J. Bischoff
2012–2020
A researcher in the Science corpus: 3 papers; trusts 0 researchers and is trusted by 0 researchers here, as inferred from the citation graph.
Papers from J. Bischoff's perspective
Ordered by how strongly the researchers J. Bischoff trusts endorse each paper. Same corpus, a different order for every researcher.
- High Chromium Ferritic and Martensitic Steels for Nuclear Applications
- Accident tolerant fuels for LWRs: A perspective
- Adhesion property and high-temperature oxidation behavior of Cr-coated Zircaloy-4 cladding tube prepared by 3D laser coating
- Silicon Carbide Oxidation in Steam up to 2 MPa
- Corrosion of Zirconium Alloys Used for Nuclear Fuel Cladding
- Optimization of grain boundary character distribution for intergranular corrosion resistant 304 stainless steel by twin-induced grain boundary engineering
- Structure of zirconium alloy oxides formed in pure water studied with synchrotron radiation and optical microscopy: relation to corrosion rate
- Hydrogen pickup measurements in zirconium alloys: Relation to oxidation kinetics
- Zirconium Alloys in Nuclear Applications
- Preliminary assessment of accident-tolerant fuels on LWR performance during normal operation and under DB and BDB accident conditions
Their papers
- High temperature steam oxidation of chromium-coated zirconium-based alloys: Kinetics and process (2020) — 339 citations
- AREVA NP's enhanced accident-tolerant fuel developments: Focus on Cr-coated M5 cladding (2018) — 245 citations
- Oxidation behavior of ferritic-martensitic and ODS steels in supercritical water (2012) — 188 citations