by an improved decay heat removal design with heat transfer enhancement mechanisms. Analyses of the ATWSs in the investigated core do not reveal any problem from the viewpoints of fuel temperature, cladding temperature, and hot pool temperature. In conclusion, the 900-MW(thermal) LFR system in this study does not pose any significant design-related concerns except for a marginal seismic loading due to the large coolant mass and a verification of the newly introduced design resolutions for long-term decay heat removal.