ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
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
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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
Oklo completes end-to-end demonstration of advanced fuel recycling
Oklo Inc. has announced that it has completed the first end-to-end demonstration of its advanced fuel recycling process as part of an ongoing $5 million project in collaboration with Argonne and Idaho National Laboratories. Oklo’s goal: scaling up its fuel recycling capabilities to deploy a commercial-scale recycling facility that would increase advanced reactor fuel supplies and enhance fuel cost effectiveness for its planned sodium fast reactors.
Werner Scholtyssek
Nuclear Technology | Volume 111 | Number 3 | September 1995 | Pages 319-330
Technical Paper | A New Light Water Reactor Safety Concept Special / Nuclear Reactor Safety | doi.org/10.13182/NT95-A15862
Articles are hosted by Taylor and Francis Online.
The TPCONT computer code is used to study the thermal-hydraulic behavior of a pressurized water reactor containment after a core-melt accident. A commercial-sized reactor of 1500-MW(electric) power output is especially designed to withstand transient and long-term loads with purely passive means. It is shown that the decay heat can be removed with an optimized cooling system based on natural-convective air flow in the annular gap with sufficient safety margins of maximum pressure and temperature to failure values. Three gap designs, which are different in the treatment of leakage flow, are investigated. In extensive parameter studies, the thermal-hydraulic evolution in the containment is found to be rather sensitive to various system data. Therefore, precise predictions of maximum loads need accurate knowledge of the design data of the reactor under consideration and better physical data, especially concerning heat transfer and flow data in the cooling duct. Various parameters are identified that may be exploited in a careful and optimized design to effectively limit the long-term loads to acceptable values.