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.
Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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
Virginia utility considers SMRs
Dominion Energy Virginia has issued a request for proposals from leading nuclear companies to study the feasibility of putting a small modular reactor at its North Anna nuclear power plant.
While the utility says it is not a commitment to build an SMR at the site, the RFP is “an important first step in evaluating the technology and the North Anna site to support Dominion Energy customers’ future energy needs consistent with the company’s most recent Integrated Resource Plan.”
Borut Mavko, Stojan Petelin, Oton Gortnar
Nuclear Technology | Volume 101 | Number 2 | February 1993 | Pages 181-192
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT93-A34779
Articles are hosted by Taylor and Francis Online.
The steam generator is one of the most important components of a pressurized water reactor (PWR) nuclear power plant. Thus, the ability to model and predict the steam generator steady-state and transient thermal-hydraulic behavior is a prerequisite for performing safety analyses of PWR systems. A RELAP5 model of the Westinghouse D4 steam generator with a 70/30 split feedwater system has been developed, and it is tested by simulating five secondary-side-initiated transients. This study of primary-to-secondary heat transfer and the secondary coolant vaporization process has enabled the primary coolant cooldown to be maximized, as required for performing a conservative steamline break analysis. These tests were realized using the RELAP5/MOD2.36.05 and RELAP5/MOD3.5M5 computer codes.