Dr. Sumit Bhattacharya is a Materials Scientist in the Chemical and Fuel Cycle (CFC) division at Argonne National Laboratory. He is part of the Advanced Fuels and Materials group under the department of Fuel Development and Qualification (FDQ) group at Argonne. His primary research focus has been in the field of surface science/surface modifications to understand and generate thin film coatings for diverse nuclear applications.
Dr. Bhattacharya has been helping develop various successful coatings specifically designed for nuclear fuel and its cladding to function as a barrier against metal and oxygen diffusion. To generate these single and tailored multilayer coatings for use as diffusion barriers against metals, he has used techniques such as atomic layer deposition (ALD), physical vapor deposition (PVD), and electrochemical deposition methods. Multilayer coatings have been primarily designed to survive extreme thermal cycling while remaining inside a nuclear environment. He has also applied the coating technique of corroding mediums within a high temperature nuclear environment.
Dr. Bhattacharya has been collaborating with researchers both from CFC as well as the Nuclear Science and Engineering division at Argonne to implement these coatings in projects involving both private and public partners. His research also focuses on developing techniques involving electrophoretic/electrochemical depositions, from which he has successfully developed methods to generate thicker ceramic/metal films and composite coatings.
Dr. Bhattacharya is a current participant in Argonne’s Launchpad Program, designed to provide motivated early- and mid-career researchers with enhanced training and mentoring for developing multimillion-dollar sponsored research programs. He has been inducted in the Launchpad group called “Material Innovations to Advance High-performance Nuclear Microreactors Development” for his expertise in the surface science field. As part of the Launchpad Program, his team is developing and promoting designs to enable next-generation nuclear microreactors through cutting-edge material innovations and to efficiently commercialize these solutions while accelerating proof-of-concept of these innovations to attract more industry interests. Dr. Bhattacharya’s primary role on the team will be to design and develop materials (e.g., coatings) tuned for very high temperature nuclear applications to protect the base materials, which can range from heat exchangers to moderators and heat pipes.
"Cross section TEM characterization of high-energy-Xe-irradiated U-Mo"
Sumit Bhattacharya,
Journal of Nuclear Materials
Vol. 488
2019
134-142
Link
U-Mo alloys irradiated with 84 MeV Xe ions to various doses were characterized with transmission electron microscopy (TEM) and scanning transmission electron microscopy (STEM) techniques. The TEM thin foils were prepared perpendicular to the irradiated surface to allow a direct observation of the entire region modified by ions. Therefore, depth-selective microstructural information was revealed. Varied irradiation-induced phenomena such as gas bubble formation, phase reversal, and recrystallization were observed at different ion penetration depths in U-Mo. |
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"In situ TEM Ion Irradiation Investigations on U3Si2 at LWR Temperatures"
Sumit Bhattacharya,
Journal of Nuclear Materials
Vol. 484
2016
168-173
Link
The radiation-induced amorphization of U3Si2 was investigated by in-situ transmission electron microscopy using 1 MeV Kr ion irradiation. Both arc-melted and sintered U3Si2 specimens were irradiated at room temperature to confirm the similarity in their responses to radiation. The sintered specimens were then irradiated at 350 °C and 550 °C up to 7.2 × 1015 ions/cm2 to examine their amorphization behavior under light water reactor (LWR) conditions. U3Si2 remains crystalline under irradiation at LWR temperatures. Oxidation of the material was observed at high irradiation doses. |
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"Nanocrystalline ZrN thin film development via atomic layer deposition for U-Mo powder"
Sumit Bhattacharya,
Journal of Nuclear Materials
Vol. 526
2019
Link
Zirconium nitride (ZrN) thin film deposited via thermal atomic layer deposition (ALD) has been recently chosen as a candidate technology for application of a diffusion barrier coating on the low enriched uranium alloy powder considered in the NNSA research reactor conversion program. Reported here is the f irst instance of using ALD for coating actinide materials. For this study, a modified ALD system was constructed to produce one micron thick zirconium nitride (ZrN) coating over spherical particulate of natural uranium-molybdenum (U-Mo) based fuel. The ALD system was designed to have a rotating drum system, with provisions for facilitating sequential exposures of chemicals such as tetrakis dimethyl amido zirconium (TDMAZr) and ammonia (NH3) in order to deposit ZrN. The ALD system was successful in developing a highly conformal ZrN coating covering every individual U-7Mo particle. This article describes the ZrN film synthesis details and reports the produced microstructure and composition of the ALD ZrN as deposited on fuel particulates. The as-fabricated coating was determined to have a nanocrystalline structure in the cubic-ZrN (cF8) phase. It exhibited a dense microstructure with adequate interfacial bonding. TEM-EELS characterization demonstrated that the coating contains a very low amount of oxygen impurity. To understand the potential microstructural evolution for ALD ZrN during reactor operation, an in-situ heavy ion (Kr) irradiation experiment was performed at the IVEM-Tandem facility. A total fluence of 7.5 1015 ions/cm2 (~10 dpa) was achieved, and apart from minor grain coarsening in the ALD ZrN coating, no significant radiation effects were observed. |
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"Nano-crystallization induced by high-energy heavy ion irradiation in UO2"
Sumit Bhattacharya,
Scripta Materialia
Vol. 155
2018
169-174
Link
Advanced microstructure investigations of the high-burnup structure (HBS) in UO2 produced by high-dose 84 MeV Xe ion irradiation are reported. Spark plasma sintered micro-grained UO2 was irradiated to 1357 dpa at 350 °C. The characteristic nano-grains and micro-pores of the HBS were formed. The grain size and grain boundary misorientation distributions of the HBS were measured using transmission electron microscopy based orientation imaging microscopy. Grain polygonization due to accumulation of radiation-induced dislocations was found to be the mechanism of nano-crystallization. The morphology of Xe bubbles was quantitatively investigated. This study provides crucial references for advanced fuel performance modeling of high-burnup UO2 |
The Nuclear Science User Facilities (NSUF) is the U.S. Department of Energy Office of Nuclear Energy's only designated nuclear energy user facility. Through peer-reviewed proposal processes, the NSUF provides researchers access to neutron, ion, and gamma irradiations, post-irradiation examination and beamline capabilities at Idaho National Laboratory and a diverse mix of university, national laboratory and industry partner institutions.
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