Degraded piping program - phase II progress

Nuclear Engineering and Design

Volumn 98, Issue 2, 1987, Pages 195-217

  Wilkowski, G ^a   Ahmad, J ^a   Barnes, D ^a   Brust, F ^a   Ghadiali, N ^a   Guerrieri, D ^a   Kiefner, J ^a   Kramer, G ^a   Landow, M ^a   Marschall, C ^a   Maxey, W ^a   Nakagaki, M ^a   Papaspyropoulos, V ^a   Pasupathi, V ^a   Scott, P ^a  

^a BATTELLE MEMORIAL INSTITUTE   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

FRACTURE MECHANICS; NUCLEAR REACTORS - PIPING SYSTEMS; STAINLESS STEEL - CRACK PROPAGATION;

CRACKED PIPES; LIMIT-LOAD ANALYSES; NRC DEGRADED PIPING PROGRAM;

PIPING SYSTEMS;

EID: 0021776658     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/0029-5493(87)90166-X     Document Type: Article

References (14)

1. Degraded Piping Program - Phase II
2. Degraded Piping Program - Phase II
3. J-integral testing instability analysis for 8-inch diameter ASTM A106 steel pipe
4. Instability predictions for circumferentially cracked Type 304 stainless steel pipes under dynamic loading: Final Report
5. Instability testing of compact and pipe specimens utilizing a test system made compliant by computer control
6. Advances in elastic-plastic fracture analysis
7. The application of fracture proof design methods using tearing instability theory to nuclear piping postulating circumferential through wall cracks
8. NRC leakbefore-break (LBB.NRC) analysis method for circumferentially through-wall cracked pipes under axial plus bending loads
9. Effects of flaw shape on J-resistance curve of a circumferentially cracked pipe
10. Material resistance and instability beyond J-controlled crack growth
11. Investigation of the initiation and extent of ductile pipe rupture, Task 17
12. Degraded Piping Program - Phase II
13. Reactor Primary Coolant System Study Quarterly Progress Report No. 16
14. Flaw Evaluation Procedures for Ferritic Piping