Radiation stability of ZrN under 2.6MeV proton irradiation

Yang, Yong; Dickerson, Clayton; Allen, Todd R.

doi:10.1016/j.jnucmat.2009.03.040

Cited by 39 publications

(17 citation statements)

References 13 publications

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“…It has been demonstrated that ZrN has a high tolerance to, low-energy, heavy and light ion bombardment [5,6]. At the same time, a limited amount of data is available regarding the radiation resistance of ZrN to fission fragment bombardment.…”

Section: Introductionmentioning

confidence: 99%

Radiation tolerance of nanostructured ZrN coatings against swift heavy ion irradiation

Vuuren¹,

Skuratov²,

Углов³

et al. 2013

Journal of Nuclear Materials

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Section: Introductionmentioning

confidence: 99%

Radiation tolerance of nanostructured ZrN coatings against swift heavy ion irradiation

Vuuren¹,

Skuratov²,

Углов³

et al. 2013

Journal of Nuclear Materials

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“…It has been observed that bulk ZrN is highly resistant to radiation-induced amorphization up to 800°C using 2.6 MeV protons [45]. In addition, bulk ZrN has been demonstrated to be tolerant to low-energy, heavy and light ion bombardment [46,47]. Of particular interest for the current study is the response of a ZrN microstructure similar to what was observed for a ZrN coating deposited using a barrel deposition system.…”

Section: Radiation Stabilitymentioning

confidence: 81%

Microstructural characterization of a thin film ZrN diffusion barrier in an As-fabricated U–7Mo/Al matrix dispersion fuel plate

Keiser

Perez

Wiencek

et al. 2015

Journal of Nuclear Materials

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The United States High Performance Research Reactor Fuel Development program is developing low enriched uranium fuels for application in research and test reactors. One concept utilizes U-7 wt,% Mo (U-7Mo) fuel particles dispersed in Al matrix, where the fuel particles are coated with a 1 m-thick ZrN coating. The ZrN serves as a diffusion barrier to eliminate a deleterious reaction that can occur between U-7Mo and Al when a dispersion fuel is irradiated under aggressive reactor conditions. To investigate the final microstructure of a physically-vapor-deposited ZrN coating in a dispersion fuel plate after it was fabricated using a rolling process, characterization samples were taken from a fuel plate that was fabricated at 500°C using ZrN-coated U-7Mo particles, Al matrix and AA6061 cladding. Scanning electron and transmission electron microscopy analysis were performed. Data from these analyses will be used to support future microstructural examinations of irradiated fuel plates, in terms of understanding the effects of irradiation on the ZrN microstructure, and to determine the role of diffusion barrier microstructure in eliminating fuel/matrix interactions during irradiation. The as-fabricated coating was determined to be cubic-ZrN (cF8) phase. It exhibited a columnar microstructure comprised of nanometer-sized grains and a region of relatively high porosity, mainly near the Al matrix. Small impurity-containing phases were observed at the U-7Mo/ZrN interface, and no interaction zone was observed at the ZrN/Al interface. The bonding between the U-7Mo and ZrN appeared to be mechanical in nature. A relatively high level of oxygen was observed in the ZrN coating, extending from the Al matrix in the ZrN coating in decreasing concentration. The above microstructural characteristics are discussed in terms of what may be most optimal for a diffusion barrier in a dispersion fuel plate application.

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“…Key research includes studies on radiation damage phenomena including segregation under irradiation, radiation induced hardening in ceramics, clustering dynamics of irradiated oxide dispersion strengthened steels, nuclear fuel stability under irradiation, and surface analysis of relevant material systems [5][6][7][8][9][10][11][12][13][14][15]. Here, selected results from research conducted using the UW-IBL and CLIM are presented to demonstrate the facility's capabilities as well as selected research results.…”

Section: Resultsmentioning

confidence: 99%

University of Wisconsin Ion Beam Laboratory: A facility for irradiated materials and ion beam analysis

Field¹,

Wetteland²,

Cao³

et al. 2013

AIP Conference Proceedings

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Radiation stability of ZrN under 2.6MeV proton irradiation

Cited by 39 publications

References 13 publications

Radiation tolerance of nanostructured ZrN coatings against swift heavy ion irradiation

Radiation tolerance of nanostructured ZrN coatings against swift heavy ion irradiation

Microstructural characterization of a thin film ZrN diffusion barrier in an As-fabricated U–7Mo/Al matrix dispersion fuel plate

University of Wisconsin Ion Beam Laboratory: A facility for irradiated materials and ion beam analysis

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