Post-Irradiation Non-Destructive Analyses of the AFIP-7 Experiment

Journal Article · Mon Aug 28 00:00:00 EDT 2017 · JOM. Journal of the Minerals, Metals & Materials Society

DOI:https://doi.org/10.1007/s11837-017-2552-y· OSTI ID:1473912

Williams, W. J. ^[1]; Robinson, A. B. ^[1]; Rabin, B. H. ^[1]

---

1. Idaho National Lab. (INL), Idaho Falls, ID (United States). Nuclear Fuels and Materials Division

This paper reports the results and interpretation of post-irradiation non-destructive examinations performed on four curved full-size fuel plates that comprise the AFIP-7 experiment. These fuel plates, having a U-10 wt.%Mo monolithic design, were irradiated under moderate operating conditions in the Advanced Test Reactor to assess fuel performance for geometries that are prototypic of research reactor fuel assemblies. Non-destructive examinations include visual examination, neutron radiography, profilometry, and precision gamma scanning. This article evaluates the qualitative and quantitative data taken for each plate, compares corresponding data sets, and presents the results of swelling analyses. Finally, these characterization results demonstrate that the fuel meets established irradiation performance requirements for mechanical integrity, geometric stability, and stable and predictable behavior.

• Research Organization: Idaho National Lab. (INL), Idaho Falls, ID (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Office of Defense Nuclear Nonproliferation; USDOE Office of Nuclear Energy (NE)
• Grant/Contract Number: AC07-05ID14517
• OSTI ID: 1473912
• Report Number(s): INL/JOU-17-41282-Rev000
• Journal Information: JOM. Journal of the Minerals, Metals & Materials Society, Vol. 69, Issue 12; ISSN 1047-4838
• Publisher: Springer
• Country of Publication: United States
• Language: English

Related Subjects

36 MATERIALS SCIENCE
U-mo
monolithic fuel
Research and Test Reactors
AFIP-7
Non- Destructive PIE