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Experimental Study of Ultrasonic Crosstalk Cancellation on SNF Canister Mock-up

  • Bozhou Zhuang
  • , Bora Gencturk
  • , Iman Asareh
  • , Assad Oberai
  • , Ryan Meyer

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

Abstract

This study examines the potential use of ultrasonic signals for detecting abnormalities in a spent nuclear fuel (SNF) storage canister. It is very difficult and, in some cases, not feasible to open sealed SNF canisters. Therefore, techniques to determine the integrity of contents of SNF canisters are needed as these packages need to be transported to interim of permanent storage in the near future. In this part of the work, a noise cancellation technique is developed so as to detect a gas signal that travels through the SNF canister, and that information is proposed to be used for detecting abnormalities in the sealed package. Optimization was used to cancel signals travelling through the solid in a multitransducer configuration. Promising results were obtained in terms of noise cancellation.

Original languageEnglish
Title of host publicationProceedings of the International High-Level Radioactive Waste Management Conference, IHLRWM 2022, Embedded with the 2022 ANS Winter Meeting
PublisherAmerican Nuclear Society
Pages723-732
Number of pages10
ISBN (Electronic)9780894487897
DOIs
StatePublished - 2022
Externally publishedYes
Event2022 International High-Level Radioactive Waste Management Conference, IHLRWM 2022, Embedded with the 2022 ANS Winter Meeting - Phoenix, United States
Duration: Nov 13 2022Nov 17 2022

Publication series

NameProceedings of the International High-Level Radioactive Waste Management Conference, IHLRWM 2022, Embedded with the 2022 ANS Winter Meeting

Conference

Conference2022 International High-Level Radioactive Waste Management Conference, IHLRWM 2022, Embedded with the 2022 ANS Winter Meeting
Country/TerritoryUnited States
CityPhoenix
Period11/13/2211/17/22

Funding

This study is funded by the U.S. Department of nE ergy under the Nuclear neE rgy University Program award no. DE - N0E 009171 . The findings and opinions presented here are those of the authors and do not necessary reflect the views of or endorsed by the sponsor. This study is funded by the U.S. Department of Energy under the Nuclear Energy University Program award no. DENE0009171. The findings and opinions presented here are those of the authors and do not necessary reflect the views of or endorsed by the sponsor.

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