Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

Carbon contamination, its consequences and its mitigation in ion-simulation of neutron-induced swelling of structural metals

Conference ·
Neutron-induced swelling in austenitic and ferritic steels is sensitive to the carbon level in the steel, as well as its distribution in matrix or precipitates. It has recently become known that ion-irradiation to high dpa levels leads to a progressive ion-beam-induced increase in carbon concentration and precipitation within the ion range, with concurrent reductions in void swelling. This neutron-atypical phenomenon imperils the credibility of ion simulation for light water reactor applications. A series of experiments involving pure iron and a structural alloy HT9, was conducted to identify the source and distribution of injected carbon. It was found that negatively-charged carbon atoms are entrained in the self-ion beam by a Coulomb drag effect, and thereby delivered at low drift energy to the irradiated surface, followed by ion-beam-mixing and diffusion. A technique for filtering out contaminants, especially carbon, oxygen and nitrogen, was developed and resulted in higher, more neutron-relevant swelling levels than achieved without filtering.
Research Organization:
Pacific Northwest National Laboratory (PNNL), Richland, WA (United States)
Sponsoring Organization:
USDOE
DOE Contract Number:
AC05-76RL01830
OSTI ID:
1570355
Report Number(s):
PNNL-SA-127786
Country of Publication:
Switzerland
Language:
English

Similar Records

Impact of composition modification induced by ion beam Coulomb-drag effects on the nanoindentation hardness of HT9
Journal Article · Thu Feb 14 19:00:00 EST 2019 · Nuclear Instruments and Methods in Physics Research. Section B, Beam Interactions with Materials and Atoms · OSTI ID:1499354

Comparison of fracture behavior for low-swelling ferritic and austenitic alloys irradiated in the Fast Flux Test Facility (FFTF) to 180 DPA
Technical Report · Fri Jan 31 23:00:00 EST 1992 · OSTI ID:5878662

Comparison of fracture behavior for low-swelling ferritic and austenitic alloys irradiated in the Fast Flux Test Facility (FFTF) to 180 DPA. Revision 1
Technical Report · Fri Jan 31 23:00:00 EST 1992 · OSTI ID:10124433

Related Subjects