J.D. Gilman

Modeling of fatigue crack growth rate for ferritic steels in light water reactor environments

Ernest D. Eason, E. E. Nelson, J.D. Gilman · Nuclear Engineering and Design · 1998 · 22 citations

Engineering, Corrosion, Mechanical Engineering +3

Analysis of pressure vessel steel fatigue tests in air

E.D. Eason, S. P. Andrew, S.B. Warmbrodt et al. · Nuclear Engineering and Design · 1989 · 18 citations

Engineering, Mechanical Engineering, Structural Health Monitoring +4

Three-Dimensional Analysis of Reactor Pressure Vessel Nozzles

Y.R. Rashid, J.D. Gilman · NCSU Libraries Repository (North Carolina State University Libraries) · 1971 · 17 citations · Full text

Three-dimensional Analysis, Engineering, Fluid Mechanics +5

Controlling stress corrosion cracking in boiling water reactors

Robin L. Jones, J.D. Gilman, J.L. Nelson · Nuclear Engineering and Design · 1993 · 16 citations

Water Reactors, Engineering, Corrosion +2

Technical Basis for a Revised Fatigue Crack Growth Rate Reference Curve for Ferritic Steels in Air

E.D. Eason, J.D. Gilman, D. P. Jones et al. · Journal of Pressure Vessel Technology · 1992 · 14 citations

Engineering, Mechanical Engineering, Section Xi +14