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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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DNFSB to hold public meeting on aging management
The Defense Nuclear Facilities Safety Board, which provides safety oversight of Department of Energy sites, is holding a public hearing on August 14 on benchmarking of best practices in the management of aging infrastructure.
According to the DNFSB, the goal of the hearing is to gather information from relevant organizations on best practices in infrastructure aging management to inform the development of potential safety improvements to DOE programs.
S. Chatzidakis, A. Ikonomopoulos, S. E. Day
Nuclear Technology | Volume 177 | Number 1 | January 2012 | Pages 119-131
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT12-A13332
Articles are hosted by Taylor and Francis Online.
This study presents numerical modeling of the SPERT-IV D-12/25 tests, a series of reactivity insertion, self-limiting, transients for a variety of coolant flow conditions. The PARET-ANL code is used to simulate the system response under these reactivity-initiated accident conditions and estimate the measured damage-indicating parameters - including the cladding temperature - using three departure from nucleate boiling (DNB) correlations, namely, those of Tong, Mirshak, and Bernath. The main objective of this sensitivity analysis is to identify, through performance measures, the DNB correlation influence on the prediction of the transient behavior. It appears that for reactivity insertions >1.20 $, the predicted transient behavior varies significantly depending on the applied DNB correlation. In addition, this study discusses the degree of conservatism introduced by each DNB correlation in the peak clad temperature estimates.