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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.
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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
BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
Ryohei Tanaka, Tatsuo Kondo
Nuclear Technology | Volume 66 | Number 1 | July 1984 | Pages 75-87
A. Selection, Production, and Development of Alloys for HTGR Component | Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material | doi.org/10.13182/NT84-A33457
Articles are hosted by Taylor and Francis Online.
The developments of the last decade are reviewed on a technical basis for heat-resistant alloys in application to the high-temperature structural components of the process heating high-temperature gas-cooled reactor. The major activities have fallen into two categories: the near-term development for the experimental reactor and the long-term R&D second-generation applications, i.e., for the materials to be used in the second-stage heat exchanger installation in the experimental reactor and those for advanced-stage reactors with very high outlet temperatures. In both categories of programs, significant advances have been made, respectively, in providing and testing a modified commercial alloy with enhanced compatibility with the service environments and in selecting potential high performance alloys from the new developmental candidate alloys. Modification of the existing commercial alloy was achieved through the application of the finding on enhanced oxidation resistance by controlling the common impurities in the material, while the enhanced creep rupture strength recognized in the best performing new alloys has been attributed to the precipitation of a tungsten-rich phase (α2) during holding at test temperatures. The new alloy development program currently under way is also introduced.