Application of the cracked pipe element to creep crack growth prediction

Conference · Tue Apr 01 00:00:00 EST 1997

OSTI ID:489308

Brochard, J; Charras, T ^[1]; Ghoudi, M ^[2]

---

1. C.E.A.-C.E.-Saclay DRN/DMT, Gif Sur Yvette (France)
2. C.E.A.-C.E.-Saclay, Gif Sur Yvette (France)

Modifications to a computer code for ductile fracture assessment of piping systems with postulated circumferential through-wall cracks under static or dynamic loading are very briefly described. The modifications extend the capabilities of the CASTEM2000 code to the determination of fracture parameters under creep conditions. The main advantage of the approach is that thermal loads can be evaluated as secondary stresses. The code is applicable to piping systems for which crack propagation predictions differ significantly depending on whether thermal stresses are considered as primary or secondary stresses.

• Research Organization: US Nuclear Regulatory Commission (NRC), Washington, DC (United States). Div. of Engineering Technology; Electricite de France (EDF), 69 - Villeurbanne (France); Battelle Memorial Inst., Columbus, OH (United States)
• OSTI ID: 489308
• Report Number(s): NUREG/CP-0155; CONF-9510432-; ON: TI97004806; TRN: 97:011448
• Resource Relation: Conference: Seminar on leak before break in reactor piping and vessels, Lyon (France), 9-11 Oct 1995; Other Information: PBD: Apr 1997; Related Information: Is Part Of Proceedings of the seminar on leak before break in reactor piping and vessels; Faidy, C. [ed.] [Electricite de France, Villeurbanne (France)]; Gilles, P. [ed.] [Framatome, Paris (France)]; PB: 773 p.
• Country of Publication: United States
• Language: English

Related Subjects

22 NUCLEAR REACTOR TECHNOLOGY
21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS
PIPES
LEAKS
CRACK PROPAGATION
THERMAL STRESSES
SAFETY ANALYSIS
C CODES