Polymers
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2024
·Vol. 16
·期 2
·229
·
IF 4.7
Zhenyu Zhang,Guangyao Shen,Rongbo Li,Lei Yuan,Hongfu Feng,Xiuming Chen,Feng Qiu,Guangyin Yuan,Xiaodong Zhuang
Soft materials bearing rigid, lightweight, and vibration-dampening properties offer distinct advantages over traditional wooden and metal-based fillings for spent fuel transport casks, due to their low density, tunable structure, excellent mechanical properties, and ease of processing. In this study, a novel type of rigid polyurethane foam is prepared using a conventional polycondensation reaction between isocyanate and hydroxy groups. Moreover, the density and size of the pores in these foams are precisely controlled through simultaneous gas generation. The as-prepared polyurethane exhibits high thermal stability exceeding 185 °C. Lifetime predictions based on thermal testing indicate that these polyurethane foams could last up to over 60 years, which is double the lifetime of conventional materials of about 30 years. Due to their occlusive structure, the mechanical properties of these polymeric materials meet the design standards for spent fuel transport casks, with maximum compression and tensile stresses of 6.89 and 1.37 MPa, respectively, at a testing temperature of −40 °C. In addition, these polymers exhibit effective flame retardancy; combustion ceased within 2 s after removal of the ignition source. All in all, this study provides a simple strategy for preparing rigid polymeric foams, presenting them as promising prospects for application in spent fuel transport casks.Keywords:polyurethane foam;fillings;long service life;spent fuel;flame retardance
研究领域:
材料科学
·
核能工程
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产品关联
DOI
PubMed
高影响因子
INORGANIC CHEMISTRY
·
2018
·
IF 4.7
Fang-Li Fan,Zhi Qin,Shi-Wei Cao,Cun-Min Tan,Qing-Gang Huang,De-Sheng Chen,Jie-Ru Wang,Xiao-Jie Yin,Chao Xu,Xiao-Gui Feng
Here, we propose the use of carboxyl-functionalized ionic liquid, [Hbet][Tf2N], to separate the fission products from spent nuclear fuels. This innovative method allows the selective dissolution of neutron poisons, lanthanides oxide, as well as some fission products with high yield, leaving most of the UO2 matrix and minor actinides behind in the spent nuclear fuel and accomplishing the actinides recovery as a group. Water-saturated [Hbet][Tf2N] can dissolve lanthanides oxide from simulated spent nuclear fuel with a dissolution ratio of 100% at 40 °C. However, the dissolution of uranium is almost negligible (<1%) under the same conditions. This big difference in dissolution provides a novel separation approach to spent nuclear fuel recycling and may open new perspectives for spent nuclear fuel reprocessing. The recovery of Nd and U from metal-loaded ionic liquids and the recyclability of the ionic liquid [Hbet][Tf2N] have also been investigated. Furthermore, a U/x value related to the lattice energy U of metal compound MxOy is used to elaborate the solubility. This work represents the first case for efficient fission products removal by selective dissolution, avoiding the complete dissolution of spent nuclear fuel, the producing of the large high-level radioactive waste, and reducing environmental hazards.
研究领域:
核化学与核燃料循环
·
环境科学
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产品关联
DOI
PubMed
高影响因子
CHEMICAL ENGINEERING JOURNAL
·
2025
·
IF 13.2
Ming Shang,Bin Wang,Jian Liu,Lin Zhu,Baoliang Xu,Tao Duan,Jing Chen
Granulation technology enables effective industrial use of powder adsorbents by addressing pressure drop and operability challenges in engineering systems. In this study, a bismuth-embedded mesoporous silicon‑iodine adsorbent (Bi/Bi 2 S 3 @SiO 2 ) was synthesized using oil-ammonia column granulation technology, enabling. This method enabled the efficient and controllable granulation of the powder adsorbent and large-scale production. Considering the high temperature, high humidity, NO x , and dynamic gas flow characteristics of spent fuel reprocessing exhaust gases, we systematically evaluated the dynamic iodine adsorption performance of the granular adsorbent under simulated real conditions. Experimental results indicate that the static adsorption capacity for iodine vapor of Bi/Bi 2 S 3 @SiO 2 –2 is approximately 600 mg/g. The optimized granular adsorbent exhibits excellent mechanical strength and a uniform particle size distribution. Although its static adsorption capacity decreases by approximately 10 %, the dynamic adsorption capacity reaches 112 mg/g after breakthrough. The iodine removal efficiency exceeds 99.00 % during a continuous 30 h test. Further mechanistic analysis reveals that the adsorption of iodine vapor by Bi/Bi 2 S 3 @SiO 2 –2 primarily occurs through stable chemical adsorption (BiI 3 ). This study provides essential data to support the advancement of controlled granulation technology and the engineering application of radioactive iodine adsorbents, presenting a new strategy for the design of adsorbents in nuclear waste treatment systems.
研究领域:
核工程
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环境科学
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材料科学
·
化学工程
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产品关联
DOI
高影响因子
CHEMICAL ENGINEERING JOURNAL
·
2022
·
IF 16.744
Mei Jiang,Lin Zhu,Qian Zhao,Guangyuan Chen,Zeru Wang,Jingjing Zhang,Ling Zhang,Jiehong Lei,Tao Duan
Effective capture of radioactive iodine in spent fuel reprocessing is an urgent problem to be solved. In this study, we reported a novel fluoride modified bismuth sulfide supported NaY zeolite material (NaY-NH 4 F-Bi 2 S 3 ), prepared by hydrothermal method. The zeolite with a hydrophobic skeleton was obtained by etching with NH 4 F solution. The adsorption mechanism generally follows preferential iodine enrichment in NaY zeolite microporous channels and is subsequently immobilized by loaded bismuth sulfide sites on NaY zeolite. Under the combination of physical and chemosorption, the sorption capacity of NaY-NH 4 F-Bi 2 S 3 reaches 491 mg/g, which is much higher than that of bare NaY zeolite. The excellent thermal stability and radiation stability greatly enhance its iodine capture performance under harsh conditions. The comprehensive characteristics of high cost-effectiveness, low toxicity, good radiation resistance, and good thermal stability make it have potential applications in the capture, immobilization and storage of radioactive gaseous iodine during spent fuel reprocessing.
研究领域:
核科学与工程
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环境科学
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材料科学
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产品关联
DOI
高影响因子
APPLIED SURFACE SCIENCE
·
2023
·
IF 6.7
Xudong Gong,Qiang Tian,Jiebiao Li,Ju Wang,Minhao Yan,Mark J. Henderson
Incorporation of fission products in spent nuclear fuel is of interest in the frame of safe storage of high-level nuclear waste in a deep geological repository. Uranyl oxyhydroxide films were grown on silicon wafer to represent the corrosion product formed on the surfaces of the fuel. Films were obtained by hydrolysis of uranyl ions (9 mM) in mild conditions (≤60 °C) using either Mg(OH) 2 , raw brucite, La(OH) 3 , or NH 4 OH to control the solution pH to ≈ 5.0. To identify the mineral phases we used the grazing-incidence X-ray technique. Atomic force microscopy data indicated that the surfaces of metaschoepite films prepared using either Mg(OH) 2 or brucite at 50 °C for 3 h were self-affine fractal ( D f = 2.5). The concentration (wt.%) of reactant ions detected in a metaschoepite film after reaction at 70 °C for three days as determined by X-ray fluorescence was: La (8.90) > Nd (5.6) > Ce (3.2) > Eu (2.5) > Pb (0.7) > Sr (0.14). Metaschoepite and sodium uranate hydrate were identified in a film formed in Cl-SO 4 -Na type groundwater from the Beishan area (China), the preselected area of a radioactive waste disposal repository.
研究领域:
核废料管理
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材料科学
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环境科学
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产品关联
DOI
高影响因子
ELECTROCHIMICA ACTA
·
2020
·
IF 6.215
Da-Wei Yang,Ya-Lan Liu,Tai-Qi Yin,Shi-Lin Jiang,Yu-Ke Zhong,Lin Wang,Mei Li,Zhi-Fang Chai,Wei-Qun Shi
To study the application perspectives of binary Ga–Al alloy electrodes in pyroprocessing, the utilization of Ga–Al alloy electrode for the separation of U from Ce was studied in this work. Specifically, the reduction behaviors of U (III) on Ga, Al and Ga–Al alloy electrodes was first explored in LiCl–KCl eutectic at 773 K. The cathode peak potential of U (III) at the Ga–Al alloy electrode was 0.44 V (vs. Li/Li 3 Bi), and less affected by the Ga/Al ratio. Moreover, potentiostatic electrolysis at 0.55 V (vs. Li/Li 3 Bi) was conducted on the Ga–Al alloy electrode for 4 h to separate U from Ce. X-ray diffraction (XRD) analysis indicated the co-existence of Al 3 U and Ga 3 U with an identical crystal structure in the deposits. Scanning electron microscopy coupled with energy dispersive spectroscopy (SEM-EDS) illustrated a good diffusion of U metal in Ga–Al alloy electrodes. Inductive coupled plasma optical emission spectrometry (ICP-OES) determinations exhibited an excellent separation performance of the Ga–Al alloy electrode.
研究领域:
核工程
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材料科学
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电化学
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产品关联
DOI
高影响因子
JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY
·
2023
·Vol. 332
·期 4
·1353-1365
·
IF 1.6
Wang Zhaoyang,Shen Yubo,Zhang Yinshan,Liu Yuhui,Dong Zhimin,Quan Meiyang,Yu Fengtao,Cao Xiaohong,Zhang Zhibin,Wang Yingcai,Liu Yunhai
In order to improve the utilization of spent fuel, electrolysis is used to recover fissile elements from nuclear waste samarium. The electrochemical behaviors of Sm(III) and Pb(II) were examined by CV, SWV, and OCP techniques in LiCl–KCl molten salts at 773 K. The redox mechanism of Sm(III) ions on the liquid Pb thin film electrode was analyzed. The results demonstrate that Sm(III) electro-reduction at the inert W electrode only occurred in a soluble–soluble electrochemical transition Sm(III)/Sm(II). Additionally, the kinetic parameters of samarium and lead ions were computed. The activation energies of diffusion for Sm(III) and Pb(II) were 32.92 kJ mol −1 and 35.21 kJ mol −1 , respectively. SmPb 3 and Sm 2 Pb intermetallic compounds were derived using constant potential electrolysis and constant current electrolysis at the Pb electrode in a molten salt system. The cathodic deposition output was characterized by XRD and SEM–EDS. The ICP-AES results showed that the average extraction ratio of Sm on the Pb electrode was about 94.23%.
研究领域:
核化学
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电化学
·
材料科学
✓ 已验证
DOI
高影响因子
危险品化学品经营许可证（带存储）