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Young Members Group
The Young Members Group works to encourage and enable all young professional members to be actively involved in the efforts and endeavors of the Society at all levels (Professional Divisions, ANS Governance, Local Sections, etc.) as they transition from the role of a student to the role of a professional. It sponsors non-technical workshops and meetings that provide professional development and networking opportunities for young professionals, collaborates with other Divisions and Groups in developing technical and non-technical content for topical and national meetings, encourages its members to participate in the activities of the Groups and Divisions that are closely related to their professional interests as well as in their local sections, introduces young members to the rules and governance structure of the Society, and nominates young professionals for awards and leadership opportunities available to members.
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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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Proving DRACO will deliver
The United States is now closer than it has been in over five decades to launching the first nuclear thermal rocket into space, thanks to DRACO—the Demonstration Rocket for Agile Cislunar Orbit.
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.