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Division Spotlight
Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
Meeting Spotlight
2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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 new build procurement considerations
It may seem counterintuitive, but the best time to enhance the ability to support operations and maintenance for a new plant is before construction starts. This is one of many lessons learned by the currently operating nuclear fleet. As construction and startup of many nuclear facilities was completed, it quickly became evident that the ability to efficiently support operations and maintenance was limited. Most of the information necessary to establish and manage procurement of spare and replacement items, maintenance, and configuration of the facilities was unavailable and had to be gathered on a case-by-case, “on-demand” basis. Absence of necessary information and the associated challenges resulted in the need for staff augmentation and multiyear-long projects to develop equipment bills of material and maintenance programs and to perform technical evaluations for the huge quantities of spare and replacement items being requested.
Gregory J. Van Tuyle, Peter Kroeger, Gregory C. Slovik, Bing C. Chan, Robert J. Kennett, Arnold L. Aronson
Nuclear Technology | Volume 91 | Number 2 | August 1990 | Pages 185-202
Technical Paper | Safety of Next Generation Power Reactor / Nuclear Saftey | doi.org/10.13182/NT90-A34427
Articles are hosted by Taylor and Francis Online.
Three advanced design concepts, including two liquid-metal-cooled reactors (LMRs), the Power Reactor Inherently Safe Module (PRISM) and the Sodium Advanced Fast Reactor (SAFR), and a high-temperature gas-cooled reactor (HTGR) are discussed and compared. Each provides inherent or passive safety to improve system safety. The focus is on two primary objectives: reactor shutdown and shutdown heat removal. The LMR and HTGR concepts rely on inherent reactivity feedback to provide an inherent reactor response under a failure-to-scram condition; SAFR also provides a passive shutdown system using Curie point magnets (the self-actuated scram system). For shutdown heat removal, the LMR and HTGR designs rely on passive air cooling of the reactor vessel as the ultimate safety-grade system.