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Division Spotlight
Robotics & Remote Systems
The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
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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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.”
Charles J. Mueller, David C. Wade
Nuclear Technology | Volume 91 | Number 2 | August 1990 | Pages 215-225
Technical Paper | Safety of Next Generation Power Reactor / Nuclear Saftey | doi.org/10.13182/NT90-A34429
Articles are hosted by Taylor and Francis Online.
The approach and methods used at Argonne National Laboratory to assess core damage probability in risk assessments for innovative liquid-metal reactor (LMR) designs using metal-fueled cores in pool configurations are outlined. Bounding estimates for the predicted frequency of core damage from all unprotected initiating events are developed by establishing a set of reference scenarios from traditional anticipated transient without scram events. Sources of uncertainty are described and categorized. A probabilistic treatment is used to propagate the various uncertainties through safety analyses to determine their effects on limiting reactor parameters. For example, probability distributions for safety margins to selected core temperatures are propagated from sensitivity studies and estimates of the underlying uncertainties in reactivity feedback coefficients. Considerable self-cancellation of many of the contributors to core response uncertainties is demonstrated analytically. Upper bound probabilities of core damage are then calculated for the LMR cores currently being designed. The results show that these designs have much lower probabilities of suffering core damage than are predicted in published risk assessments for commercial power reactors. Finally, design strategies that can be used to reduce these already low probabilities to almost arbitrarily low values are discussed.