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Division Spotlight
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.
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
NRC engineers share their expertise at the University of Puerto Rico
Robert Roche-Rivera and Marcos Rolón-Acevedo are licensed professional engineers who work at the U.S. Nuclear Regulatory Commission. They are also alumni of the University of Puerto Rico–Mayagüez (UPRM) and have been sharing their knowledge and experience with students at their alma mater since last year, serving as adjunct professors in the university’s Department of Mechanical Engineering. During the 2023–2024 school year, they each taught two courses: Fundamentals of Nuclear Science and Engineering, and Nuclear Power Plant Engineering.
Mohamed S. El-Tokhy, Imbaby I. Mahmoud
Nuclear Science and Engineering | Volume 195 | Number 1 | January 2021 | Pages 69-100
Technical Paper | doi.org/10.1080/00295639.2020.1787013
Articles are hosted by Taylor and Francis Online.
This paper is focused on overcoming reactor shutdown malfunction and diagnostics due to poor cooling and water drop level within a pressurized water reactor. So the temperature coupling analysis between the heat exchanger (HEX) and the U-tube steam generator (UTSG) is inspected under changes of primary and secondary water temperature. This coupling allows the removal of heat from the UTSG via the HEX. For the UTSG, implicit and explicit solutions for analysis and evaluation of UTSG characteristics are conducted. Scarce explicit models describing the behaviors of the UTSG are available. This analytical framework is proposed to control the water/steam flow within the UTSG of a nuclear power reactor (NPR). Exact performances for temperatures of metal tube temperature and primary water entering and exiting from the tube are derived. There is no one implicit model that can describe the performance characteristics of heat transfer within the UTSG. So a novel simulator declaring the operational behavior of the UTSG in an NPR has been built. This simulator of the UTSG provides exact handling of the UTSG performance characteristics. For the HEX, the exact handling of the HEX including boundary temperature and the primary and secondary interface temperatures are proposed. Three different models are implemented (combinational, steady state, and integral). The possibility of realizing higher steam quality is established through block diagram programming models. Compared to literature results, the built models are validated with high agreement. As a final conclusion, the proposed analyses allow the control of steam generation and flow. The introduced results compensate for the necessity of expensive and complicated controllers within the HEX and UTSG through parameter variation. Accordingly, the performance of the NPR is enhanced.