Assessment of the leak tightness integrity of the steam generator tubes affected by ODSCC at the tube support plates [electronic resource]
Saved in:
| Online Access: |
Online Access (via OSTI) |
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| Corporate Author: | |
| Format: | Government Document Electronic eBook |
| Language: | English |
| Published: |
Richland, Wash. : Oak Ridge, Tenn. :
CH2M Hill, inc. ; distributed by the Office of Scientific and Technical Information, U.S. Department of Energy,
1997.
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| Subjects: |
| Abstract: | An EPRI report gives a method for predicting a conservative value of the total primary-to-secondary leak rate which may occur during, a postulated steam generator depressurization accident such as a Main Steam Line Break (MSLB) in a steam generator with axial through-wall ODSCC at the TSP intersections. The Belgian utility defined an alternative method deviating somewhat from the EPRI method. When reviewing this proposed method, the Belgian safety authorities performed some calculations to investigate its conservatism. This led them to recommend some modifications to the EPRI method which should reduce its undue conservatism while maintaining the objective of conservatism in the offsite dose calculations. |
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| Item Description: | Published through SciTech Connect. 02/01/1997. "nureg/cp--0154" " anl--96/14" "nea/cnra/r--(96)1" "conf-9510423--" "TI97004312" CNRA/CSNI workshop on steam generator tube integrity in nuclear power plants, Oak Brook, IL (United States), 30 Oct - 2 Nov 1995. Cuvelliez, Ch.; Roussel, G. [AIB-Vincotte Nuclear, Brussels (Belgium)] |
| Physical Description: | pp. 385-398 : digital, PDF file. |