Safety and availability of steam generator tubes affected by secondary side corrosion

Nuclear Engineering and Design

Volumn 185, Issue 1, 1998, Pages 11-21

  Dvorsek T ^a   Cizelj, L ^a   Mavko, B ^a  

^a JO EF STEFAN INSTITUTE   (Slovenia)

Author keywords

[No Author keywords available]

Indexed keywords

ACCIDENT PREVENTION; AVAILABILITY; DEFECTS; LEAKAGE (FLUID); MATHEMATICAL MODELS; NICKEL ALLOYS; NUMERICAL ANALYSIS; PRESSURIZED WATER REACTORS; PREVENTIVE MAINTENANCE; PROBABILITY; SENSITIVITY ANALYSIS; STRESS CORROSION CRACKING;

STEAM GENERATOR TUBES;

SUPERHEATER TUBES;

EID: 0032154372     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/s0029-5493(98)00228-3     Document Type: Article

References (14)

1. ASME, 1986. Boiler and Pressure Vessel Code, Section XI.
2. Cizelj, L., Mavko, B., Riesch-Oppermann, H., 1994. Application of first and second order reliability methods on the safety assessment of steam generator tubing. Nucl. Eng. Des. 147, 359-368.
3. Cizelj, L., et al, 1995. Safety Analysis of Krško NPP Steam Generator Tubes Damaged by Outside Diameter Stress Corrosion Cracking at Tube Support Plates. Report No. IJS-DP-7175, Rev. 0, J. Stefan Institute, Ljubljana, Slovenia, proprietary.
4. Cizelj, L.H., Riesch-Oppermann, 1991. ZERBERUS - the Code for Reliability Analysis of Crack Containing Structures. Report KfK 5019, Kernforschungszentrum Karlsruhe, Germany.
5. Cizelj, L., Mavko, B., Riesch-Oppermann, H., 1996. On the Probabilistic Approaches Applied to the Maintenance of Degraded Steam Generator Tubes. CSNI-PW3 Workshop on Probabilistic Structural Integrity Analysis and its Relationship to Deterministic Analysis, NEA/CSNI/R (96) 4 (1996), Stockholm, Sweden, 28 February-1 March, pp. 261-272.
6. Cizelj, L., Mavko, B., Vencelj, P., 1996a. Reliability of steam generator tube with axial cracks, service experience and reliability improvement. J. Press. Vessel Technol., Trans. ASME 118 (4), 441-446.
7. Cizelj, L., Soršek, I., Roussel, G., Cuvelliez, Ch., 1996b. Some Comments on the Probabilistic Modeling of Leak Rates Through Degraded SG Tubing. 15th EPRI Steam Generator NDE Workshop, EPRI Report No. TR-107161, Long Beach, CA, USA, 29-31 July, pp. 31/1-31/10.
8. Clark, R.A., Kurtz, R.J. 1988. Compendium and Comparison of International Practice for Plugging, Repair and Inspection of Steam Generator Tubing, NUREG/CR-5016.
9. Dvoršek, T., 1996. Comparison of Maintenance Strategies Applied to Steam Generator Tube (in Slovene), M.Sc. Thesis, University of Ljubljana, Slovenia.
10. EPRI Steam Generator Degradation Specific Management (Draft), 1993. EPRI Report No. TR-103017.
11. Inetec, 1996. Results of Revaluation of EC Data Under TSP and Their Statistic Analysis, Final Report, Rev. 3.
12. MacDonald, P.E., Maruska, C. Shah, V.N. 1995. Assessment and Management of Ageing of Major Nuclear Power Plant Components: Steam Generators (Draft), Safety Series, International Atomic Energy Agency, Vienna, Austria.
13. Mavko, B., Cizelj, L., 1992. Failure probability of axially cracked steam generator tubes: a probabilistic fracture mechanics model. Nucl. Technol. 98 (2), 171-177.
14. NPP Krško, 1997. Technical Specification, Rev. 50. US NRC, 1993. Voltage-Based Interim Plugging Criteria for Steam Generator Tubes, Draft report NUREG-1477, Washington DC.