Feasibility study for detection of fuel assemblies state inside sealed dry storage casks using external gamma flux measurements

Reuven Rachamin, Uwe Hampel

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

Abstract

The license for the storage of spent nuclear fuel assemblies in dry casks is limited to 40 years. In Germany, a site for a final repository of spent fuel is not yet available. Therefore, this license has to be renewed for prolonged storage period. Currently, there is no experience with dry cask storage worldwide that goes beyond a period of 40 years. Beside regulatory and security aspects, there are questions concerning the long-term integrity of the spent fuel assemblies as this is of relevance for final transportation and reloading to final waste repository casks. Once the cask is filled and sealed, the knowledge about the state of the fuel assemblies is limited. This study investigates the feasibility of using external gamma flux measurements to detect the state of the spent fuel assemblies inside the cask. Monte-Carlo simulations were performed to evaluate the gamma flux distribution outside the sidewall of a cask with all intact fuel assemblies and a cask with one damaged fuel assembly, mimicking a fuel assembly with expanded rods and fuel relocation. The evaluation was performed for different location of the damaged fuel assembly and different storage times. The results of the investigation showed that the intensity and the shape of the gamma flux outside the sidewall of the cask are sufficient to identify the damaged fuel assembly, in case it is located near the inner wall of the cask. The detection of the inner damaged fuel assemblies, however, is less feasible. Due to the self-shielding of the fuel assemblies, the gamma photons which come from the inner fuel assemblies stopped within the fuel basket and assemblies materials. The gamma photons which do survive the fuel assemblies self-shielding reach the inner cask wall with not enough energy to escape the shielding of the thick cast iron wall. In general, it can be concluded that the more the damaged fuel assembly is close to the cask inner walls and that the damage is in a large scale (i.e., significant fuel relocation), the more it can be detected by external gamma flux measurements.

Original languageEnglish
Title of host publication20th Topical Meeting of the Radiation Protection and Shielding Division, RPSD 2018
PublisherAmerican Nuclear Society
ISBN (Electronic)9780894487460
StatePublished - 1 Jan 2018
Externally publishedYes
Event20th Topical Meeting of the Radiation Protection and Shielding Division, RPSD 2018 - Santa Fe, United States
Duration: 26 Aug 201831 Aug 2018

Publication series

Name20th Topical Meeting of the Radiation Protection and Shielding Division, RPSD 2018

Conference

Conference20th Topical Meeting of the Radiation Protection and Shielding Division, RPSD 2018
Country/TerritoryUnited States
CitySanta Fe
Period26/08/1831/08/18

ASJC Scopus subject areas

  • Instrumentation
  • Radiation

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