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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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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Latest News
Glass strategy: Hanford’s enhanced waste glass program
The mission of the Department of Energy’s Office of River Protection (ORP) is to complete the safe cleanup of waste resulting from decades of nuclear weapons development. One of the most technologically challenging responsibilities is the safe disposition of approximately 56 million gallons of radioactive waste historically stored in 177 tanks at the Hanford Site in Washington state.
ORP has a clear incentive to reduce the overall mission duration and cost. One pathway is to develop and deploy innovative technical solutions that can advance baseline flow sheets toward higher efficiency operations while reducing identified risks without compromising safety. Vitrification is the baseline process that will convert both high-level and low-level radioactive waste at Hanford into a stable glass waste form for long-term storage and disposal.
Although vitrification is a mature technology, there are key areas where technology can further reduce operational risks, advance baseline processes to maximize waste throughput, and provide the underpinning to enhance operational flexibility; all steps in reducing mission duration and cost.
Sadia Khalid, Idrees Ahmad, Awais Zahur
Nuclear Technology | Volume 205 | Number 9 | September 2019 | Pages 1175-1184
Technical Paper | doi.org/10.1080/00295450.2019.1580530
Articles are hosted by Taylor and Francis Online.
The long-term, safe, and reliable operation of a reactor coolant pump is vital for the safety of a nuclear reactor. In the case of a station blackout or power failure to the pump, the inertia of rotating parts of the pump should provide sufficient pumping capacity or flow rate to remove decay heat to ensure the safety of the reactor. An accurate flow coastdown analysis is required for the design and manufacture of reactor coolant pumps. In this paper a mathematical model is formulated to study flow coastdown of CHASNUPP-2, which is a pressurized water reactor. Frictional losses in the pump are also incorporated in the model to get accurate results. Two important parameters of the model are inertia of the pump impeller and inertia of the coolant, which are related to each other in the form of effective energy ratio. The effective energy ratio is made variable in order to accurately model the flow coastdown transient. The model is solved numerically to get flow coastdown curves and the comparison of the theoretical and experimental results shows a good agreement between them.