Post-Irradiation Non-Destructive Analyses of the AFIP-7 Experiment
Abstract
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.
- Authors:
-
- Idaho National Lab. (INL), Idaho Falls, ID (United States). Nuclear Fuels and Materials Division
- Publication Date:
- Research Org.:
- Idaho National Lab. (INL), Idaho Falls, ID (United States)
- Sponsoring Org.:
- USDOE National Nuclear Security Administration (NNSA), Office of Defense Nuclear Nonproliferation; USDOE Office of Nuclear Energy (NE)
- OSTI Identifier:
- 1473912
- Report Number(s):
- INL/JOU-17-41282-Rev000
Journal ID: ISSN 1047-4838
- Grant/Contract Number:
- AC07-05ID14517
- Resource Type:
- Accepted Manuscript
- Journal Name:
- JOM. Journal of the Minerals, Metals & Materials Society
- Additional Journal Information:
- Journal Volume: 69; Journal Issue: 12; Journal ID: ISSN 1047-4838
- Publisher:
- Springer
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 36 MATERIALS SCIENCE; U-mo; monolithic fuel; Research and Test Reactors; AFIP-7; Non- Destructive PIE
Citation Formats
Williams, W. J., Robinson, A. B., and Rabin, B. H. Post-Irradiation Non-Destructive Analyses of the AFIP-7 Experiment. United States: N. p., 2017.
Web. doi:10.1007/s11837-017-2552-y.
Williams, W. J., Robinson, A. B., & Rabin, B. H. Post-Irradiation Non-Destructive Analyses of the AFIP-7 Experiment. United States. https://doi.org/10.1007/s11837-017-2552-y
Williams, W. J., Robinson, A. B., and Rabin, B. H. Mon .
"Post-Irradiation Non-Destructive Analyses of the AFIP-7 Experiment". United States. https://doi.org/10.1007/s11837-017-2552-y. https://www.osti.gov/servlets/purl/1473912.
@article{osti_1473912,
title = {Post-Irradiation Non-Destructive Analyses of the AFIP-7 Experiment},
author = {Williams, W. J. and Robinson, A. B. and Rabin, B. H.},
abstractNote = {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.},
doi = {10.1007/s11837-017-2552-y},
journal = {JOM. Journal of the Minerals, Metals & Materials Society},
number = 12,
volume = 69,
place = {United States},
year = {Mon Aug 28 00:00:00 EDT 2017},
month = {Mon Aug 28 00:00:00 EDT 2017}
}
Web of Science
Works referenced in this record:
Fission product induced swelling of U–Mo alloy fuel
journal, December 2011
- Kim, Yeon Soo; Hofman, G. L.
- Journal of Nuclear Materials, Vol. 419, Issue 1-3
Works referencing / citing this record:
Advanced Postirradiation Characterization of Nuclear Fuels Using Pulsed Neutrons
journal, November 2019
- Vogel, Sven C.; Bourke, Mark A. M.; Craft, Aaron E.
- JOM, Vol. 72, Issue 1