G. Was
Materials Chemistry · 2002–2019
A researcher in the Science corpus: 17 papers; trusts 3 researchers and is trusted by 28 researchers here, as inferred from the citation graph.
Subfields
- Materials Chemistry — 75 citations into it; #902 of 11,513 by trust here, #3,093 by citations
Whom G. Was trusts overall
Their strongest outbound trust, strongest first, inferred from their citations.
Who trusts G. Was overall
Papers from G. Was's perspective
Ordered by how strongly the researchers G. Was trusts endorse each paper. Same corpus, a different order for every researcher.
- Materials Challenges for Advanced Nuclear Energy Systems
- Microstructure of Neutron-irradiated Iron Before and After Tensile Deformation
- The glide of screw dislocations in bcc Fe: Atomistic static and dynamic simulations ☆
- Electronic origin of the anomalous stability of Fe-rich bcc Fe-Cr alloys
- Self-interstitial atom defects in bcc transition metals: Group-specific trends
- A ‘magnetic’ interatomic potential for molecular dynamics simulations
- TEM characterization of structure and composition of nanosized ODS particles in reduced activation ferritic martensitic steels
- On the potentiality of using ferritic/martensitic steels as structural materials for fusion reactors
- Status of reduced activation ferritic/martensitic steel development
- Ab initio study of helium in α-Fe : Dissolution, migration, and clustering with vacancies
Their papers
- Fundamentals of Radiation Materials Science: Metals and Alloys (2007) — 1,096 citations
- On the use of SRIM for computing radiation damage exposure (2013) — 1,458 citations
- Fundamentals of radiation materials science (2007) — 774 citations
- Materials Challenges in Nuclear Energy (2013) — 2,378 citations
- Materials Challenges for Advanced Nuclear Energy Systems (2009) — 148 citations
- The relationship between hardness and yield stress in irradiated austenitic and ferritic steels (2005) — 489 citations
- Corrosion and stress corrosion cracking in supercritical water (2007) — 411 citations
- Novel features of radiation-induced segregation and radiation-induced precipitation in austenitic stainless steels (2011) — 190 citations
- Zirconium alloys for supercritical water reactor applications: Challenges and possibilities (2006) — 159 citations
- Materials for future nuclear energy systems (2019) — 312 citations
- Radiation damage and irradiation-assisted stress corrosion cracking of additively manufactured 316L stainless steels (2019) — 151 citations
- Challenges to the use of ion irradiation for emulating reactor irradiation (2015) — 258 citations
- Emulation of reactor irradiation damage using ion beams (2014) — 308 citations
- Assessment of radiation-induced segregation mechanisms in austenitic and ferritic–martensitic alloys (2011) — 148 citations
- Oxidation of ferritic–martensitic alloys T91, HCM12A and HT-9 in supercritical water (2007) — 181 citations
- Microstructural evolution of proton irradiated T91 (2006) — 146 citations
- Isolating the effect of radiation-induced segregation in irradiation-assisted stress corrosion cracking of austenitic stainless steels (2002) — 137 citations