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.
Explore membership for yourself or for your organization.
Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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!
Latest Magazine Issues
Jul 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
August 2025
Nuclear Technology
Fusion Science and Technology
July 2025
Latest News
Hash Hashemian: Visionary leadership
As Dr. Hashem M. “Hash” Hashemian prepares to step into his term as President of the American Nuclear Society, he is clear that he wants to make the most of this unique moment.
A groundswell in public approval of nuclear is finding a home in growing governmental support that is backed by a tailwind of technological innovation. “Now is a good time to be in nuclear,” Hashemian said, as he explained the criticality of this moment and what he hoped to accomplish as president.
Jacob A. Farber, Daniel G. Cole (Univ of Pittsburgh)
Proceedings | Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technolgies (NPIC&HMIT 2019) | Orlando, FL, February 9-14, 2019 | Pages 868-878
In the nuclear power industry, one important class of accidents is the loss of coolant accident (LOCA). This paper presents methods to detect a LOCA that is initiated: (i) while the plant is going through a small transient, and (ii) with a time-varying leak magnitude. The accident is simulated using a generic pressurized water reactor (GPWR) simulator. The fault is detected using a model-based approach with models identi ed using GPWR data. The model-based approach is multiple-model adaptive estimation (MMAE), which uses multiple system models representing both normal and faulted operating conditions. During operation, these models simulate the potential operating conditions, incorporating measurement feedback in a Kalman lter state-estimation structure. Faults are detected by selecting the model that most closely matches the system according to statistical characteristics. For a LOCA, data-driven models of the pressurizer liquid level are derived using rst-principles and system identi cation. In system identi cation, a physics-based model form is derived that contains unknown parameters. System identi cation is then used to estimate the parameter values based on measurement data, providing plant-speci c pressurizer models. For the accident scenario described above, the proposed methods di erentiate between the transient and the accident, and provide real-time estimates of the leak magnitude after it has been initiated.