Failure and leakage through circumferential cracks in steam generator tubing during accident conditions-Reference-Cited by-同舟云学术

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Failure and leakage through circumferential cracks in steam generator tubing during accident conditions

Published:1999-10 Issue:12 Volume:76 Page:839-847
ISSN:0308-0161
Container-title:International Journal of Pressure Vessels and Piping
language:en
Short-container-title:International Journal of Pressure Vessels and Piping

Author:

Majumdar S

Publisher

Elsevier BV

Subject

Mechanical Engineering,Mechanics of Materials,General Materials Science

Reference10 articles.

1. Ranganath S, Mehta HS. Engineering methods for the assessment of ductile fracture margin in nuclear power plant piping. Fracture Resistance Curves and Engineering Applications. ASTM STP 803, Philadelphia, 1983.

2. Hernalsteen P. Presented at the NEA/CNRA/CSNI Workshop on Steam Generator Integrity in Nuclear Power Plants. Oak Brook, IL, 30 Oct–2 Nov 1995.

3. Wilkowski GM. Degraded-Piping Program–Phase II. Semiannual Report. NUREG/CR-4082, vols. 1–8, USNRC, Washington DC, 1984–1989.

4. Wilkowski GM. Short Cracks in Piping and Piping Welds, Semiannual Report. NUREG/CR-4599, vols. 1–3, USNRC, Washington DC, 1991–1994.

5. Tada H, Paris PC, Gamble RM. A stability analysis of circumferential cracks for reactor piping systems”. Fracture Mechanics. ASTM STP 700, Philadelphia, 1980.

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2. J -resistance curves for Inconel 690 and Incoloy 800 nuclear steam generators tubes at room temperature and at 300 °C;Journal of Nuclear Materials;2017-04

3. Structural integrity assessment of nuclear steam generator;Steam Generators for Nuclear Power Plants;2017

4. Experimental determination of J-resistance curves of nuclear steam generator tubes;Engineering Fracture Mechanics;2016-09

5. Structural integrity assessments of steam generator tubes using the FAD methodology;Nuclear Engineering and Design;2015-12

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