Author

N. D. Ghadiali

Observed names: Ghadiali N., N Ghadiali, N. Ghadiali, ND Ghadiali, Nu Ghadiali

Institution: Battelle

Observed institution: Battelle

OpenAlex ID: A5111502285

Crack-opening-area analyses for circumferential through-wall cracks in pipes—Part I: analytical models

1998 · S. Rahman, F.W. Brust, et al. · International Journal of Pressure Vessels and Piping · 55

Probabilistic pipe fracture evaluations for leak-rate-detection applications

1995 · Nuclear Regulatory Commission, Washington, DC (United States). Div. of Engineering Technology, S Rahman, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 40

Crack-opening-area analyses for circumferential through-wall cracks in pipes—Part II: model validations

1998 · S Rahman, F.W Brust, et al. · International Journal of Pressure Vessels and Piping · 38

Short Cracks in Piping and Piping Welds

1991 · US Nuclear Regulatory Commission (NRC), Washington, DC (United States). Div. of Engineering, G. Wilkowski, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 36

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Refinement and evaluation of crack-opening-area analyses for circumferential through-wall cracks in pipes

A computer model for probabilistic leak-rate analysis of nuclear piping and piping welds

1997 · S. Rahman, N. Ghadiali, et al. · International Journal of Pressure Vessels and Piping · 26

Degraded piping program - phase II progress

1987 · G. Wilkowski, J. Ahmad, et al. · Nuclear Engineering and Design · 25

Crack-opening-area analyses for circumferential through-wall cracks in pipes—Part III: off-center cracks, restraint of bending, thickness transition and weld residual stresses

1998 · S. Rahman, N. Ghadiali, et al. · International Journal of Pressure Vessels and Piping · 24

Degraded piping program -- Phase II: Summary of technical results and their significance to leak-before-break and in-service flaw acceptance criteria, March 1984--January 1989

1989 · G. M. Wilkowski, J. Ahmad, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 20

Elastic-Plastic Analysis of Small Cracks in Tubes

1995 · F. W. Brust, S. Rahman, et al. · Journal of Offshore Mechanics and Arctic Engineering · 17

Effects of off-centered cracks and restraint of induced bending caused by pressure on the crack-opening-area analysis of pipes

1996 · S. Rahman, N. Ghadiali, et al. · Nuclear Engineering and Design · 16

Deterministic and probabilistic evaluations for uncertainty in pipe fracture parameters in leak-before-break and in-service flaw evaluations

1996 · Nuclear Regulatory Commission, Washington, DC (United States). Div. of Engineering Technology, N Ghadiali, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 9

Pipe Axial Flaw Failure Criteria (PAFFC): Version 1.0 user`s manual and software

1994 · Brian N. Leis, N. Ghadiali · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 9

SQUIRT. Seepage Quantification of Upsets In Reactor Tubes

1994 · D. Paul, N. Ghadiali, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 8

Development of a New Generation Computer Code (PRO-LOCA) for the Prediction of Break Probabilities for Commercial Nuclear Power Plants Loss-of-Coolant Accidents

2006 · David L. Rudland, Heqin Xu, et al. · ASME Pressure Vessels and Piping Conference (PVP) · 7

Effects of toughness anisotropy and combined tension, torsion, and bending loads on fracture behavior of ferritic nuclear pipe

1995 · Battelle, Columbus, OH (United States), R Mohan, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 7

A finite element algorithm to study creep cracks based on the creep hardening surface

1995 · P. Krishnaswamy, F. W. Brust, et al. · International Journal for Numerical Methods in Engineering · 6

Finite Element Analysis of History-Dependent Damage in Time-Dependent Fracture Mechanics

1993 · P. Krishnaswamy, F. W. Brust, et al. · Journal of Pressure Vessel Technology · 5

Fracture mechanics database for nuclear piping materials (PIFRAC)

1996 · N. Ghadiali, G. Wilkowski · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 4

L51720 Pipe Axial Flaw Failure Criteria - PAFFC Version 1.0 Users Manual and Software

1994 · B.N. Leis, N. D. Ghadiali · 4

Development of a J-estimation scheme for internal circumferential and axial surface cracks in elbows

1996 · Nuclear Regulatory Commission, Washington, DC (United States). Div. of Engineering Technology, R Mohan, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 3

Fracture Tolerance Analysis of the Solid Rocket Booster Servo-Actuator for the Space Shuttle

1982 · SH Smith, ND Ghadiali, et al. · 2

An Approach to Life Prediction of Domestic Gas Furnace Clam Shell Type Heat Exchangers

1980 · Brian Leis, Allen Hopper, et al. · Springer eBooks · 2

Determination of crack morphology parameters from service failures for leak-rate analyses

1997 · Gery Wilkowski, N. Ghadiali, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 1

The Effect of Constraint Due to Out-of-Plane Stress Field on Fracture of Reactor Pressure Vessel Steel--An Experimental and Numerical Study

1995 · DL Rudland, R Mohan, et al. · 1

Works count: 38

Citation count: 393

H-index: 11

I10-index: 11