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Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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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Nuclear News 40 Under 40 discuss the future of nuclear
Seven members of the inaugural Nuclear News 40 Under 40 came together on March 4 to discuss the current state of nuclear energy and what the future might hold for science, industry, and the public in terms of nuclear development.
To hear more insights from this talented group of young professionals, watch the “40 Under 40 Roundtable: Perspectives from Nuclear’s Rising Stars” on the ANS website.
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.