DataExpo GAKG DeepReport Navigation

Copyright©2015-2024 Acemap, Inc. Shanghai Jiao Tong University. All rights reserved.

沪ICP备18028330号

ES

E.P. Simonen

Pacific Northwest National Laboratory

Author Statistics

Papers

Citation

H-Index

i-10 index

Research Trends

Author Order

Document Type

Co-Authors

S.M. Bruemmer

Pacific Northwest National Laboratory

J.L. Brimhall

Pacific Northwest National Laboratory

Charles H. Henager

Pacific Northwest National Laboratory

L.A. Charlot

Pacific Northwest National Laboratory

Danny J. Edwards

Pacific Northwest National Laboratory

R.H. Jones

Pacific Northwest National Laboratory

J.S. Vetrano

Office of Basic Energy Sciences

R.H. Jones

Pacific Northwest National Laboratory

Gary S. Was

University of Michigan–Ann Arbor

H.E. Kissinger

Pacific Northwest National Laboratory

Cooperative Institutions

Pacific Northwest National Laboratory

Battelle

United States Department of Energy

United States Department of Commerce

National Technical Information Service

Westinghouse Electric (United States)

University of Michigan–Ann Arbor

Office of Scientific and Technical Information

Argonne National Laboratory

Idaho National Laboratory

Author Statistics

Papers

Citation

H-Index

i-10 index

Research Field

Tritium/hydrogen barrier development

Fusion Engineering and Design (1995)

G.W. Hollenberg E.P. Simonen G. Kalinin A. Terlain

Fusion power

Liquid metal

10.1016/0920-3796(95)90039-x

Cite

Citations (216)

Radiation-Induced Minor Element Segregation at Austenitic Stainless Steel Grain Boundaries

MRS Proceedings (1996)

E.P. Simonen S.M. Bruemmer

Austenitic stainless steel

10.1557/proc-439-569

Cite

Citations (0)

Early Stages Of Intergranular Stress Corrosion Cracking

CORROSION (1997)

R.H. Jones E.P. Simonen R.E. Williford

Environmental stress fracture

Cite

Citations (0)

Stage I stress corrosion cracking behavior

Materials Science and Engineering A (1993)

R.H. Jones E.P. Simonen

10.1016/0921-5093(93)90505-9

Cite

Citations (5)

Radiation-induced material changes and susceptibility to intergranular failure of light-water-reactor core internals

Journal of Nuclear Materials (1999)

S.M. Bruemmer E.P. Simonen P.M. Scott Peter L. Andresen Gary S. Was

Microchemistry

Light-water reactor

10.1016/s0022-3115(99)00075-6

Cite

Citations (354)

Defect-Solute Interactions Near Irradiated Grain Boundaries

MRS Proceedings (1993)

E.P. Simonen J.S. Vetrano H.L. Heinisch S.M. Bruemmer

Kirkendall Effect

Austenitic stainless steel

10.1557/proc-319-399

Cite

Citations (0)

Pulsed irradiation creep in nickel

Journal of Nuclear Materials (1981)

E.P. Simonen Charles H. Henager

10.1016/0022-3115(82)90778-4

Cite

Citations (10)

Diffusivities from the calculation and measurement of radiation kinetics

Lattice diffusion coefficient

Austenitic stainless steel

10.1007/bf03223264

Cite

Citations (1)

Radiation-Induced Grain Boundary Segregation in Austenitic Stainless Steels

Materials science forum (1998)

E.P. Simonen S.M. Bruemmer

Radiation-induced segregation (RIS) to grain boundaries in Fe-Ni-Cr-Si stainless alloys has been measured as a function of irradiation temperature and dose. Heavy-ion irradiation was used to produce damage levels from 1 to 20 displacements per atom (dpa) at temperatures from 175 to 550{degrees}C. Measured Fe, Ni, and Cr segregation increased sharply with irradiation dose (from G to 5 dpa) and temperature (from 175 to about 350{degrees}C). However, grain boundary concentrations did not change significantly as dose or temperatures were further increased. Although interfacial compositions were similar, the width of radiation-induced enrichment or depletion profiles increased consistently with increasing dose or temperature. Impurity segregation (Si and P) was also measured, but only Si enrichment appeared to be radiation-induced. Grain boundary Si peaked at levels approaching 10 at% after irradiation doses to 10 dpa at an intermediate temperature of 325{degrees}C. No evidence of grain boundary silicide precipitation was detected after irradiation at any temperature. Equilibrium segregation of P was measured in the high-P alloys, but interfacial concentration did not increase with irradiation exposure. Comparisons to reported RIS in neutron-irradiated stainless steels revealed similar grain boundary compositional changes for both major alloying and impurity elements.

Austenitic stainless steel

10.4028/www.scientific.net/msf.294-296.755

Cite

Citations (4)

Radiation Hardening and Radiation-Induced Chromium Depletion Effects on Intergranular Stress Corrosion Cracking in Austenitic Stainless Steels

CORROSION (1994)

S.M. Bruemmer E.P. Simonen

Abstract Radiation hardening and radiation-induced chromium (Cr) depletion were related to intergranular stress corrosion cracking (IGSCC) response among various stainless steels (SS). Available da...

Hardening (computing)

Austenitic stainless steel

10.5006/1.3293485

Cite

Citations (18)

More pages