最新刊期
      卷 43 ， 期 11 ， 2020

        ACCELERATOR, RAY TECHNOLOGY AND APPLICATIONS

      • “在核材料定量分析领域，专家利用LIBS技术对氧化铈进行研究，验证了等离子体满足局部热动力学平衡条件，为核材料分析提供新方法。”
        WANG Xiangli,GAO Zhixing,CHENG Yimei
        Vol. 43, Issue 11, (2020) DOI: 10.11889/j.0253-3219.2020.hjs.43.110201
        摘要：BackgroundThe analysis and determination of nuclear material is an important part in nuclear safeguards. Laser-induced breakdown spectroscopy (LIBS) is a very promising technology in material quantitative analysis.PurposeThis study aims to explore the feasibility of using LIBS technology to analyze nuclear materials of CeO2 as a substitute for PuO2.MethodsBy using single pulse laser-induced breakdown spectroscopy (SP-LIBS), the main properties of CeO2 plasma when samples were in solid form were investigated. Boltzmann curve fitting, Stark broadening analysis and electron density calculation were employed to study the basic properties of SP-LIBS plasma of CeO2 in solid state.ResultsThe results showed that under the condition of 20 mJ single pulse laster energy, the best delay time for quantitative analysis is 0.4 μs. Simultaneously, plasma temperatures of Ce II and Si II obtained by Boltzmann curve fitting of their spectral lines were (6 710±805) K and (12 898±1 522) K, respectively, when delay time was set at 0.4 μs, and the electron density calculation derived from multi-peaks fit of Stark broadening by Si element spectral lines is (2.88±0.57)×1018 cm-3.ConclusionUnder the established experimental condition, the plasma of CeO2 satisfies local thermodynamic equilibrium (LTE) condition, and these results of this study provide reference basis for the quantitative analysis of nuclear material by using LIBS technology.  
        关键词：CeO2;LIBS;Plasma temperature;Local themodynamic equilibrium   
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        发布时间：2024-10-25
      • “在全面禁止核试验条约放射性核素核查领域，专家改进了β-γ符合能谱解谱算法，显著降低了氙同位素误识别率，提高了活度计算准确性。”
        ZHANG Xinjun,WANG Shilian,JIA Huaimao,LI Qi,SHI Jianfang,FAN Yuanqing,ZHAO Yungang
        Vol. 43, Issue 11, (2020) DOI: 10.11889/j.0253-3219.2020.hjs.43.110202
        摘要：BackgroundThe β-γ coincidence technique is a key method to measure the radioactivity of radioxenon isotopes for comprehensive nuclear-test-ban treaty (CTBT) radionuclide verification. The β-γ coincidence spectrum is usually analyzed by the net count calculation method (NCC) which systematically subtracts gas background from sample spectra regardless of memory effect of the previous sample. Negative net gas background counts are very frequently observed in β-γ coincidence data from International Monitoring System (IMS) radionuclide stations. Gas background subtraction in such cases can potentially lead to overestimated of the activity concentration and even false positives.PurposeThis study aims to solve the problem of gas background subtraction in NCC.MethodsFirst of all, the judgment condition of gas background subtraction was proposed to avoid negative net gas background counts. Then the memory effect of the previous sample was eliminated by modifying the processing flow in NCC algorithm for analyzing β-γ coincidence spectrum. Finally, historical β-γ coincidence data from IMS radionuclide stations were taken for verification of modified NCC and comparison with original NCC.ResultsComparing the analysis results of original NCC and modified NCC, the false identification number of 131Xem, 133Xem, 133Xe and 135Xe is reduced by 63%, 68%, 72% and 26%, respectively.ConclusionsThe modified NCC algorithm can decrease the positive fault of identification of xenon isotopes and improve the accuracy of calculation of their radioactivity concentration.  
        关键词：Radioxenon isotopes;β-γ coincidence spectra;Net count calculation method;Memory effects   
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      • “在放射源检查领域，专家研究了屏蔽下多特征能量点状γ射线源的活度估算方法，为处理“孤儿源”提供解决方案。”
        XIONG Maolin,ZHANG Qingxian,ZHANG Jian,YANG Jin,GE Liangquan,SUN Kun
        Vol. 43, Issue 11, (2020) DOI: 10.11889/j.0253-3219.2020.hjs.43.110203
        摘要：BackgroundDuring the radioactive source inspection or the orphan source disposal, it is essential to estimate the activity of the radioactive source quickly and effectively. However, this may be difficult, especially when the source is under shield with unknown shield thickness.PurposeThis study aims to establish an activity estimation method of shielded multi-energy gamma-ray sources.MethodsFirst of all, based on the relationship between the material attenuation coefficient and energy of the gamma-ray source, a method for the activity estimation of shielded multi-energy gamma-ray source was established. Then, influences of the position bias between the radioactive source and the detector, the characteristic energy selection, and the effect of statistical fluctuations were investigated by experiments. Finally, the optimal characteristic energy of common multi-energy gamma-ray sources and the maximum measurable shield thickness of the radioactive sources with different activities were analyzed.ResultsThe experimental results show that the relative errors between the estimated thickness and the real thickness is less than 4%, and the relative errors between the estimated activity and the real activity is less than 5%.ConclusionsThe method proposed in the paper can be applied to the radioactive source inspection or the orphan source disposal.  
        关键词：Radiation detection;Activity estimation;Error analysis;Monte Carlo simulation   
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        发布时间：2024-10-25

        NUCLEAR CHEMISTRY, RADIOCHEMISTRY, RADIOPHARMACEUTICALS AND NUCLEAR MEDICINE

      • “在熔盐堆氟盐冷却剂净化领域，专家基于固体氧化物膜电解法，有效去除有害杂质，提高冷却剂服役周期和反应堆安全性。”
        ZUO Yong,SHEN Miao,XIE Leidong,XIE Hongwei,ZHAI Yuchun
        Vol. 43, Issue 11, (2020) DOI: 10.11889/j.0253-3219.2020.hjs.43.110301
        摘要：BackgroundAs a coolant for molten salt reactors (MSRs), fluoride salt should be kept clean during the whole service life. Impurities in the salt (such as O2- and Cr3+, Fe2+, Ni2+, et al.) could greatly prompt the corrosive behaviour. Otherwise, O2- may react with uranium ions (U4+) to form UO2 precipitation in the fuel salts, which may cause unpredictable security problem for the MSRs.PurposeThis study aims to propose an on-line purification concept of fluoride salts to improve the quality of the fluoride salts coolant for security assurance.MethodsBased on a solid oxide membrane (SOM) electrolysis method, the SOM anode was made from an 8-YSZ (8 mol% Y2O3-92 mol% ZrO2) tube containing metal deoxidizers while the graphite rod or container acted as the cathode. The effects of different metal deoxidizers and electrolysis conditions using SOM electrodes on the purification of FLiNaK salt under the temperature of 600 ℃ were investigated by experiments. When DC current was applied to the two electrodes, impurities in the fluoride salts (such as O2-, Cr3+, Fe2+, Ni2+, H2O) was collected or decomposed on either anode or cathode. The factors affecting the deoxidation and purification of SOM electrolysis were analyzed from the point of thermodynamics and kinetics.ResultsExperimental results show that O2- and transition metal ions (Cr3+, Fe2+, Ni2+) are decreased to below 100 μg·g-1 and 10 μg·g-1 respectively after 40 h-electrolysis with an SOM(Zn) anode and a graphite cathode in fluoride salts at 600 ℃. Impact factors on the deoxidization behavior of the SOM process were discussed from the perspective of thermodynamic and kinetics.ConclusionsIt is indicated that the SOM electrolysis method has a good application in the on-line purification of fluoride salts coolant of the MSRs.  
        关键词：Molten salt reactor;Fluoride salt;On-line purification;Solid oxide membrane;Yttria stabilized zirconia   
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        发布时间：2024-10-25
      • “在乏燃料镧锕分离领域，固相萃取法具有成本低、操作简便等优势。研究人员以SiO2和树脂为基体，合成含N固相吸附材料，综述了其制备方法、吸附条件及分离效果，为乏燃料处理提供新思路。”
        ZU Jianhua,FU Lingxiao,PAN Xiaohan,WANG Huan
        Vol. 43, Issue 11, (2020) DOI: 10.11889/j.0253-3219.2020.hjs.43.110302
        摘要：This paper aims to review on the synthesis and Lanthanides/Actinides separation performance of N-containing solid-phase adsorption materials in treatment of high-level waste liquids. The main technology of separating lanthanides and actinides in the spent fuel processing are solvent extraction and solid phase extraction. Compared with solvent extraction, solid phase extraction has some unique advantages such as no possibility of third phase formation, more compact equipment, less organic solvent utilization and less secondary waste generation. N-containing solid phase adsorption materials, synthesized by physical impregnation or chemical modification with SiO2 and resin as solid carriers, respectively, were taken as research object. In physical impregnation method, N-containing extractant was loaded into the micropores of SiO2 or resin, and the content of extractant was as high as 30%~40% after filling whilst the chemical modification method was to graft the ligand functional groups onto the matrix through chemical reaction to obtain solid-phase adsorption materials. The preparation methods and the adsorption conditions of these N-containing solid phase adsorption materials are reviewed in this paper, as well as the adsorption mechanisms and the separation efficiency of lanthanides and actinides. Compared with the separation of lanthanide and actinide by liquid-liquid extraction, N-containing solid-phase adsorption material with resin and SiO2 as carrier has the advantages of low cost, almost no organic waste liquid and suitable for dilute solution.  
        关键词：Separation of lanthanides and actinides;Solid phase extraction;N-containing solid phase adsorption material;SiO2;Resin   
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        发布时间：2024-10-25

        NUCLEAR ELECTRONICS AND INSTRUMENTATION

      • “在高能物理实验电子学领域，专家提出了一种利用SiTCP协议远程更新FPGA固件的新方法，无需额外芯片，内建安全机制，适合网络远程操作，可同时更新多块FPGA固件。”
        CHEN Zhang,WANG Zheng,HU Jun
        Vol. 43, Issue 11, (2020) DOI: 10.11889/j.0253-3219.2020.hjs.43.110401
        摘要：BackgroundField programmable gate array (FPGA) is widely used in many places, including readout system of large-scale high-energy physics experiments. This kind of experiments usually has large electronic systems with thousands of channels implemented together with FPGAs. Furthermore, these detectors and electronics are often located in special environments such as radiation field, under water or underground, hence the traditional single FPGA update method with joint test action group (JTAG) cable becomes unsuitable or inapplicable.PurposeThis study aims to realize FPGA remote firmware update without additional Ethernet chips or network protocol, and ensure the security mechanism of the process and multi-FPGA updating extendibility in the future.MethodsA new approach using silicon transmission control protocol (SiTCP) technique was proposed. The update firmware in the UDP packages was sent under the SiTCP protocol by MATLAB in host computer to FPGA, and the process of Flash memory programming to update firmware was dominated by FPGA, placing the role of PHY and MAC chips. The secure rollback function was implemented in the modified structure of FPGA firmware with separate update data area and original data area.ResultsUDP broadcasting has the ability to multi-FPGA updating, remote firmware update is achieved and tested the secure rollback mechanism well.ConclusionsThis method is suitable for remote operation with advantages such as no need for additional Ethernet chips, built-in safety function to fall back to a known situation, and extendibility of multi-FPGA updating.  
        关键词：FPGA;Remote update;SiTCP;Roll back   
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      • “在模数转换器领域，专家分析了电源噪声对ADC性能的影响，设计了低噪声ADC测试电路，验证了电源噪声与ADC输入信号的互调效应，为提高ADC性能提供解决方案。”
        WANG Li,WU Jie
        Vol. 43, Issue 11, (2020) DOI: 10.11889/j.0253-3219.2020.hjs.43.110402
        摘要：BackgroundPower supply quality is an important factor affecting the performance of an analog-to-digital converter (ADC).PurposeThis study aims to explore the influence of power supply noise on the performance of ADC.MethodsFirstly, the theoretical influence of power supply noise on the performance of ADC was analyzed. Then, a 32 bit low-noise ADC test circuit was designed for power supply analysis. Finally, a sine wave of known frequency and amplitude was taken as noise and overlaid on the ADC power supply to verify the influence of power supply noise on ADC performance.ResultsThe test results show that the power supply noise and the input signal of the ADC are mutually modulated to produce intermodulation noise, of which the second-order intermodulation noise is the main component. The low-frequency power supply noise of the ADC power supply is more easily to enter the signal frequency range while the ripple and noise of switching power supplies have limited impact on the performance of the ADC with high power supply rejection ratios. In addition, ADCs with digital filters can further reduce the influence of power supply noise on ADC performance.ConclusionsIn the pursuit of power supply efficiency, it is recommended to use to power the ADC instead of using the low-dropout linear regulator (LDO) power supply, the switch mode power supply can be used to pursue power supply efficiency for ADC.  
        关键词：ADC;Power noise;Modulation   
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        发布时间：2024-10-25
      • “在先进核能系统中，采用Cu/Cu2O参比电极的LBE氧传感器可有效测量225~500°C温区下的氧浓度，为抑制结构材料腐蚀提供解决方案。”
        ZHU Huiping,ZHANG Yu,ZHAO Yungan,LIU Xudong,CHANG Baochen,LI Xiaobo,NIU Fenglei,MA Yan,ZHAO Ping
        Vol. 43, Issue 11, (2020) DOI: 10.11889/j.0253-3219.2020.hjs.43.110403
        摘要：BackgroundIn the future advanced nuclear energy system cooled by liquid lead-bismuth alloy (LBE), the corrosion of structural materials can be effectively restrained by controlling the concentration of dissolved oxygen in LBE. Sensor for measuring oxygen concentration is very important for on-line monitoring and control of oxygen in LBE.However the existing Bi/Bi2O3 and Pt/air oxygen sensors are limited by the reference electrode, or the measurement temperature range is limited, or the structure stability is poor, so it is necessary to select new reference electrode to solve these problems.PurposeThis study aims to improve the performance of the existing oxygen sensors and test the performance of a new oxygen sensor using Cu/Cu2O as the reference electrode.MethodsStep cooling experiments were carried out in LBE for both the oxygen sensor test and device calibration. The applicable temperature range, measurement stability and response characteristics of Cu/Cu2O were evaluated. The electromotive force (EMF) signals were calibrated according to the theoretical data whilst the accuracy of this new oxygen sensor with different mass ratio of reference electrode were tested through the calibration experiment.Results & ConclusionsExperimental results show that the oxygen sensor with Cu/Cu2O reference electrode is applicable for LBE to measure oxygen concentration in the temperature range of 225 °C to 500 °C. The EMF signal of this sensor is stable and repeatable while the response speed is slightly slow. There is no obvious difference in the calibration signal among oxygen sensors with different reference mass ratios, and the error of the measured signals of all sensors after calibration is less than 3.2%.  
        关键词：Lead-bismuth eutectic alloy;Oxygen concentration;Oxygen sensor;Reference electrode   
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        发布时间：2024-10-25

        NUCLEAR PHYSICS, INTERDISCIPLINARY RESEARCH

      • “在光中子反应领域，专家设计了一种4π平坦效率3He中子探测器阵列，模拟显示其在1 keV~6 MeV能区的平均效率为40%~46%，为区分单中子、双中子和三中子事件提供解决方案。”
        HAO Zirui,FAN Gongtao,LIU Longxiang,WANG Hongwei,ZHANG Yue,HU Xinrong,LI Xinxiang,WANG Junwen,KUANG Pan,GE Songyu
        Vol. 43, Issue 11, (2020) DOI: 10.11889/j.0253-3219.2020.hjs.43.110501
        摘要：BackgroundThe flattening efficiency is very important to distinguish single neutron, double neutron and three neutron events and to calculate the cross section of photoneutron reaction, but few research has been made in China about this kind of detector.PurposeThis study aims to design a 4π flat-efficiency 3He neutron detector array used in the measurement of photonuclear cross section at Shanghai laser electron gamma source (SLESG) by simulation, and obtain its flat efficiency.MethodsA 4π flat-efficiency 3He neutron detector array was designed using 20 3He proportional counters of ⌀50 mm×500 mm and 6 3He proportional counters of ⌀25 mm×500 mm. These counters were optimized by using Geant4 code to obtain its detection efficiency. 209Bi target of ⌀20 mm×4 mm was taken for photoneutron reaction simulation study to calculate the angular distribution and energy spectra of neutrons.ResultsSimulation results of the 4π flat-efficiency 3He neutron detector array show the flat efficiency is 34.4%~45.9% in the neutron energy range of 1 keV~6 MeV. Simulation study of photoneutron reaction of 209Bi target indicates that the neutron emitted angle is symmetric at 90°, hence the 4π distribution of detectors can capture incident neutrons completely. A regular changing relationship between emitting neutron energy and neutron separation energy show that with the increase of gamma energy, more outgoing channels are open, the emitting neutron energy lays between 1 keV~4 MeV invariably, and the average efficiency of detector array in this energy region is about 40%~46%.ConclusionsThe 4π flat-efficiency 3He neutron detector designed for SLEGS is highly efficient and energy-independent, which is suitable for research in photoneutron measurement.  
        关键词：4π flat-efficiency 3He neutron detector array;Detector efficiency;Monte Carlo   
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        发布时间：2024-10-25

        NUCLEAR ENERGY SCIENCE AND ENGINEERING

      • “在核能领域，研究人员基于2500MWth氯盐快堆，研究了Th-U循环和U-Pu循环的中子学特性，发现TRU+Th循环具有较优的自持增殖性能和较高的嬗变性能。”
        LI Xiaoxiao,YU Chenggang,MA Yuwen,CAI Xiangzhou,CHEN Jingen,CHEN Xingwei
        Vol. 43, Issue 11, (2020) DOI: 10.11889/j.0253-3219.2020.hjs.43.110601
        摘要：BackgroundThe molten chloride salt fast reactor (MCFR) has advantages of high solubility of nuclear fuel and fast neutron spectrum, which makes it possible to achieve high breeding and transmutation efficiency.PurposeThis study aims to investigate the neutronics characteristics of Th-U fuel cycle and U-Pu fuel cycle in a 2 500 MWth MCFR, including the critical characteristic, burnup evolution, and breeding and transmutation performance.MethodsThe 233U and 239Pu were used as ignition fuels of Th-U fuel cycle (U3+Th) and U-Pu fuel cycle (Pu9+DU) respectively, and their fertile materials were 232Th and depleted uranium (DU), correspondingly. The analysis of the transition modes TRU+Th and TRU+DU with TRU as ignition fuel are also introduced.ResultsConsidering the neutron absorption rate of actinides, neutrons produced per fission (ν) and the conversion ratio (CR), nuclear fuel cycle mode of U3+Th needs a variable feed of fissile fuel to maintain the critical operation of the core, whereas Pu9+DU, TRU+DU and TRU+Th can be operated for a long time without on-line refueling, that is 46 a, 50 a and 29 a, respectively.ConclusionsTRU+Th fuel cycle mode is promising to MCFR due to its high self-sustaining breeding and high effective transmutation.  
        关键词：MCFR;Th-U fuel cycle;U-Pu fuel cycle;Breeding;Transmutation   
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      • “在聚变堆偏滤器水冷却回路材料研究领域，专家构建了CuCrZr合金腐蚀模型，为放射性源项计算提供科学依据。模型计算值与实验值相对误差最大12.1%。”
        ZHU Huiping,LIU Xudong,CHEN Jiawei,YANG Pengwei,HUANG Bokun,MA Yan
        Vol. 43, Issue 11, (2020) DOI: 10.11889/j.0253-3219.2020.hjs.43.110602
        摘要：BackgroundCuCrZr alloy is an important structural material for divertor water cooling circuit of fusion reactor. It is the primary contributor to the activated corrosion products of the fusion reactor. Therefore, it is urgent to develop the corrosion model of CuCrZr alloy in the calculation program of radioactive source term of fusion reactor.PurposeThe study aims to clarify the corrosion mechanism and develop the corrosion model in the calculation program of the CuCrZr alloy radioactive source term in fusion reactor.MethodsFirst of all, the corrosion experiments for CuCrZr alloy samples were carried out in the same dynamic and continuous water environment as the International Thermonuclear Experimental Reactor (ITER). Then the corrosion weight loss analysis and microscopic analysis were carried out to find the corrosion mechanism. Finally, the corrosion model of CuCrZr alloy was established and verified by experimental data.ResultsCorrosion experimental results indicate that the corrosion of CuCrZr alloy was caused by the combined action of fluid erosion and water oxidation corrosion. The maximum relative error between the calculated value and the experimental value of the established CuCrZr alloy corrosion model is 12.1%.ConclusionsThe model built in this study can be used as an empirical formula to predict the corrosion behavior of CuCrZr alloy in fusion reactor conditions.  
        关键词：CuCrZr alloy;ITER condition;Oxygen concentration;Corrosion model   
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      • “在聚变堆离子回旋加热领域，中国聚变工程试验堆天线的辐照损伤和屏蔽性能评估取得进展，为天线冷却系统设计和寿命评估提供数据，同时评估了屏蔽是否满足需求。”
        WU Qiuran,LU Peng,ZHENG Yu,DU Hua,XU Kun,WANG Yongsheng,TONG Yunhua,CHEN Gen,LIU Songlin
        Vol. 43, Issue 11, (2020) DOI: 10.11889/j.0253-3219.2020.hjs.43.110603
        摘要：BackgroundIon cyclotron range frequency (ICRF) antenna is one of the effective auxiliary heating systems to maintain the long pulse and high power steady-state operation of fusion reactors. The ICRF antenna has been designed to be introduced into China Fusion Engineering Test Reactor (CFETR) through one upper port, and the front-end will occupy one blanket. Since the antenna faces the plasma directly, it will be irradiated by high flux neutrons. It is necessary to evaluate the irradiation damage of the antenna. Besides, due to a lot of gaps in the antenna system, the neutron leakage will produce irradiation effects on the vacuum vessel (VV) and toroidal field coil (TFC) behind. Thus the shielding performance needs to be evaluated to support the shielding design.PurposeThis study aims to evaluate nuclear responses of the exposed components of ICRF antenna by neutronic simulation, and provide data for designing the cooling system and estimating its life after irradiation.MethodsBased on CFETR model of 22.5° fan section water cooled cladding, the neutronic model was converted from CAD file into MCNP input file by cosVMPT software. Nuclear analysis of ion cyclotron heating antenna was performed by using MCNP5 particle transport program and fendl-2.1 database, as well as the variance reduction method of Global Variance Reduction (GVR) "on the fly". The radiation damage and nuclear response of the main components of the antenna, including neutron flux, displacement per atom (DPA), gas production rate and nuclear thermal density, were calculated to provide data for the design and life assessment of the antenna cooling system.Results & ConclusionsThe neutron radiation damage of the vacuum chamber, window and longitudinal field coil at the corresponding position of lead-in antenna is obtained to evaluate whether the shielding meets the requirements of material. In addition, the Tritium Breeding Ratio (TBR) of the whole reactor is decreased from original 1.151 to 1.147 due to the blanket opening, which corresponds to a reduction of 0.35%.  
        关键词：CFETR;ICRF antenna;Neutronic calculations   
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        发布时间：2024-10-25
      • “在核燃料闭式循环领域，专家通过烧结实验，发现烧结气氛中水含量对MOX燃料芯块性能有重要影响，为快堆MOX燃料芯块制造提供解决方案。”
        ZHU Tongyu,YANG Tinggui,WANG Junping,TU Zhenhua,ZHANG Wande
        Vol. 43, Issue 11, (2020) DOI: 10.11889/j.0253-3219.2020.hjs.43.110604
        摘要：BackgroundThe mixed oxide fuel of uranium and plutonium (MOX fuel) is mainly used in fast reactor (FBR) and pressurized water reactor (PWR), and a small amount of MOX fuel is used in boiling water reactor (BWR). The MOX fuel manufacturing is the key link of "nuclear fuel closed cycle" whilst the key process of MOX fuel manufacturing is to sinter the fully mixed uranium plutonium oxide powder into the sintering pellets which meet the performance requirements. Sintering temperature, insulation time and sintering atmosphere are the key factors that affect the densification, the oxygen metal ratio and the microstructure of sintering pellet, etc.PurposeThis study aims to investigate the influence of sintering atmosphere on the properties of pellets.MethodsPuO2 powder was pretreated and mixed with UO2 powder in a certain proportion. The mixed powder was ground and granulated to form green body by two-way pressing. The same batch of green samples obtained by the same treatment process were fired in a high-temperature sintering furnace at 1 700 ℃ for 6 h, and then slowly reduced to room temperature. The microstructure of MOX fuel pellet was observed and analyzed by metallurgical microscope. The effect of the different water content on the properties of pellets in hydrogen argon mixture sintering atmosphere was studied experimentally.ResultsExperimental results show that the compactness and the O/M ratio of MOX sintered pellets increases with the increasing of water content in sintering atmosphere when the sintering temperature and holding time remain unchanged. When the water content in sintering atmosphere is more than 1 600 ppm, the obtained stoichiometric MOX sintered pellets have uniform microstructure without microcracks.ConclusionsThe sintering process conforms to the theory of vacancy diffusion mechanism.  
        关键词：MOX fuel;Fuel pellet;Sintering atmosphere;Pellet properties   
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