ML18023A085: Difference between revisions

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{{#Wiki_filter:U.S. Nuclear Regulatory Commission PublishedNUREG/CR-7225 -Stability of Circumferential Flaws in Once-Through Steam Generator Tubes under Thermal Loading during LOCA, MSLB, and FWLB (November 2017, ML17324B296)
{{#Wiki_filter:RECENT NUREG PUBLICATIONS Published NUREG/CR-7225 - Stability of Circumferential Flaws in Once-Through Steam Generator Tubes under Thermal Loading during LOCA, MSLB, and FWLB (November 2017, ML17324B296)
In PublicationNUREG/CR-7210 -Development and Validation of Models for Predicting Leakage from Degraded Tube-to-Tubesheet Joints during Severe Accidents 1RECENT NUREG PUBLICATIONS}}
In Publication NUREG/CR-7210 - Development and Validation of Models for Predicting Leakage from Degraded Tube-to-Tubesheet Joints during Severe Accidents U.S. Nuclear Regulatory Commission 1}}

Latest revision as of 03:29, 22 October 2019

2018 January SGTF - NRC Slide - NUREGs
ML18023A085
Person / Time
Issue date: 01/23/2018
From:
Office of Nuclear Reactor Regulation
To:
References
Download: ML18023A085 (1)


Text

RECENT NUREG PUBLICATIONS Published NUREG/CR-7225 - Stability of Circumferential Flaws in Once-Through Steam Generator Tubes under Thermal Loading during LOCA, MSLB, and FWLB (November 2017, ML17324B296)

In Publication NUREG/CR-7210 - Development and Validation of Models for Predicting Leakage from Degraded Tube-to-Tubesheet Joints during Severe Accidents U.S. Nuclear Regulatory Commission 1