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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
Materials in Nuclear Energy Systems (MiNES 2023)
December 10–14, 2023
New Orleans, LA|New Orleans Marriott
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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Nuclear Science and Engineering
December 2023
Nuclear Technology
Fusion Science and Technology
January 2024
Latest News
Illinois lifts ban on some new nuclear construction
Illinois Gov. J. B. Pritzker returned to the good graces of the nuclear community last Friday, signing H.B. 2473, a bill that partially lifts the state’s decades-long moratorium on new nuclear power builds by permitting the construction of small modular reactors.
Pritzker had vetoed similar legislation, S.B. 76, in August, saying in a veto message that the bill included an overly broad definition of “advanced reactors,” which would “open the door to the proliferation of large-scale nuclear reactors that are so costly to build that they will cause exorbitant ratepayer-funded bailouts.” Pritzker had also asserted that S.B. 76 lacked “regulatory protections or updates to address the health and safety of Illinois residents who would live and work around these new reactors.”
Prathamesh N. Bilgunde, Leonard J. Bond
Nuclear Technology | Volume 202 | Number 2 | May-June 2018 | Pages 161-172
Technical Paper | doi.org/10.1080/00295450.2017.1419782
Articles are hosted by Taylor and Francis Online.
Advanced piezoelectric-based ultrasonic transducers offer the potential for in-coolant nondestructive testing (NDT) measurements at high temperatures (HTs), including during hot standby (~260°C) for liquid-sodium–cooled advanced small modular reactors. The reliability of the NDT measurements is typically quantified by the probability of detection (POD) measured at the corresponding temperature. Obtaining such data in liquid sodium is challenging. Using a model-assisted POD approach, a transfer function is reported that enables data obtained on low carbon steel specimens at room temperature to give an estimated POD at an HT. A primary source of the difference in POD between room temperature and HT is due to the transducer material temperature-dependent performance. This paper demonstrates the transfer function approach using data for modified lead zirconium titanate (PZT-5A). A physics-based model was developed using a finite element method and used to quantify reduction in the scattering amplitude for standard reflectors, side drilled holes (SDHs), for a range of sizes, from 15°C to 195°C. Scattering amplitudes for the room-temperature–simulated data are compared with the experimental data measured at 2.25 MHz. A temperature correction and transfer functions were developed to transform the simulated temperature effect in the physics-based model to compare with the experimental data. The model-based approach was validated with experimental data. It was seen and validated for a PZT-5A ultrasonic transducer operating at 2.25 MHz that the 95% POD at 15°C was 0.58 λ, and due to variation in temperature-dependent properties of PZT-5A, the 95% POD was achieved only for a 1.41 λ SDH diameter.