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51316-7244-Eddy Current for Sizing Cracks in Canisters for Dry Storage Casks – Laboratory Measurements”

Picture for Eddy Current for Sizing Cracks in Canisters for Dry Storage Casks – Laboratory Measurements
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This paper will provide an overview of activities related to the nondestructive examination of dry storage casks for spent nuclear fuel.  The aim is to help ensure their integrity over extended interim storage periods.

Product Number: 51316-7244-SG
ISBN: 7244 2016 CP
Author: Ryan Meyer
Publication Date: 2016
Industries: Energy Generation , Corrosion Monitoring and Control
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Extended interim storage of spent nuclear fuel in dry storage casks increases the public safety concern related to possible spent fuel degradation as a consequence of aging of these systems before the spent fuel can be retrieved and shipped to a final repository. Measurements are thus necessary to help verify the integrity of these systems and justify the safety of extended interim dry storage. This paper will provide an overview of activities related to the nondestructive examination of dry storage casks to help ensure their integrity over extended interim storage periods.

Keywords:  downloadable, nuclear fuel, dry storage, safety, nondestructive inspection

Extended interim storage of spent nuclear fuel in dry storage casks increases the public safety concern related to possible spent fuel degradation as a consequence of aging of these systems before the spent fuel can be retrieved and shipped to a final repository. Measurements are thus necessary to help verify the integrity of these systems and justify the safety of extended interim dry storage. This paper will provide an overview of activities related to the nondestructive examination of dry storage casks to help ensure their integrity over extended interim storage periods.

Keywords:  downloadable, nuclear fuel, dry storage, safety, nondestructive inspection

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51316-7237-Corrosion Assessment of Nickel-based Alloy Candidates for SCWR Fuel Cladding

Product Number: 51316-7237-SG
ISBN: 7237 2016 CP
Author: Yimin Zeng
Publication Date: 2016
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Supercritical water-cooled reactor (SCWR) is an innovative Generation IV nuclear reactor. Nickel-based alloys, such as UNS N06625, UNS R20033 and UNS N07214 alloys, are selected for the fuel cladding. Knowledge gaps exist as regards their use for the fuel cladding in the SCWR. This paper introduces laboratory results on corrosion and stress corrosion cracking (SCC) of the nickel-based alloys.
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51316-7250-Sour Localized Pitting Corrosion Model of Carbon Steel: A Status Update

Product Number: 51316-7250-SG
ISBN: 7250 2016 CP
Author: Sankara Papavinasam
Publication Date: 2016
$20.00

The sour model had been previously developed to predict localized internal pitting corrosion of carbon steel. This model included the effects of carbon dioxide (CO2), crude oil, temperature, pressure, flow, sulfur, sulfates, bicarbonates, chlorides and microbiologically influenced corrosion (MIC). The paper discusses  field use, merits, precautions and parameterization in using the model.
Picture for Corrosion Risk Assessment and Cathodic Protection for Aging Electric Utility Transmission Sructures
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51316-7245-Corrosion Risk Assessment and Cathodic Protection for Aging Electric Utility Transmission Sructures

Product Number: 51316-7245-SG
ISBN: 7245 2016 CP
Author: Mehrooz Zamanzadeh
Publication Date: 2016
$20.00

Discussion on Transmission and Distribution (T&D) structures and system-wide cathodic protection as a mitigation technique. In general soil, corrosivity, lack of cathodic protection/coating, stray current AC interference and copper grounding should be considered in design of T&D structures.
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