"Corrosion of Structural Alloys in High-Temperature Molten Fluoride Salts for Applications in Molten Salt Reactors" Guiqiu Zheng, Kumar Sridharan, JOM Vol. 70 2018 1535-1541 Link | ||
"Effect of exposure environment on surface decomposition of SiC–silver ion implantation diffusion couples"
Todd Allen, Kevin Field, Tyler Gerczak, Guiqiu Zheng,
Journal of Nuclear Materials
Vol. 456
2015
281-286
Link
SiC is a promising material for nuclear applications and is a critical component in the construction of tristructural isotropic (TRISO) fuel. A primary issue with TRISO fuel operation is the observed release of 110mAg from intact fuel particles. The release of Ag has prompted research efforts to directly measure the transport mechanism of Ag in bulk SiC. Recent experimental efforts have focused primarily on Ag ion implantation designs. The effect of the thermal exposure system on the ion implantation surface has been investigated. Results indicate the utilization of a mated sample geometry and the establishment of a static thermal exposure environment is critical to maintaining an intact surface for diffusion analysis. The nature of the implantation surface and its potential role in Ag diffusion analysis are discussed. |
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"Effect of exposure environment on surface decomposition of SiC–silver ion implantation diffusion couples" Tyler Gerczak, Guiqiu Zheng, Kevin Field, Todd Allen, Journal of Nuclear Materials Vol. 456 2015 281-286 Link | ||
"Experimental Measurement and Multiphysics Simulation of Tritium Transport in Neutron Irradiated Flibe Salt"
Kieran Dolan, Guiqiu Zheng, Michael Ames, David Carpenter, Lin-wen Hu,
Nuclear Technology
Vol. 209
2023
515-531
Link
Predicting the distribution and release of tritium remains a technical challenge for advanced nuclear reactors with molten Flibe (2LiF-BeF2) salt coolants. Tritium transport models, which are currently used to forecast release behavior, are limited by uncertainty in Flibe-related tritium transport properties and by a lack of relevant benchmark experiments to test input parameters and solution methods. A new test facility has been developed at the Massachusetts Institute of Technology Research Reactor (MITR) to irradiate a molten Flibe target in an ex-core neutron beam port to further investigate tritium transport mechanisms at prototypical reactor conditions. The experiment monitored the time-dependent release of tritium from the salt-free surface and the permeation rate of tritium through the stainless steel Flibe-containing test stand. Measured results were benchmarked with a multiphysics tritium transport simulation to resolve complex effects in the test. Trends in tritium release rates from the irradiation were in agreement with the multiphysics simulation of the test, which combined computational fluid dynamics, radiative heat transfer in participating media, and tritium transport in STAR-CCM+. |
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"Investigation of Nuclear Graphite and Cf/C Composite in High-Temperature Molten FLiBe Salt in the MIT Reactor" David Carpenter, Guiqiu Zheng, Lin-wen Hu, MIT technical report MIT-NRL-17-03 Vol. 2017 75 | ||
"Tritium Content and Chemical Form in Nuclear Graphite from Molten Fluoride Salt Irradiations"
Kieran Dolan, Guiqiu Zheng, David Carpenter, Steven Huang, Lin-wen Hu,
Fusion Science and Technology
Vol. 76
2020
398-403
Link
Advanced reactor applications that use a molten fluoride salt coolant and graphite moderator
are under consideration as next-generation energy technologies. For molten salts with lithium or beryllium, such as flibe (2LiF-BeF2), the production of tritium from neutron irradiation is a significant technical challenge. Understanding the expected quantities and mechanisms for tritium retention in graphite is important for designing tritium management strategies in these advanced reactors. In this work, the tritium content of IG-110U graphite from a 2013 in-core flibe irradiation experiment was measured by leaching in water and thermal desorption. Five total samples were tested, with an average measured tritium content per salt-contacting surface area of 3.83 ± 0.25 Ci/m2. The tritium measured from the thermal desorption experiments was primarily in a water-insoluble form. Compared to the overall tritium generation during the irradiation, the total amount of retention in graphite predicted by the desorption measurements is significant. |
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"Tritium generation, release, and retention from in-core fluoride salt irradiations"
Kieran Dolan, Guiqiu Zheng, Kaichao Sun, David Carpenter,
Progress in Nuclear Energy
Vol. 131
2021
Link
Further understanding of tritium transport mechanisms in the combined molten fluoride salt and graphite environment is necessary for the design and licensing of a Fluoride-Salt-Cooled High-Temperature Reactor (FHR). The three in-core fluoride salt irradiations completed at the Massachusetts Institute of Technology Reactor (MITR) are a useful parallel for studying transport phenomena expected in a FHR environment. During the irradiations, evolution of tritium from the flibe salt was monitored and compared to the calculated total generation rate. A difference of 22 ± 10% between the integrated calculated tritium generation rate and the total release was measured for the third MITR irradiation (FS-3). The fraction of tritium which was not released from the salt could be explained by tritium retention in graphite. For post irradiation examination, a thermal desorption furnace was used to heat nuclear graphite samples in order to release and measure retained tritium. The desorption analysis in this work utilized seven subsections of graphite from the second salt irradiation (FS-2); three from a disc of IG-110U and four from ARB matrix graphite. Observed desorption versus temperature as well as total tritium content in the samples after irradiation indicate that the graphites were not volumetrically saturated with tritium, but rather tritium retention was likely limited to the near-surface region. Measurements of the samples resulted in 2.90 ± 0.29 μCi/mm2 of tritium retained by IG-110U and 1.83 ± 0.31 μCi/mm2 for ARB during the 300 h FS-2 in-core irradiation. Based on the desorption measurements, the estimated total tritium retention in graphite from the FS-2 samples is consistent with the tritium release measurements from the FS-3 experiment. |
"Investigation of Nuclear Graphite and C/C Composite in Molten Li2BeF4 (FLiBe) under Neutron Irradiation" Guiqiu Zheng, David Carpenter, Kieran Dolan, Lin-wen Hu, 19th International Nuclear Graphite Specialists' Meeting September 2-6, (2018) Link | |
"Microstructure of In-Core Molten Salt Corrosion Hastelloy N® and 316 Stainless Steel" Michael Ames, David Carpenter, Gordon Kohse, Guiqiu Zheng, 2017 ANS Annual Meeting [unknown] |
RTE 1st Call Awards Announced - Projects total approximately $1.4 million These projects will continue to advance the understanding of irradiation effects in nuclear fuels and materials in support of the mission of the DOE-NE. Friday, February 8, 2019 - Calls and Awards |
RTE 2nd Call Awards Announced - Projects total approximately $1.6 million These project awards went to principal investigators from 26 U.S. universities, eight national laboratories, two British universities, and one Canadian laboratory. Tuesday, May 14, 2019 - Calls and Awards |
"Complex Structure of Molten FLiBe (2 LiF – BeF 2 ) Examined by Experimental Neutron Scattering, X-Ray Scattering, and Deep-Neural-Network Based Molecular Dynamics"
Rajni Chahal, Haley Williams, D. Nathanael Gardner, Guiqiu Zheng, David Sprouster, Jörg C. Neuefeind, Dan Olds, Andrea Hwang, Joanna Mcfarlane, Ryan C. Gallagher, Mark Asta, Stephen Lam, Raluca O. Scarlat, Boris Khaykovich, Sean Fayfar,
[2024]
PRX Energy
· DOI: 10.1103/prxenergy.3.013001
The use of molten salts as coolants, fuels, and tritium breeding blankets in the next generation of fission and fusion nuclear reactors benefits from furthering the characterization of the molecular structure of molten halide salts, paving the way to predictive capability of the chemical and thermophysical properties of molten salts. Due to its neutronic, chemical, and thermochemical properties, 2 |
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"High Spatial Resolution and Accurate Temperature Profile Measurements in a Nuclear Reactor Core Enabled by Machine Learning" Mohan Wang, Zekun Wu, Kehao Zhao, Sheng Huang, Mohamed A. S. Zaghloul, Rongtao Cao, David Carpenter, Guiqiu Zheng, Steven Derek Rountree, Zhi-Hong Mao, Kevin P. Chen, Jingyu Wu, [2024] IEEE Sensors Journal · DOI: 10.1109/jsen.2024.3408838 | |
"An electrochemical mesoscale tool for modeling the corrosion of structural alloys by molten salt" Guiqiu Zheng, Kumar Sridharan, Daniel Schwen, Michael R. Tonks, Chaitanya Vivek Bhave, [2023] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2022.154147 | |
"Towards in-Situ Corrosion Measurements in Molten Fluoride Salt By Simultaneous X-Ray Absorption Spectroscopy and Electrochemistry"
Sean Fayfar, Guiqiu Zheng, David J. Sprouster, Eli Stavitski, Boris Khaykovich,
[2022]
ECS Meeting Abstracts
· DOI: 10.1149/ma2022-0212763mtgabs
Effects of corrosion products on molten salt properties are a focus of many studies motivated by the needs of molten-salt nuclear reactors. We demonstrate in-situ measurements of corrosion products from NiCr (80%-20%) foil in molten FLiNaK. We used X-ray absorption spectroscopy (XAS) and a combination of XAS with electrochemical spectroscopy. Using XAS, we measured both the space and time distributions of Ni and Cr ions leaching from the foil and characterized their valence state and the local structure. We also correlated the XAS results with simultaneous electrochemical measurements. We also demonstrated a novel sample environment that we developed that enables simultaneous XAS and electrochemical measurements of molten fluoride salts. The next step of this program is to measure the corrosion on structural alloys such as stainless steel in molten FLiBe. |
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"Distributed Fiber Sensors With High Spatial Resolution in Extreme Radiation Environments in Nuclear Reactor Cores" Mohan Wang, Kehao Zhao, Sheng Huang, Mohamed Zaghloul, Rongtao Cao, David Carpenter, Guiqiu Zheng, Steven Rountree, K. P. Chen, Jingyu Wu, [2021] Journal of Lightwave Technology · DOI: 10.1109/jlt.2021.3075630 | |
"Femtosecond laser fabrication of nanograting-based distributed fiber sensors for extreme environmental applications"
Kehao Zhao, Jingyu Wu, Yuqi Li, Yang Yang, Sheng Huang, Jieru Zhao, Thomas Tweedle, David Carpenter, Guiqiu Zheng, Qingxu Yu, Kevin P Chen, Mohan Wang,
[2021]
International Journal of Extreme Manufacturing
· DOI: 10.1088/2631-7990/abe171
The femtosecond laser has emerged as a powerful tool for micro- and nanoscale device fabrication. Through nonlinear ionization processes, nanometer-sized material modifications can be inscribed in transparent materials for device fabrication. This paper describes femtosecond precision inscription of nanograting in silica fiber cores to form both distributed and point fiber sensors for sensing applications in extreme environmental conditions. Through the use of scanning electron microscope imaging and laser processing optimization, high-temperature stable, Type II femtosecond laser modifications were continuously inscribed, point by point, with only an insertion loss at 1 dB m−1 or 0.001 dB per point sensor device. High-temperature performance of fiber sensors was tested at 1000 °C, which showed a temperature fluctuation of ±5.5 °C over 5 days. The low laser-induced insertion loss in optical fibers enabled the fabrication of a 1.4 m, radiation-resilient distributed fiber sensor. The in-pile testing of the distributed fiber sensor further showed that fiber sensors can execute stable and distributed temperature measurements in extreme radiation environments. Overall, this paper demonstrates that femtosecond-laser-fabricated fiber sensors are suitable measurement devices for applications in extreme environments. |
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"Tritium Content and Chemical Form in Nuclear Graphite from Molten Fluoride Salt Irradiations" Guiqiu Zheng, David Carpenter, Steven Huang, Lin-Wen Hu, Kieran Dolan, [2020] Fusion Science and Technology · DOI: 10.1080/15361055.2020.1712993 | |
"Corrosion of commercial alloys in FLiNaK molten salt containing EuF |
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"Proton irradiation-decelerated intergranular corrosion of Ni-Cr alloys in molten salt"
Yang Yang, Guiqiu Zheng, Kevin B. Woller, Peter W. Stahle, Andrew M. Minor, Michael P. Short, Weiyue Zhou,
[2020]
Nature Communications
· DOI: 10.1038/s41467-020-17244-y
· EID: 2-s2.0-85087807008
The effects of ionizing radiation on materials often reduce to “bad news”. Radiation damage usually leads to detrimental effects such as embrittlement, accelerated creep, phase instability, and radiation-altered corrosion. Here we report that proton irradiation decelerates intergranular corrosion of Ni-Cr alloys in molten fluoride salt at 650 °C. We demonstrate this by showing that the depth of intergranular voids resulting from Cr leaching into the salt is reduced by proton irradiation alone. Interstitial defects generated from irradiation enhance diffusion, more rapidly replenishing corrosion-injected vacancies with alloy constituents, thus playing the crucial role in decelerating corrosion. Our results show that irradiation can have a positive impact on materials performance, challenging our view that radiation damage usually results in negative effects. |
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"Summary of Tritium Source Term Study in 10 MW High Temperature Gas-Cooled Test Reactor" W. Peng, F. Xie, J. Cao, Y. Dong, X. Duan, Y. Wen, B. Shan, K. Sun, G. Zheng, X. Liu, [2020] Fusion Science and Technology · DOI: 10.1080/15361055.2020.1718856 · EID: 2-s2.0-85082752744 | |
"Fusion Blankets and Fluoride-Salt-Cooled High-Temperature Reactors with Flibe Salt Coolant: Common Challenges, Tritium Control, and Opportunities for Synergistic Development Strategies Between Fission, Fusion, and Solar Salt Technologies" Guiqiu (Tony) Zheng, Ronald G. Ballinger, Stephen T. Lam, Charles Forsberg, [2019] Nuclear Technology · DOI: 10.1080/00295450.2019.1691400 · ISSN: 0029-5450 | |
"Experimental investigation of alumina coating as tritium permeation barrier for molten salt nuclear reactors" David Carpenter, Kieran Dolan, Lin-wen Hu, Guiqiu Zheng, [2019] Nuclear Engineering and Design · DOI: 10.1016/j.nucengdes.2019.110232 · ISSN: 0029-5493 | |
"A simultaneous corrosion/irradiation facility for testing molten salt-facing materials" Kevin B. Woller, Guiqiu (Tony) Zheng, Peter W. Stahle, Michael P. Short, Weiyue Zhou, [2019] Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms · DOI: 10.1016/j.nimb.2018.11.024 · ISSN: 0168-583X | |
"Corrosion of Structural Alloys in High-Temperature Molten Fluoride Salts for Applications in Molten Salt Reactors" Kumar Sridharan, Guiqiu Zheng, [2018] JOM · DOI: 10.1007/s11837-018-2981-2 · ISSN: 1047-4838 | |
"Investigation of materials corrosion in molten fluoride salts" [2018] Transactions of the American Nuclear Society · EID: 2-s2.0-85062960184 | |
"Tritium Production and Partitioning from the Irradiation of Lithium-Beryllium Fluoride Salt" Michael Ames, Guiqiu Zheng, Gordon Kohse, Lin-wen Hu, David Carpenter, [2017] Fusion Science and Technology · DOI: 10.1080/15361055.2017.1291040 · ISSN: 1536-1055 | |
"Microstructure of in-core molten salt corrosion hastelloy N® and 316 stainless steel" [2017] Transactions of the American Nuclear Society · EID: 2-s2.0-85033438121 | |
"Corrosion-induced microstructural developments in 316 stainless steel during exposure to molten Li2BeF4(FLiBe) salt" Lingfeng He, David Carpenter, Kumar Sridharan, Guiqiu Zheng, [2016] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2016.10.023 | |
"Corrosion-induced microstructural developments in 316 stainless steel during exposure to molten Li |
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"High Temperature Corrosion of Structural Alloys in Molten Li2BeF4(FLiBe) Salt" David Carpenter, Lin-Wen Hu, Kumar Sridharan, Guiqiu Zheng, [2016] Advances in Materials Science for Environmental and Energy Technologies V: Ceramic Transactions · DOI: 10.1002/9781119323624.ch9 | |
"High temperature corrosion of structural alloys in molten Li |
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"Materials corrosion and electrochemistry in molten FLiBe salt for FHR applications" [2016] International Congress on Advances in Nuclear Power Plants, ICAPP 2016 · EID: 2-s2.0-84986252319 | |
"High-Temperature Corrosion of UNS N10003 in Molten Li2BeF4(FLiBe) Salt"
Brian Kelleher, Lingfeng He, Guoping Cao, Mark Anderson, Todd Allen, Kumar Sridharan, Guiqiu Zheng,
[2015]
CORROSION
· DOI: 10.5006/1657
· ISSN: 0010-9312
Corrosion testing of UNS N10003 in molten fluoride salt was performed in purified molten 27LiF-BeF2 (66–34 mol%) (FLiBe) salt at 700°C for 1,000 h, in pure nickel and graphite capsules. In the nickel capsule tests, the near-surface region of the alloy exhibited an approximately 200 nm porous structure, an approximately 3.5 μm chromium-depleted region, and MoSi2 precipitates. In the tests performed in graphite capsules, the alloy samples gained weight because of the formation of a variety of Cr3C2, Cr7C3, Mo2C, and Cr23C6 carbide phases on the surface and in the subsurface regions of the alloy. A Cr-depleted region was observed in the near-surface region where Mo thermally diffused toward either the surface or the grain boundary, which induced an approximately 1.4 μm Ni3Fe alloy layer in this region. The carbide-containing layer extended to approximately 7 μm underneath the Ni3Fe layer. The presence of graphite dramatically changes the mechanisms of corrosion attack in UNS N10003 in molten FLiBe salt. In terms of the depth of attack, graphite clearly accelerates the corrosion, but the results appear to indicate that the formation of the Cr23C6 phase might stabilize the Cr and mitigate its dissolution in molten FLiBe salt. Moreover, a thermal diffusion controlled corrosion model that was fundamentally derived from Fick's second law was applied to predict the corrosion attack depth of 17.2 μm/y for UNS N10003 in molten FLiBe in the pure nickel capsule at 700°C. |
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"High-Temperature corrosion of UNS N10003 in Molten Li2BeF4 (FLiBe) Salt"
Brian Kelleher, Lingfeng He, Guoping Cao, Mark Anderson, Todd Allen, Kumar Sridharan, Guiqiu Zheng,
[2015]
Corrosion
· DOI: 10.5006/1657
· EID: 2-s2.0-84942913529
Corrosion testing of UNS N10003 in molten fluoride salt was performed in purified molten 27LiF-BeF2 (66–34 mol%) (FLiBe) salt at 700°C for 1,000 h, in pure nickel and graphite capsules. In the nickel capsule tests, the near-surface region of the alloy exhibited an approximately 200 nm porous structure, an approximately 3.5 μm chromium-depleted region, and MoSi2 precipitates. In the tests performed in graphite capsules, the alloy samples gained weight because of the formation of a variety of Cr3C2, Cr7C3, Mo2C, and Cr23C6 carbide phases on the surface and in the subsurface regions of the alloy. A Cr-depleted region was observed in the near-surface region where Mo thermally diffused toward either the surface or the grain boundary, which induced an approximately 1.4 μm Ni3Fe alloy layer in this region. The carbide-containing layer extended to approximately 7 μm underneath the Ni3Fe layer. The presence of graphite dramatically changes the mechanisms of corrosion attack in UNS N10003 in molten FLiBe salt. In terms of the depth of attack, graphite clearly accelerates the corrosion, but the results appear to indicate that the formation of the Cr23C6 phase might stabilize the Cr and mitigate its dissolution in molten FLiBe salt. Moreover, a thermal diffusion controlled corrosion model that was fundamentally derived from Fick's second law was applied to predict the corrosion attack depth of 17.2 μm/y for UNS N10003 in molten FLiBe in the pure nickel capsule at 700°C. |
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"Corrosion of 316 stainless steel in high temperature molten Li2BeF4 (FLiBe) salt" Brian Kelleher, Guoping Cao, Mark Anderson, Todd Allen, Kumar Sridharan, Guiqiu Zheng, [2015] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2015.03.004 · ISSN: 0022-3115 | |
"Corrosion of 316 stainless steel in high temperature molten Li |
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"Effect of exposure environment on surface decomposition of SiC–silver ion implantation diffusion couples" Guiqiu Zheng, Kevin G. Field, Todd R. Allen, Tyler J. Gerczak, [2015] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2014.09.063 · ISSN: 0022-3115 | |
"Effect of exposure environment on surface decomposition of SiC-silver ion implantation diffusion couples" Guiqiu Zheng, Kevin G. Field, Todd R. Allen, Tyler J. Gerczak, [2015] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2014.09.063 · EID: 2-s2.0-84908157331 | |
"Advanced heat exchanger development for molten salts" Denis Clark, Michael Glazoff, Guiqiu Zheng, Kumar Sridharan, Mark Anderson, Piyush Sabharwall, [2014] Nuclear Engineering and Design · DOI: 10.1016/j.nucengdes.2014.09.026 · ISSN: 0029-5493 | |
"Investigation of 2LiF-BeF |
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"Purification of non uranium bearing fluoride salts for nuclear applications" [2013] Transactions of the American Nuclear Society · EID: 2-s2.0-84902775842 | |
"Corrosion behavior of structural alloys in molten fluoride salts for next generation nuclear reactors" [2012] Transactions of the American Nuclear Society · EID: 2-s2.0-84876403409 | |
"Pore Structure Analysis of Nuclear Graphites IG-110 and NBG-18" P. Xu, K. Sridharan, T. R. Allen, G. Q. Zheng, [2011] Ceramic Transactions Series · DOI: 10.1002/9781118144527.ch24 · ISSN: 2637-4390 | |
"Versatile nanostructured processing strategy for bone grafting nanocomposites based on collagen fibrillogenesis" X. L. Wang, J. F. Ma, J. M. Jiang, G. Q. Zheng, Z. H. Chen, X. D. Li, X. M. Wang, [2009] Advances in Applied Ceramics · DOI: 10.1179/174367608x372907 · ISSN: 1743-6753 | |
"Structural characteristics of poly(vinyl alcohol)–calcium carbonate composites prepared by sequential method" X. D. Li, X. M. Wang, J. F. Ma, Z. W. Gu, G. Q. Zheng, [2008] Advances in Applied Ceramics · DOI: 10.1179/174367608x263313 · ISSN: 1743-6753 | |
"Structural characteristics of poly(vinyl alcohol)-calcium carbonate composites prepared by sequential method" X. D. Li, X. M. Wang, J. F. Ma, Z. W. Gu, G. Q. Zheng, [2008] Advances in Applied Ceramics · DOI: 10.1179/174367608x263313 · EID: 2-s2.0-39049157020 | |
"Fabrication and characterization of biodegradable artificial lacrimal canaliculus for treating lacrimal canalicular obstruction" [2008] Unpublished · DOI: 10.13140/2.1.1496.7686 | |
"Preparation and characterization of novel degradable artificial lacrimal canaliculus" [2008] Zhongguo xiu fu chong jian wai ke za zhi = Zhongguo xiufu chongjian waike zazhi = Chinese journal of reparative and reconstructive surgery · EID: 2-s2.0-66849091869 | |
"Synthesis of Hydroxyapatite in Polymeric Solutions for Organic-Inorganic Nanocomposites"
Xu Dong Li, Xiao Min Wang, Su Hong Yu, Zhong Wei Gu, Xing Dong Zhang, Gui Qiu Zheng,
[2007]
Key Engineering Materials
· DOI: 10.4028/www.scientific.net/kem.330-332.427
· ISSN: 1662-9795
Synthesis of hydroxyapatite (HA) in organic solutions has received extensive attention in recent years with an attempt to obtain HA of a nanometer level. In this preliminary study, we demonstrated that organic-HA nanocomposites could also be achieved with one step method via in situ mineralization and subsequent crosslinking of organic species. This design was realized through in situ synthesis of hydroxyapatite in poly(vinyl alcohol) and acrylic acid aqueous solution as an organic template. The aforementioned organic-inorganic nanocomposites were analyzed by using X-ray diffraction, Fourier-transform infrared spectroscopy, scanning electrical microscopy, thermal analysis. The comparative structural measurements were also conducted with the synthesized HA with absence of the organic template. The results indicated that the existence of organic species effectively inhibits the growth of calcium phosphate and that relatively pure HA can be obtained in sintered composite products. The present study provides a direct and versatile route for fabrication of nanocomposite biomaterials. |
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"In situ synthesis of PVA-PAA-HA interpenetrating composite hydrogel" Xu Dong Li, Gui Qiu Zheng, Jian Ming Jiang, Ji Yong Chen, Xing Dong Zhang, Xiao Min Wang, [2006] Key Engineering Materials · DOI: 10.4028/0-87849-992-x.1165 · EID: 2-s2.0-33645332866 | |
Source: ORCID/CrossRef using DOI |
This NSUF Profile is 55
Authored an NSUF-supported publication
Presented an NSUF-supported publication
Submitted an RTE Proposal to NSUF
Awarded 3+ RTE Proposals
Collaborated on an RTE Proposal
Reviewed an RTE Proposal
Microstructural characterizations of in-core molten salt irradiated TRISO particles - FY 2019 RTE 2nd Call, #19-1785
Thermal diffusivity and microstructure analysis of in-core molten salt irradiated graphite - FY 2019 RTE 1st Call, #19-1676
Microstructural characterization of grain boundaries in Hastelloy N corroded in molten FLiBe salt under neutron irradiation - FY 2018 RTE 3rd Call, #18-1545
Microstructural Characterization of Post-Irradiation Alloys for Integrated FHR Technology Development - FY 2016 RTE 2nd Call, #16-633
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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