Assessment of spent nuclear fuel during dry storage in casks with fuel rod performance codes - TÜV NORD EnSys approach for fuel rod performance calculation for an extended dry storage period

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dc.contributor.authorGerold Spykman (TÜV NORD EnSys GmbH & Co.KG, Hannover)
dc.date.accessioned2023-04-12T01:13:44Z
dc.date.available2023-04-12T01:13:44Z
dc.date.issued2022-07-10
dc.identifier.urihttps://www.lib.ncsu.edu/resolver/1840.20/40612
dc.publisherIASMiRT
dc.relation.ispartofseriesD09 - Fuel Cycle Facilities, Waste Management and Decommissioning
dc.relation.ispartofseriesD09-Tu.2.F - D09 - Spent Fuel Storage and Transportation
dc.relation.ispartofseries00 - SMiRT 26 - Berlin/Potsdam, Germany. July 10-15, 2022
dc.titleAssessment of spent nuclear fuel during dry storage in casks with fuel rod performance codes - TÜV NORD EnSys approach for fuel rod performance calculation for an extended dry storage period
dc.typeConference Proceeding

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