Thermochemically-informed mass transport model for interdiffusion of U and Zr in irradiated U-Pu-Zr fuel with fission products
Max Poschmann (ORCID 0000-0002-4955-6259), Markus H.A. Piro, Theodore M. Besmann, Kevin T. Clarno (ORCID 0000-0002-5999-2978), Srdjan Simunovic
Journal of Nuclear Materials 554 153089 (2021) · Elsevier BV
DOI: 10.1016/j.jnucmat.2021.153089
Data: JSON record · id doi:10.1016/j.jnucmat.2021.153089 · metadata: crossref
Roles in ORCHID
- discovery lead (found by Crossref assessment discovery, not read): rank 1501, score 75; systems named in title: Pu–U–Zr
Systems
Availability
Read by ORCHID: no. Open-access licence (Crossref license field): none deposited. Crossref is-referenced-by count: 22 (retrieved 2026-10-23).
Relations
References (Crossref, publisher-deposited) (2)
- Contribution to the thermodynamic description of the corium – The U-Zr-O system (2018) [crossref_reference_list]
- Thermodynamic assessment of the Pu-U, Pu-Zr, and Pu-U-Zr systems (1999) [crossref_reference_list]