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  • About
  • The Global ETD Search service is a free service for researchers to find electronic theses and dissertations. This service is provided by the Networked Digital Library of Theses and Dissertations.
    Our metadata is collected from universities around the world. If you manage a university/consortium/country archive and want to be added, details can be found on the NDLTD website.
1

DEVELOPMENT OF THE CENTRIFUGALLY TENSIONED METASTABLE FLUID DETECTOR FOR IN-AIR RADON AND ACTINIDE ALPHA DETECTION

Mitchell Hemesath (8801069) 21 June 2022 (has links)
This thesis pertains to two R&D objectives associated with deploying TMFD sensor technology for meeting AARST-NRPP metrics for Radon (Rn) in-air detection, as well as for monitoring of ultra-trace actinides in air, amidst other Rn-progeny alpha emitting radionuclides. A challenge has persisted over the past 40+ years for detecting trace actinides in air amidst a 100-1000x higher Rn-progeny background. This thesis had a primary aim for addressing this challenge, and developing and assessing for a novel technology solution. Both objectives were successfully met. Methods, designs, and experimental effects of apparatus are discussed for successful Rn and progeny detection for 1-100 pCi/L concentration levels, as well as for Rn-progeny “blind” spectroscopic detection of 10-12 μCi/cc concentrations of actinides (Pu/U/Am) in air. The resulting CTMFD based technology was compared with the state-of-art “Alpha Sentry” CAM system and found to offer superior performance in multiple categories, and ~18x improvement in time to detect (e.g. at 0.02 DAC in 3 hrs vs ~70 hrs for state-of-art) for actinides while also remaining ~100% blind to ~102x higher Rn-progeny background; and, with 1 keV energy resolution vs ~300-400 keV for Alpha Sentry.
2

Safeguards for Uranium Extraction (UREX) +1a Process

Feener, Jessica S. 2010 May 1900 (has links)
As nuclear energy grows in the United States and around the world, the expansion of the nuclear fuel cycle is inevitable. All currently deployed commercial reprocessing plants are based on the Plutonium - Uranium Extraction (PUREX) process. However, this process is not implemented in the U.S. for a variety of reasons, one being that it is considered by some as a proliferation risk. The 2001 Nuclear Energy Policy report recommended that the U.S. "develop reprocessing and treatment technologies that are cleaner, more efficient, less waste-intensive, and more proliferation-resistant." The Uranium Extraction (UREX+) reprocessing technique has been developed to reach these goals. However, in order for UREX+ to be considered for commercial implementation, a safeguards approach is needed to show that a commercially sized UREX+ facility can be safeguarded to current international standards. A detailed safeguards approach for a UREX+1a reprocessing facility has been developed. The approach includes the use of nuclear material accountancy (MA), containment and surveillance (C/S) and solution monitoring (SM). Facility information was developed for a hypothesized UREX+1a plant with a throughput of 1000 Metric Tons Heavy Metal (MTHM) per year. Safeguard goals and safeguard measures to be implemented were established. Diversion and acquisition pathways were considered; however, the analysis focuses mainly on diversion paths. The detection systems used in the design have the ability to provide near real-time measurement of special fissionable material in feed, process and product streams. Advanced front-end techniques for the quantification of fissile material in spent nuclear fuel were also considered. The economic and operator costs of these systems were not considered. The analysis shows that the implementation of these techniques result in significant improvements in the ability of the safeguards system to achieve the objective of timely detection of the diversion of a significant quantity of nuclear material from the UREX+1a reprocessing facility and to provide deterrence against such diversion by early detection.

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