Author Information

Ronald Adamson

Affiliation: Zircology Plus

Address:
36848 Montecito Dr
Fremont, California 94536
United States

Other Names:
R. Adamson; R. B. Adamson; Ronald B. Adamson; Ronald B. Adamson

Publications


An Overview of Microstructural and Experimental Factors That Affect the Irradiation Growth Behavior of Zirconium Alloys

STP28108S
R. B. Adamson
General Electric Company


Beta-Quenched Zircaloy-4: Effects of Thermal Aging and Neutron Irradiation

STP18881S
Ronald B. Adamson
GE Nuclear Energy


Corrosion Behavior of Irradiated Zircaloy

STP15200S
Ronald B. Adamson
GE Nuclear Energy


Degraded Fuel Cladding Fractography and Fracture Behavior

STP14306S
Ronald B. Adamson
General Electric Co., Vallecitos Nuclear Center


Development of a Sensitive and Reproducible Steam Test for Zircaloy Nodular Corrosion

STP28124S
R. B. Adamson
General Electric Company


Development of New Zirconium Alloys for a BWR

STP16203S
Ronald B. Adamson
GE Nuclear Energy


Effect of Alloying Elements, Cold Work, and Hydrogen on the Irradiation-Induced Growth Behavior of Zirconium Alloy Variants

STP159720160040
Ronald Adamson
Zircology Plus


Effect of Hydrogen on Dimensional Changes of Zirconium and the Influence of Alloying Elements: First-Principles and Classical Simulations of Point Defects, Dislocation Loops, and Hydrides

STP154320120170
R. B. Adamson
Zircology Plus


Effect of Ion Irradiation on Microstructure and Hardness in Zircaloy-4

JAI11316
R. B. Adamson
Zircology Plus


Effect of Ion Irradiation on Microstructure and Hardness in Zircaloy-4

STP11271S
R. B. Adamson
Zircology Plus


Effects of Neutron Irradiation on Microstructure and Properties of Zircaloy

MNL12117R
Ronald B. Adamson
Vallecitos Nuclear Center


Effects of Neutron Irradiation on Microstructure and Properties of Zircaloy

STP14292S
Ronald B. Adamson
GE Nuclear Energy


Effects of Thermomechanical Processing on In-Reactor Corrosion and Post-Irradiation Mechanical Properties of Zircaloy-2

STP16199S
Ronald B. Adamson
Vallecitos Nuclear Center


Failure Strain for Irradiated Zircaloy Based on Subsized Specimen Testing and Analysis

STP33001S
R. B. Adamson
General Electric Company


Fatigue Behavior of Irradiated and Unirradiated Zircaloy and Zirconium

STP15206S
Ronald B. Adamson
GE Nuclear Energy


High-Fluence Irradiation Growth of Zirconium Alloys at 644 to 725 K

STP34484S
Ronald B. Adamson
General Electric Co.


High-Temperature Irradiation Growth in Zircaloy

STP37056S
R. B. Adamson
Vallecitos Nuclear Center


Irradiation Growth of Zircaloy

STP35579S
R. B. Adamson
Vallecitos Nuclear Center


Mechanistic Studies of Zircaloy Nodular Corrosion

STP28134S
R. B. Adamson
General Electric Company


Modeling of Localized Deformation in Neutron Irradiated Zircaloy-2

STP35582S
R. B. Adamson
General Electric Company


Performance of Irradiated Copper and Zirconium Barrier-Modified Zircaloy Cladding Under Simulated Pellet-Cladding Interaction Conditions

STP36676S
R. B. Adamson
Vallecitos Nuclear Center


Post-Irradiation Characterization of Ultra-High-Fluence Zircaloy-2 Plate

STP14299S
R. B. Adamson
GE Nuclear Energy


Round-Robin Testing of Fracture Toughness Characteristics of Thin-Walled Tubing

STP48138S
R. Adamson
Zircology Plus


Round-Robin Testing of Fracture Toughness Characteristics of Thin-Walled Tubing

JAI101140
R. Adamson
Zircology Plus


Texture Measurement Techniques for Zircaloy Cladding: A Round-Robin Study

STP37045S
R. B. Adamson
General Electric Co.


Understanding Irradiation Growth through Atomistic Simulations: Defect Diffusion and Clustering in α-Zirconium and the Influence of Alloying Elements

STP159720160093
Ronald B. Adamson
Zircology Plus


Use of Ion Bombardment to Study Irradiation Damage in Zirconium Alloys

STP32117S
R. B. Adamson
General Electric Co.


Zircaloy-2 Lined Zirconium Barrier Fuel Cladding

STP16196S
Ronald B. Adamson
General Electric Nuclear Energy


Zirconium-Barrier Cladding Attributes

STP28152S
R. B. Adamson
Vallectios Nuclear Center


StockCodeTitlePublished AsAffiliationPub Date by Most Viewed
STP28108S An Overview of Microstructural and Experimental Factors That Affect the Irradiation Growth Behavior of Zirconium Alloys R. B. Adamson General Electric Company 01 January 1987
STP18881S Beta-Quenched Zircaloy-4: Effects of Thermal Aging and Neutron Irradiation Ronald B. Adamson GE Nuclear Energy 01 January 1989
STP15200S Corrosion Behavior of Irradiated Zircaloy Ronald B. Adamson GE Nuclear Energy 01 January 1994
STP14306S Degraded Fuel Cladding Fractography and Fracture Behavior Ronald B. Adamson General Electric Co., Vallecitos Nuclear Center 01 January 2000
STP28124S Development of a Sensitive and Reproducible Steam Test for Zircaloy Nodular Corrosion R. B. Adamson General Electric Company 01 January 1987
STP16203S Development of New Zirconium Alloys for a BWR Ronald B. Adamson GE Nuclear Energy 01 January 1996
STP159720160040 Effect of Alloying Elements, Cold Work, and Hydrogen on the Irradiation-Induced Growth Behavior of Zirconium Alloy Variants Ronald Adamson Zircology Plus 01 January 2018
STP154320120170 Effect of Hydrogen on Dimensional Changes of Zirconium and the Influence of Alloying Elements: First-Principles and Classical Simulations of Point Defects, Dislocation Loops, and Hydrides R. B. Adamson Zircology Plus 30 January 2015
JAI11316 Effect of Ion Irradiation on Microstructure and Hardness in Zircaloy-4 R. B. Adamson Zircology Plus 07 April 2004
STP11271S Effect of Ion Irradiation on Microstructure and Hardness in Zircaloy-4 R. B. Adamson Zircology Plus 01 January 2004
MNL12117R Effects of Neutron Irradiation on Microstructure and Properties of Zircaloy Ronald B. Adamson Vallecitos Nuclear Center 01 January 2010
STP14292S Effects of Neutron Irradiation on Microstructure and Properties of Zircaloy Ronald B. Adamson GE Nuclear Energy 01 January 2000
STP16199S Effects of Thermomechanical Processing on In-Reactor Corrosion and Post-Irradiation Mechanical Properties of Zircaloy-2 Ronald B. Adamson Vallecitos Nuclear Center 01 January 1996
STP33001S Failure Strain for Irradiated Zircaloy Based on Subsized Specimen Testing and Analysis R. B. Adamson General Electric Company 01 January 1986
STP15206S Fatigue Behavior of Irradiated and Unirradiated Zircaloy and Zirconium Ronald B. Adamson GE Nuclear Energy 01 January 1994
STP34484S High-Fluence Irradiation Growth of Zirconium Alloys at 644 to 725 K Ronald B. Adamson General Electric Co. 01 January 1984
STP37056S High-Temperature Irradiation Growth in Zircaloy R. B. Adamson Vallecitos Nuclear Center 01 January 1982
STP35579S Irradiation Growth of Zircaloy R. B. Adamson Vallecitos Nuclear Center 01 January 1977
STP28134S Mechanistic Studies of Zircaloy Nodular Corrosion R. B. Adamson General Electric Company 01 January 1987
STP35582S Modeling of Localized Deformation in Neutron Irradiated Zircaloy-2 R. B. Adamson General Electric Company 01 January 1977
STP36676S Performance of Irradiated Copper and Zirconium Barrier-Modified Zircaloy Cladding Under Simulated Pellet-Cladding Interaction Conditions R. B. Adamson Vallecitos Nuclear Center 01 January 1979
STP14299S Post-Irradiation Characterization of Ultra-High-Fluence Zircaloy-2 Plate R. B. Adamson GE Nuclear Energy 01 January 2000
STP48138S Round-Robin Testing of Fracture Toughness Characteristics of Thin-Walled Tubing R. Adamson Zircology Plus 01 January 2009
JAI101140 Round-Robin Testing of Fracture Toughness Characteristics of Thin-Walled Tubing R. Adamson Zircology Plus 28 February 2008
STP37045S Texture Measurement Techniques for Zircaloy Cladding: A Round-Robin Study R. B. Adamson General Electric Co. 01 January 1982
STP159720160093 Understanding Irradiation Growth through Atomistic Simulations: Defect Diffusion and Clustering in α-Zirconium and the Influence of Alloying Elements Ronald B. Adamson Zircology Plus 01 January 2018
STP32117S Use of Ion Bombardment to Study Irradiation Damage in Zirconium Alloys R. B. Adamson General Electric Co. 01 January 1974
STP16196S Zircaloy-2 Lined Zirconium Barrier Fuel Cladding Ronald B. Adamson General Electric Nuclear Energy 01 January 1996
STP28152S Zirconium-Barrier Cladding Attributes R. B. Adamson Vallectios Nuclear Center 01 January 1987