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Featured researches published by Greg Oberson.


Archive | 2011

Overview of NRC Proactive Management of Materials Degradation (PMMD) Program

C. E. Gene Carpenter; Amy Hull; Greg Oberson

Materials degradation phenomena, if not appropriately managed, have the potential to adversely impact the design functionality and safety margins of nuclear power plant (NPP) systems, structures and components (SSCs). Therefore, the U.S. Nuclear Regulatory Commission (NRC) has initiated an over-the-horizon multi-year research Proactive Management of Materials Degradation (PMMD) Research Program, which is presently evaluating longer time frames (i.e., 80 or more years) and including passive long-lived SSCs beyond the primary piping and core internals, such as concrete containment and cable insulation. This will allow the NRC to (1) identify significant knowledge gaps and new forms of degradation; (2) capture current knowledge base; and, (3) prioritize materials degradation research needs and directions for future efforts. This effort is being accomplished in collaboration with the U.S. Department of Energy’s (DOE) LWR Sustainability (LWRS) program. This presentation will discuss the activities to date, including results, and the path forward.


Archive | 2011

SOAR: A MODEL FOR SCOPING OF OPTIONS AND ANALYZING RISK VERSION 1.0 USER GUIDE

Chris Markley; Osvaldo Pensado; Jin-Ping Gwo; James Winterle; Tae Ahn; Roland Benke; Tianqing Cao; Hipólito González; Anita Gray; Xihua He; Ronald Janetzke; Hundal Jung; Greg Oberson; Pavan K. Shukla; Timothy Sippel; Stuart A. Stothoff; Lynn Tipton


ECS Transactions | 2013

Chloride-Induced Stress Corrosion Cracking of Austenitic Stainless Steel Used for Dry Storage of Spent Nuclear Fuel

Tae M. Ahn; Greg Oberson; Sara DePaula


Corrosion | 2013

Coastal Salt Effects on the Stress Corrosion Cracking of Type 304 Stainless Steel

Todd S. Mintz; Larry Miller; Yi-Ming Pan; Xihua He; Roberto T. Pabalan; Leonardo Caseres; Greg Oberson; Darrell Dunn


Meeting Abstracts | 2012

Chloride-Induced Stress Corrosion Cracking of Austenitic Stainless Steel for Dry Storage of Spent Nuclear Fuel

Tae M. Ahn; Greg Oberson; Sara DePaula


educational data mining | 2017

NRC Perspectives on Primary Water Stress Corrosion Cracking of High-Chromium, Nickel-Based Alloys

Greg Oberson; Margaret Audrain; Jay Collins; Eric Reichelt


Corrosion | 2017

Assessment of Aging Mechanisms for Carbon Steel, Low-Alloy Steel, and Stainless Steel Components Exposed to Outdoor and Sheltered Environments in Spent Nuclear Fuel Dry Storage Systems

Xihua He; Yi-Ming Pan; R. A. Page; John Wise; Darrell Dunn; Greg Oberson; Matthew Hiser


Corrosion | 2016

Assessment of Aging Mechanisms for Stainless Steel-and Al-Based Neutron Absorbing Materials Used in Spent Nuclear Fuel Dry Cask Storage Systems

Xihua He; Yi-Ming Pan; R. A. Page; Emma Wong; Greg Oberson; Matthew Hiser; Darrell Dunn


Corrosion | 2014

Stress Corrosion Cracking of UNS S30400 Stainless Steel Exposed to Atmospheric Ammonium Nitrate and Sodium Chloride Mixtures

Xihua He; Todd S. Mintz; Darrell Dunn; Roberto T. Pabalan; Greg Oberson; Tae Ahn


Corrosion | 2014

Review and Assessment of Techniques for Monitoring Environmental Conditions and Stress Corrosion Cracking of Stainless Steel Canisters

Xihua He; Pavan K. Shukla; Yi-Ming Pan; Leonardo Caseres; Greg C. Willden; Darrell Dunn; Greg Oberson

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Xihua He

Southwest Research Institute

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Darrell Dunn

Nuclear Regulatory Commission

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Yi-Ming Pan

Southwest Research Institute

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Roberto T. Pabalan

Southwest Research Institute

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Larry Miller

Southwest Research Institute

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Leonardo Caseres

Southwest Research Institute

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Matthew Hiser

Nuclear Regulatory Commission

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Pavan K. Shukla

Southwest Research Institute

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R. A. Page

Southwest Research Institute

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Sara DePaula

Nuclear Regulatory Commission

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