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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
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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Nuclear Technology
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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.
James J. Dahl, Shivi Singh, Marvin G. Zimmerman
Nuclear Technology | Volume 180 | Number 1 | October 2012 | Pages 1-17
Technical Paper | Fission Reactors | doi.org/10.13182/NT12-A14515
Articles are hosted by Taylor and Francis Online.
This paper investigates the potential impacts of the transition to the U.S. Department of Energy (DOE) Order 420.1B requirements and the criteria promulgated by the new DOE-STD-1189 on the current practice for seismic design of structures, systems, and components (SSCs). Addressed in the review is the modification of the prescribed methodology provided in ANSI/ANS-2.6-2004 by the new DOE standard. The new ANSI/ANS standards provide criteria and guidance in selecting the seismic design category (SDC) and the limit state (LS) for the SSCs that are important to safety. An unmitigated consequence analysis considering the uncertainties in estimating failure and the safety consequences of the failure may be performed to determine the SDC and the LS, which then are used to establish the level of peak ground acceleration and design response spectra. The new DOE-STD-1189 modifies the prescribed methodology provided in ANSI/ANS-2.6-2004 for calculation of unmitigated radiological dose consequence. Unmitigated consequence analysis is a procedure that has been used by the DOE for the purpose of incorporating safety in the design and operation of its nuclear facilities and is also used in 10 CFR 70, the U.S. Nuclear Regulatory Commission regulation applicable to fuel cycle facilities, and the associated Standard Review Plan (NUREG-1520). This paper identifies the iterative DOE double-pronged approach to seismic design, and a simplified example demonstrates the unmitigated seismic hazard consequence analysis.