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Division Spotlight
Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
Lightbridge announces first U-Zr fuel rod samples extruded at INL
Lightbridge Corporation announced today that it has reached “a critical milestone” in the development of its extruded solid fuel technology. Coupon samples using an alloy of zirconium and depleted uranium—not the high-assay low-enriched uranium (HALEU) that Lightbridge plans to use to manufacture its fuel for the commercial market—were extruded at Idaho National Laboratory’s Materials and Fuels Complex.
Sang Won Lee, Han Gon Kim, Seung Jong Oh
Nuclear Technology | Volume 158 | Number 3 | June 2007 | Pages 396-407
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT07-A3850
Articles are hosted by Taylor and Francis Online.
APR1400 is an evolutionary pressurized water reactor developed in Korea. The emergency core cooling system (ECCS) of APR1400 has been improved by adopting an independent four-train safety injection system. Each train is composed of a safety injection pump and an accumulator with a fluidic device, the passive flow rate controlling equipment. Also, ECCS water is injected directly into the reactor vessel upper downcomer, ~2 m above the cold-leg centerline. With these design characteristics, more complex thermal-hydraulic phenomena can be observed in a large-break loss-of-coolant accident (LBLOCA) scenario. In this paper, the effects of these design characteristics on the LBLOCA scenario are examined using the RELAP5/MOD3.3 code. The code modeling capability in predicting the phenomena important to APR1400 ECCS design is examined using available experiments. It shows that RELAP5/MOD3.3 conservatively predicts the bypass rate and downcomer boiling phenomena. RELAP5/MOD3.3 code analysis of APR1400 LBLOCA with conservative assumptions show that ECCS design is adequate and there is no degradation of core cooling capability and reheat phenomena during the late reflood phase. All fuel rods are quenched in the early reflood phase when the fluidic devices are inactive, showing the effectiveness of the direct vessel injection and fluidic devices against an APR1400 LBLOCA scenario.