Concrete Shield Performance of the VSC-17 Spent Nuclear Fuel Cask

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In 2003, representatives from the Central Research Institute of Electric Power Industry (CRIEPI) requested development of a project with the objective of determining the performance of a concrete spent nuclear fuel storage cask. Radiation and environmental effects may cause chemical alteration of the concrete that could result in excessive cracking, spalling, and loss of compressive strength. The Idaho National Laboratory (INL) project team and CRIEPI representatives identified the Ventilated Storage Cask (VSC-17) spent nuclear fuel storage cask as a candidate to study cask performance, because it had been used to store fuel as part of a dry cask storage demonstration ... continued below

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Morton, Sheryl L.; Winston, Philip L.; Saegusa, Toshiari; Shirai, Koji; Sasahara, Akihiro & Hattori, Takatoshi April 1, 2006.

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In 2003, representatives from the Central Research Institute of Electric Power Industry (CRIEPI) requested development of a project with the objective of determining the performance of a concrete spent nuclear fuel storage cask. Radiation and environmental effects may cause chemical alteration of the concrete that could result in excessive cracking, spalling, and loss of compressive strength. The Idaho National Laboratory (INL) project team and CRIEPI representatives identified the Ventilated Storage Cask (VSC-17) spent nuclear fuel storage cask as a candidate to study cask performance, because it had been used to store fuel as part of a dry cask storage demonstration project for more than 15 years. The project involved investigating the properties of the concrete shield. INL performed a survey of the cask in the summers of 2003 and 2004. Preliminary cask evaluations performed in 2003 indicated that the cask has no visual degradation. However, a 4-5 mrem/hr step-change in the radiation levels about halfway up the cask and a localized hot spot beneath an upper air vent indicate that there may be variability in the density of the concrete or localized cracking. In 2005, INL and CRIEPI scientists performed additional surveys on the VSC-17 cask. This document summarizes the methods used on the VSC-17 to evaluate the cask for compressive strength, concrete cracking, concrete thickness, and temperature distribution.

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  • International High-Level Radioactive Waste Management Conference,Las Vegas, Nevada,04/20/2006,05/04/2006

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  • Report No.: INL/CON-05-00895
  • Grant Number: DE-AC07-99ID-13727
  • Office of Scientific & Technical Information Report Number: 911595
  • Archival Resource Key: ark:/67531/metadc889324

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  • April 1, 2006

Added to The UNT Digital Library

  • Sept. 22, 2016, 2:13 a.m.

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  • Nov. 7, 2016, 7:20 p.m.

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Morton, Sheryl L.; Winston, Philip L.; Saegusa, Toshiari; Shirai, Koji; Sasahara, Akihiro & Hattori, Takatoshi. Concrete Shield Performance of the VSC-17 Spent Nuclear Fuel Cask, article, April 1, 2006; [Idaho Falls, Idaho]. (digital.library.unt.edu/ark:/67531/metadc889324/: accessed September 24, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.