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Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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Reflections on NOW
Hash Hasemianpresident@ans.org
Last month, I talked about my goal of strengthening ANS’s voice, in part by attending three conferences. I have now checked the first event off that list: the Nuclear Opportunities Workshop.
This year, NOW took another step in outgrowing its “workshop” moniker and transitioning to a full-fledged regional conference and expo. What started only a few years ago as a small gathering in Oak Ridge, Tenn., with roughly 50 attendees has skyrocketed to an event with 1,100 people in attendance in Knoxville.
NOW’s popularity reflected how busy the roughly 350 nuclear companies in Tennessee have been in recent years. There is significant work going on surrounding Gen IV reactor development and deployment, advancements in new nuclear fuels, and defense-related builds like the Uranium Processing Facility.
Rainer Moormann, Klaus Hilpert
Nuclear Technology | Volume 94 | Number 1 | April 1991 | Pages 56-67
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT91-A16221
Articles are hosted by Taylor and Francis Online.
An overview of high-temperature gas-cooled reactor (HTR) fission product chemistry and its influence on source terms in core heatup accidents is given. These accidents are risk-dominating for medium-sized HTRs and are characterized by maximum core temperatures of ∼2500°C (2773 K) and a late-starting, slowly proceeding fission product release from the fuel particles. In these accidents, the number of chemical reactions in the core and primary circuit is limited by the low oxygen potential and preferential release of metal from the fuel. The graphite in the core acts as a very powerful barrier to metallic fission products because of its chemisorption action. Cesium iodide (CsI) formation can reduce this sorptive retention for cesium when there is a high cesium burden on the graphite. This is not necessarily expected for small HTRs, which have much lower maximum accident temperatures (1600° C = 1873 K) and a much lower fractional release of fission products from coated particles. In the primary circuit, less efficient chemisorption of fission products on metals occurs. The fission product chemistry in the HTR reactor building is similar to that for other reactor types. Conservatisms in handling fission product chemistry in HTR safety analyses are identified. This leads to the conclusion that, especially for metallic fission products, a significant potential for reduction of the actual core heatup source terms exists. In modern medium-sized HTRs, these source terms are of the order of <1% of the core inventory for cesium, iodine, and noble gases and <0.1% for strontium. For small HTRs, these source terms remain several orders of magnitude smaller.