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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.
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Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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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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.”
Dong H. Nguyen
Nuclear Technology | Volume 91 | Number 1 | July 1990 | Pages 61-74
Technical Paper | Safety of Next Generation Power Reactor / Fission Reactor | doi.org/10.13182/NT90-A34441
Articles are hosted by Taylor and Francis Online.
The design of the next generation of power reactors will emphasize passive safety and enhanced engineered systems. True passivity can be achieved by capitalizing on natural laws to restore reactor stability during an off-normal event. The most effective stabilizing mechanisms relying solely on natural laws— without human interference—are the feedback reactivities produced by a change in the reactor thermal state. During 1986 and 1987, an important research program was undertaken at the Fast Flux Test Facility (FFTF) to advance the understanding of feedback mechanisms and to investigate passive safety in liquid-metal reactors. The experimental program began with a series of static feedback reactivity measurements aimed at separating feedback components and ended with a demonstration of passive safety in a series of loss-of-flow-without-scram (LOFWOS) to natural circulation tests. Described here are (a) the fundamental experimental concepts used to unfold various feedback components, (b) the analysis of integral data used to construct feedback reactivity models, (c) the comparison of FFTF reactivities with mechanistic feedback models in the SASSYS/SAS4A code system, and (d) the pretest calculations for the LOFWOS test series, using the new FFTF feedback models.