Caple AUF900 Uživatelský manuál stáhnout pdf (Strana 166)

164

ENSI Erfahrungs- und Forschungsbericht 2011

7. Publications

❚ G. Qian, M. Niffenegger, S. Li, Probabilistic

analysis of pipelines with corrosion defects by

using FITNET FFS procedure, Corrosion Science,

53(2011) 855-61.

❚ G. Qian, M. Niffenegger, Probabilistic fracture

assessment of piping systems based on FITNET

FFS procedure, Nuclear Engineering and Design,

241 (2011) 714-22.

❚ Y. Hong, G. Qian, Effect of aqueous environment

on high cycle and very-high-cycle fatigue beha-

viour for a structural steel, Key Engineering Ma-

terials, 462-463 (2011) 355-360.

❚ Y. Hong, A. Zhao, G. Qian, C. Zhou, Fatigue

strength and crack initiation mechanism of ve-

ry-high-cycle fatigue for low alloy steels, Metal-

lurgical & Materials Transactions A, 2011, DOI:

10.1007/s11661-011-0816-7.

8. Conferences and Seminars

❚ NULIFE network meeting, September 11–15,

2011, Espoo, Finland.

❚ SMiRT 21, November 5–12, 2011, New Delhi,

India.

9. References

[1] M. Niffenegger, H.P. Seifert, Projektantrag PISA

zu Handen des ENSI, AN-46-09-03, 10.1.2009.

[2] ENSI Research Report 2010.

[3] S. Chapuliot et al., WPS Criterion propositi-

on based on experimental database interpre-

tation, Fontevraud 7, 26–30 September 2010

Contribution of Materials Investigations to im-

prove the Safety and Performance of LWRs, pa-

per reference no.A0141.

[4] U. Alsmann, Werkstoffmechanische Untersu-

chungen zu den Mechanismen des Vorbelas-

tungseffekts, Diss. MPA Stuttgart 2002.

[5] R. Beleznai and Sz. Szavai, Analysis of Warm

Prestressing effect on fracture toughness of re-

actor pressure vessel steels, Strength of Mate-

rials, Vol. 42, No. 1, 2010.

[6] D. Moinereau et al., NESC VII (2008–2012), A

European project (NESC VII) for the application

of WPS in RPV assessment including biaxial loa-

ding, Status September 2011.

[7] M. EricksonKirk, et al., Technical Basis for Re-

vision of the Pressurized Thermal Shock (PTS)

Screening Limit in the PTS Rule (10CFR 50.61):

Summary Report, NUREG 1806, U.S. Nuclear

Regulatory Commission, Rockville, MD, May,

2006.

[8] U.S. Nuclear Regulatory Commission, Regu-

latory Guide 1.154, Format and Content of

Plant-Specific Pressurized Thermal Shock Safe-

ty Analysis Reports for Pressurized Water Reac-

tors, 1987.

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