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Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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 Science and Engineering
September 2024
Nuclear Technology
August 2024
Fusion Science and Technology
Latest News
Taking shape: Fusion energy ecosystems built with public-private partnerships
It’s possible to describe fusion in simple terms: heat and squeeze small atoms to get abundant clean energy. But there’s nothing simple about getting fusion ready for the grid.
Private developers, national lab and university researchers, suppliers, and end users working toward that goal are developing a range of complex technologies to reach fusion temperatures and pressures, confounded by science and technology gaps linked to plasma behavior; materials, diagnostics, and electronics for extreme environments; fuel cycle sustainability; and economics.
Anthony Birri, Christian M. Petrie, Thomas E. Blue
Nuclear Technology | Volume 207 | Number 12 | December 2021 | Pages 1865-1872
Technical Paper | doi.org/10.1080/00295450.2020.1844532
Articles are hosted by Taylor and Francis Online.
This paper describes the parametric analysis of an optical fiber–based gamma thermometer (OFBGT) that is intended to be used to infer the power distribution in the Ohio State University Research Reactor (OSURR). The OFBGT measures the radial temperature difference between an optical fiber that is within the thermal mass and an optical fiber that is within the capillary tube that is attached to the exterior of the outer sheath of the OFBGT. This gas gap acts as a thermal resistance to volumetric gamma heating of the OFBGT thermal mass. Of the six that are analyzed, one is deemed most appropriate for operation in the OSURR Central Irradiation Facility. This design produces a maximum of ~50°C at full reactor power (450 kW). A comparison of the six OFBGT designs generally shows how modifications of the design that increase suffer from decreased spatial resolution.