最新刊期
      卷 45 ， 期 3 ， 2022

        INVITED REVIEW

      • “日本福岛核事故后，Cr涂层包壳技术成为耐事故燃料研发主要方向。法国和美国在Cr涂层研发方面取得实质性突破，为我国研究提供参考。”
        DUAN Zhengang,CHEN Ping,ZHOU Yi,GAO Shixin,JIAO Yongjun,YIN Chunyun,HE Liang
        Vol. 45, Issue 3, Article number: 030001(2022) DOI: 10.11889/j.0253-3219.2022.hjs.45.030001
        摘要：Surface coating technology of nuclear fuel cladding has been one of the main research fields of accident tolerant fuel (ATF) since the Fukushima nuclear accident in Japan in 2011. A great deal of studies about the coating on nuclear fuel cladding have been carried out both at home and aboard. After nearly ten years of continuous technical exploration, Cr-coating cladding has stood out from the rest and has been the main technical roadmap of coated cladding development. At present, the development of Cr-coated cladding in the world has nearly completed the research on the preparation process, performance evaluation and design criterion, and has entered a critical phase from the technical research to engineering application. A large number of in-pile and out-of-pile tests for research and development (R&D) of Cr coated cladding have been carried out in France and United States, and substantive breakthroughs have been made in engineering application. The latest research contents, methods, achievements and future plans of Cr coating in France and the United States are systematically reviewed in this study. It is expected to provide valuable references for domestic R&D of Cr-coated cladding.  
        关键词：Cr coating;Fuel cladding;Accident tolerant fuel (ATF);Nuclear fuel   
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        发布时间：2024-10-25

        SYNCHROTRON RADIATION TECHNOLOGY AND APPLICATIONS

      • “在腐蚀性气体参与的气固反应研究中，科研人员研发了两种原位XRD表征装置，解决了特定气固反应原位XRD表征的需求，推动了同步辐射技术在化学反应原位表征中的应用。”
        ZHOU Jingtian,TAO Yajun,LUO Zhenlin
        Vol. 45, Issue 3, Article number: 030101(2022) DOI: 10.11889/j.0253-3219.2022.hjs.45.030101
        摘要：BackgroundCharacterizing the microstructure evolution of materials during the gas-solid reaction is crucial for the comprehensive understanding of the reaction mechanism. In situ synchrotron X-ray diffraction (XRD) is a powerful tool for this purpose. For the reactions involving corrosive gases, unique devices need to be designed for the in situ experiments.PurposeThe study aims to develop two kinds of in situ synchrotron XRD devices for characterizing gas-solid reaction.MethodsLiquid volatilization and solid heat treatment were applied respectively to the generation of reaction gas for two kinds of in situ synchrotron XRD devices. The gas-solid reaction in liquid volatilization was triggered and precisely controlled by injecting liquid into the cell, suitable for gas-solid reaction at room temperature and near atmospheric pressure. For in situ XRD characterization device with reaction gas generated by heat treatment of solid, both the cell and the X-ray window were made of quartz glass, hence suitable for the gas-solid reaction temperature up to 450 ℃ and X-ray photon energy above 18 keV.Results & ConclusionsThe two in situ devices have the advantages of compact, disassemble and reusable. These devices help to facilitate the application of synchrotron experimental techniques for in situ characterization of chemical reaction processes.  
        关键词：Synchrotron radiation;X-ray diffraction;In situ device;Gas-solid reaction   
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        发布时间：2024-10-25

        ACCELERATOR, RAY TECHNOLOGY AND APPLICATIONS

      • “在月球演化研究领域，专家通过中子活化分析，确保了嫦娥五号月壤样品元素含量测定的准确性和可靠性，为月球演化研究提供了重要数据支撑。”
        JIN Xiangchun,XIAO Caijin,YAO Yonggang,ZHANG Junxin,WU Peng,WANG Pingsheng,NI Bangfa
        Vol. 45, Issue 3, Article number: 030201(2022) DOI: 10.11889/j.0253-3219.2022.hjs.45.030201
        摘要：BackgroundDetermination of the elements in lunar soil samples returned by Chang'E 5- mission is of great significance for exploring the origin of lunar soil and the physical and chemical conditions for its formation, and for studying the evolutionary history of the moon. Neutron activation analysis (NAA) has the inherent advantages of non-destructiveness, high sensitivity, and the ability to analyze multiple elements. The NAA Laboratory of China Institute of Atomic Energy (CIAE) is responsible for the quantitative analysis of elements in the lunar soil samples returned by Chang'E-5 mission.PurposeThis study aims at the quality assurance and the control of NAA for the determination of element content of lunar soil samples to ensure the accuracy and reliability of the analysis results.MethodsBased on the principle of neutron activation analysis and sources of error, the quality assurance measures taken by NAA laboratory in sample preparation, selection of analysis protocols, γ-ray spectrometer performance control, measurement, spectrum analysis, calibration were discussed. The results of NAA were evaluated and verified by internal quality control samples with known property values (and uncertainties) and the consistent in different characteristics γ rays of the same radionuclide. The analysis results of each element to be measured were compared with relative method and single comparator k0 method to achieve the purpose of internal quality control.ResultsThe analysis results of internal quality control samples meet the laboratory's acceptance criteria. Internal quality control methods such as repeated tests, etc., verify the consistency of the element measurement results.ConclusionsBy analyzing the measurement data, the reliability of the test results is verified, and the quality assurance process and quality control method are proved to be effective.  
        关键词：Lunar soil samples;Neutron activation analysis;Quality assurance;Quality control   
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        发布时间：2024-10-25
      • “在硼中子俘获治疗领域，专家利用Geant4软件优化设计加速器装置，成功获得超热中子占比高达95.6%的中子源终端，为技术验证提供基础。”
        LU Yu,LI Wenyi,XU Zhao,LI Taosheng
        Vol. 45, Issue 3, Article number: 030202(2022) DOI: 10.11889/j.0253-3219.2022.hjs.45.030202
        摘要：BackgroundWith the development of accelerator technology, the accelerator-based Boron Neutron Capture Therapy (BNCT) has attracted more and more attention, and metallic 9Be is one of the most suitable materials for neutron-producing targets.PurposeThe study aims to investigate the possibility of obtaining BNCT neutron sources based on proton cyclotron with energy of 14 MeV and current intensity of 80 μA.MethodsGeant4 was used to simulate the neutron beam properties of Be target bombarded by 14 MeV proton beams and to optimize the target thickness. In addition, spherical natural uranium was considered as a neutron multiplier, the neutron beams generated by the combination of different materials and thicknesses of Beam Shaping Assembly (BSA) were investigated by simulation.ResultsThe optimized irradiated field at beam outlet of proton cyclotron can reach 95.6% of epithermal neutrons, and 6.26×107 n·cm-2·s-1 of the epithermal flux rate.ConclusionsThis design solution can be initially used for the technical verification of BNCT neutron source experimental terminal.  
        关键词：BNCT;GEANT4;9Be(p,n) reaction;Beam shaping assembly;Epithermal neutron field   
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        发布时间：2024-10-25

        NUCLEAR CHEMISTRY, RADIOCHEMISTRY, RADIOPHARMACEUTICALS AND NUCLEAR MEDICINE

      • “在放射化学纯度分析领域，专家建立了一种快速简便的氯化铜［64Cu］溶液分析方法，满足欧洲药典技术要求，可实现快速、可靠的产品检验。”
        WANG Xiaoming,CHEN Mengyi,WU Fuhai,WEN Kai,ZHAO Hailong,ZHOU Jiajun,LI Hongyu
        Vol. 45, Issue 3, Article number: 030301(2022) DOI: 10.11889/j.0253-3219.2022.hjs.45.030301
        摘要：BackgroundCopper[64Cu] chloride solution is commonly used as raw material for the preparation of radiopharmaceuticals, which can be used in PET imaging or as a paired nuclide for tumor theranostic. Quality control test of copper[64Cu] chloride solution for radiolabelling must be done before use, and the radiochemical purity test is the key item of quality control.PurposeThis study aims to establish a rapid and reliable method for radiochemical purity analysis of copper[64Cu] chloride solution, by screening the test conditions of stationary phase and mobile phase.MethodsiTLC-SG silica gel paper plate was used as the stationary phase, and the mixed solution of dichloromethane, acetonitrile, methanol and 0.05 mol∙L-1 HCl was used as the mobile phase. The reference solution was prepared by mixing the test solution with DTPA solution in equal volume. The test solution and the reference solution were loaded on the paper plate separately and developed using the mobile phase. The kinds of stationary phase, composition and proportion of the mobile phase were optimized.ResultsUnder the optimized conditions, the Rf of the test solution is greater than 0.9 and the Rf of the reference solution is less than 0.1, and the separation degree is greater than 1.0, which satisfies the system suitability of thin-layer chromatography (TLC).ConclusionsEstablished method in this study is simple, reliable and rapid for the detection of radiochemical purity of copper[64Cu] chloride solution, and complying with the technical requirements of European pharmacopoeia for the determination of radionuclide solution for radiolabelling.  
        关键词：Copper[64Cu] chloride solution;Radiochemical purity;TLC;Quality control   
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        发布时间：2024-10-25
      • “环烯烃共聚物COC在医疗器械领域应用广泛，但辐照灭菌会导致性能变化。研究发现，辐照产生的自由基浓度随剂量增大而增加，导致COC分子链断裂和氧化降解，表面亲水性增强。”
        ZHANG Fan,JI Zhenyan,SHEN Rongfang,XING Zhe,WU Guozhong
        Vol. 45, Issue 3, Article number: 030302(2022) DOI: 10.11889/j.0253-3219.2022.hjs.45.030302
        摘要：BackgroundCyclic olefin copolymer (COC), synthesized by catalytic copolymerization of ethylene and norbornene, can be applied in medical devices and drug packaging, owing to its many outstanding properties such as good light transmittance, water vapor barrier and biocompatibility. When this type of medical devices or drug package is sterilized by high energy irradiation, COC will inevitably undergo changes such as radiation scission, oxidation, discoloration and so on. It is of great significance to explain the performance change of COC from the free radical reaction initiated by ionization radiation for the radiation sterilization application of COC medical supplies.PurposeThis study aims to investigate radiation effect of COC in the dose range of radiation sterilization.MethodsEffects of γ-rays on chemical structure, free radical, glass transition temperature, thermal stability, molecular weight distribution, surface properties and melt index of the irradiated COC with the sterilization dose were investigated by Fourier transform infrared spectroscopy (FT-IR), X-ray photoelectron spectroscopy (XPS), ultraviolet-visible absorption spectroscopy (UV-vas), electron spin resonance spectroscopy (ESRS), differential scanning calorimetry (DSC), thermogravimetric analysis (TGA), gel permeation chromatography (GPC), water contact angle (WCA) and melt mass-flow rate measurement.ResultsThe concentration of free radicals produced by COC irradiation in air increases linearly with the increase of absorbed dose. With the increase of absorbed dose, radiation degradation is dominant, hence the average molecular weight of the radiation oxidation products include carbonyl and hydroxyl compounds decreases, and the surface hydrophilicity is enhanced whilst the melt index is increased.ConclusionsThe molecular chain breakage caused by radiation and the reaction between free radicals and oxygen are the main causes of COC degradation.  
        关键词：γ-ray irradiation;Cyclic olefin copolymers;Radiation degradation   
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        发布时间：2024-10-25
      • “在放射性表面去污领域，研究人员采用预乳液聚合法制备了两种表面去污剂，实现了90%以上的去污率，为去污剂技术发展提供新方向。”
        HE Zhiyu,JIANG Huan,CHEN Liang,QIU Tian,LU Yanzhi,LI Yintao,ZHOU Yuanlin
        Vol. 45, Issue 3, Article number: 030303(2022) DOI: 10.11889/j.0253-3219.2022.hjs.45.030303
        摘要：BackgroundStrippable and self-brittle decontaminants are the two most commonly used surface decontaminants. However, peelable decontaminants have problems such as poor mechanical properties and difficulty in peeling whilst the self-brittle decontaminants become brittle due to the diaphragm and cause the potential of secondary pollution during the curing process.PurposeThis study aims to prepare several surface radiaction decontaminants and analyze their performance of decontamination.MethodsFirst of all, butyl acrylate (BA), methacrylic acid (MAA), methyl methacrylate (MMA), acrylic acid (AA) were selected, and preemulsion polymerization was adopted. Two kinds of surface decontaminants with different curing morphology were prepared. Then, the mechanical properties were tested by electronic universal testing machine and the surface of the membrane was observed by optical microscope, and simulated cold decontamination rate test was carried out according to IAEA recommended steps. Finally, action mechanism of surface radioactive decontaminant was studied by wettability and zeta potential test, as well as the combination of detergent and pollutants.ResultsThe test results for BA, MMA, and AA show that the good physical and mechanical properties is achieved when mBA:mMMA:mAA=1:0.9:0.1 hereby the tensile strength can be up to 9.16 MPa and the breaking elongation can be up to 671%, which is a good peeling detergent substrate. Particle size control of MAA and MMA can control the solidification morphology of decontaminant.ConclusionsThe two detergents can be completely excreted and embrittled on different surfaces and forms, and the decontamination rate of simulated nuclides can reach more than 90%.  
        关键词：Surface decontaminant;Peelable;Self-brittle   
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        发布时间：2024-10-25

        NUCLEAR PHYSICS, INTERDISCIPLINARY RESEARCH

      • “东方超环装置通过充入适量氖气或氩气实现辐射偏滤器运行模式，有效降低靶板热负荷，缓解高能粒子流损伤。专家建立了不同杂质浓度估算方法，为优化辐射偏滤器运行参数提供重要参考。”
        JI Huajian,ZHANG Hongming,YANG Xiuda,YIN Xianghui,LI Kedong,HE Liang,FU Jia,WANG Fudi,SHEN Yongcai,WAN Shunkuan,LYU Bo,GONG Xueyu,GONG Xianzu,ZANG Qing,WANG Yumin,LIN Xin,WANG Shouxin
        Vol. 45, Issue 3, Article number: 030501(2022) DOI: 10.11889/j.0253-3219.2022.hjs.45.030501
        摘要：BackgroundBy injecting gaseous neon (Ne) or argon (Ar) into the divertor region, the radiative divertor operation mode has been successfully realized on experimental advanced superconducting tokamak (EAST). During the radiative divertor operation phase, the damage to divertor plates is effectively mitigated by reducing heat load from high energy particles. However, the injected excess impurity gas may penetrate the last closed flux surface and transport to the core region, causing the degradation of core plasma confinement.PurposeThis study aims to develop an evaluation method to measure the core impurity concentration for assessment the effects of injected impurity on the confinement of core plasma.MethodsThe absolute intensity of impurity radiation characteristic line was measured and calculated in combination with collisional radiation model (CR model), and different evaluation methods of impurity concentration were developed for different impurity species. The concentration of impurity tungsten (W) was evaluated by combining the radiation intensity measurement from extreme ultraviolet spectroscopy and CR model whilst the concentration of impurity Ne was assessed on the basis of measurement of effective charge number (Zeff). The impurity level in the core region was analyzed in details.ResultsMeasurement and model calculation results show that the concentration of Ne and W impurities in the core increases significantly after Ne impurity injected.ConclusionsThe evaluation method in the study is important for evaluating confinement in the core region during radiative divertor and improving plasma performance.  
        关键词：Impurity concentration;Impurity transport;Radiative divertor operation;Extreme ultraviolet spectroscopy;Effective charge number   
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        发布时间：2024-10-25
      • “在合成生物学领域，研究人员通过基因电路调控细菌蛋白表达，将生物膜改造成活体材料。但生物膜机械性能较弱，限制了其应用。本研究通过融合蛋白表达和碳酸钙矿化，增强了生物膜的机械性能，为活体功能材料设计提供新思路。”
        QIN Simin,LIU Suying,ZHU Ying,LYU Min
        Vol. 45, Issue 3, Article number: 030502(2022) DOI: 10.11889/j.0253-3219.2022.hjs.45.030502
        摘要：BackgroundBacterial biofilm is a structure formed by bacteria communities living in a self-produced matrix of extracellular polymeric substances (EPS) composed of polysaccharides, proteins, nucleic acids, and so on. In the field of synthetic biology, bacterial biofilms can be transformed into variable active functional materials by regulating the expression of specific bacterial proteins with different gene circuits. However, the weak mechanical properties of bacterial biofilms limit the application of these materials in wearable devices, coatings and building materials. [Propose] This study aims to investigate the effect of expression of fusion protein to the mechanical property of bacterial biofilm, and the non-opportunistic pathogen Bacillus subtilis was selected as model strain.MethodsThe engineering bacterial biofilm was prepared as a block gel by traditional calcium carbonate mineralization method. After characterization with synchrotron radiation X-ray transmission microscope, scanning electron microscope (SEM) and transmission electron microscope (TEM), the mechanical property of the original biofilm and biofilm gel was studied by rheological analysis.ResultsResults of rheological test show that slight increase of the storage modulus is discovered, indicating the enhancement of the mechanical property of biofilm block gel, and the bacterial structure inside the biofilm is complete and remains active.ConclusionsThis study provides a new idea for the biomimetic mineralization of bacterial biofilms and the design and preparation of active functional materials.  
        关键词：Bacterial biofilm;Synchrotron based X-ray transmission microscope;Fusion protein;Mechanical property;TasA-n16N   
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        发布时间：2024-10-25

        NUCLEAR ENERGY SCIENCE AND ENGINEERING

      • “在铅基快堆领域，专家构建了100 MWt堆芯模型，研究冷却剂选型，发现208Pb-Bi冷却剂能实现堆芯小型化、长寿命和固有安全性。”
        YU Qingyuan,XIAO Hao,LIU Zijing,ZHAO Pengcheng,YU Tao
        Vol. 45, Issue 3, Article number: 030601(2022) DOI: 10.11889/j.0253-3219.2022.hjs.45.030601
        摘要：BackgroundSmall long life natural circulation lead-based fast reactor has broad development prospects in the fields such as marine nuclear power, portable power, thermal-electric co-generation in remote areas, seawater desalination, et al., and is one of the important development directions of lead-based fast reactor.PurposeThis study aims at the coolant selection for the design goals of long life, miniaturization and natural circulation of lead-based fast reactors.MethodsFirst of all, refer to the ALFRED design scheme of EU small lead based demonstration fast reactor, a 100 MWt lead-based fast reactor core model was taken as design paramenters. Then, Pb element/mixture and Pb-Bi mixtures were selected for study by using three dimensional transport Monte Carlo code (RMC) developed by the reactor engineering calculation and analysis laboratory of Tsinghua University. High temperature nuclear database ADS-2.0 released by the International Atomic Energy Agency was employed to calculate and analyze the burnup characteristics, reactivity coefficient and effective delayed neutron fraction of lead based fast reactor cores with different coolants. Finally, the neutronics characteristics of different coolant cores and the natural circulation characteristics of different coolants were analyzed and compared.ResultsThe results show that the neutron capture cross-section combined with Bi is smaller due to the small inelastic scattering cross-section of 208Pb in the high-energy region and the extremely small neutron capture cross-section in the middle and low energy regions. The 208Pb-Bi cooled lead-based fast reactor core has the lowest burnup reactivity loss and the best breeding performance with large negative void coefficient, coolant temperature coefficient and large effective delayed neutron fraction in at 30 EFPY operating cycle.ConclusionsThe 208Pb-Bi cooled lead-based fast reactor core can be loaded with a lower enrichment or a smaller amount of fuel, which is beneficial to miniaturization, long life and inherent safety of the core; compared with Pb, 208Pb-Bi cooled lead-based fast reactor has stronger natural circulation capability, weaker material corrosion, and wider operating temperature range, which is conduvtive to the safe operation and maintenance of reactor.  
        关键词：Lead-based fast reactor;Coolant selection;Neutronics characteristics;Natural circulation   
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        发布时间：2024-10-25
      • “在钠冷快堆钠泄漏事故研究领域，专家改进了Tsai钠雾火模型，有效预测了钠喷雾燃烧现象，为钠泄漏事故分析提供新方法。”
        YU Zhitong,CAO Xuewu
        Vol. 45, Issue 3, Article number: 030602(2022) DOI: 10.11889/j.0253-3219.2022.hjs.45.030602
        摘要：BackgroundDuring a sodium leakage accident in sodium fast reactor, the sodium droplets reacted violently with air in the process of ejection, resulting in a sodium spray fire.PurposeThis study aims to analyse the applicability of modified Tsai sodium spray fire model based on the experimental results.MethodsFirst of all, the droplet dynamic model in Tsai model was changed to constant velocity model, the influence of sodium combustion was set to instantaneous. Then the influences of different experimental stages in the T3 experiment of Sandia National Laboratories (SNL) on the applicability of the model were analyzed in by comparison of the model prediction results with the experimental measurement. Meanwhile the influence of initial oxygen concentration on the applicability of the model was analyzed in the spray fire experiments of Atomics International (AI). Finally, sodium generator was taken into consideration in low oxide concentration conditions.ResultsThe analysis results show that the predictions of modified spray fire model are consistent with the atmosphere temperature and pressure changes as well as the sodium consumption of sodium spray fire in air.ConclusionsThe modified sodium spray fire model is suitable for predicting the combustion behavior of sodium spray in the air when sodium leakage accident occurs in sodium-processing room.  
        关键词：Sodium spray fire model;Applicability analysis;Sodium fast reactor   
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        发布时间：2024-10-25
      • “液态燃料熔盐堆动力学模型研究取得进展，开发了三维动力学程序ThorCORE3D，为堆稳态设计与瞬态分析提供解决方案。”
        ZUO Xiandi,CHENG Maosong,DAI Zhimin
        Vol. 45, Issue 3, Article number: 030603(2022) DOI: 10.11889/j.0253-3219.2022.hjs.45.030603
        摘要：BackgroundIn molten salt reactors (MSRs), the liquid fuel salt circulates in the whole primary loop. Part of the delayed neutron precursors (DNP) decay outside the reactor core, but most of the reactor fission power releases directly in the fuel salt. Therefore, the neutronics kinetics (NK) and thermal-hydraulics (TH) are strongly coupled due to the liquid fuel in MSRs, hence traditional dynamic codes cannot be used for MSRs.PurposeThis study aims to develop and validate a three-dimensional time-spatial dynamic code named ThorCORE3D which can be used to carry out design and transient analysis of MSRs.MethodsNodal expand method was used to solve time-dependent neutron diffusion equations and a thermal-hydraulics solver for circulating liquid fuel with internal heat source was developed in ThorCORE3D. Then the code was validated using both steady state and transient experimental benchmark questions of Molten Salt Reactor Experiment (MSRE) of Oak Ridge National Laboratory (ORNL).ResultsThe results show that numerical results from ThorCORE3D are in good agreement with the experiment results and that of other codes. The unique phenomena in MSRs can be well modeled and simulated by the ThorCORE3D.ConclusionsThe ThorCORE3D dynamics code can be used reliably for steady state and transient analyses of liquid fuel MSRs.  
        关键词：Molten salt reactor;Coupled neutronics and thermal-hydraulics;Delayed neutron precursors   
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        发布时间：2024-10-25
      • “在低普朗特数流体传热特性预测领域，研究者采用SST k-ω湍流模型，分析了不同湍流普朗特数模型的适用性，为铅铋传热特性预测提供解决方案。”
        LIU Shuyong,YU Dali,MEI Huaping,WANG Zhen,ZHANG Shichao,LI Taosheng
        Vol. 45, Issue 3, Article number: 030604(2022) DOI: 10.11889/j.0253-3219.2022.hjs.45.030604
        摘要：BackgroundIn order to accurately predict the heat transfer characteristics in the sub-channel of fuel assembly for the low Prandtl number fluid, it is necessary to select a suitable turbulent-Prandtl-number model.PurposeThis study aims at the applicability of turbulent-Prandtl-number models for liquid lead-bismuth turbulence in triangular fuel rod bundles.MethodsBased on the triangular rod bundle heat transfer correlation, the turbulent models of Shear Stress Transfer (SST) k-ω was adopted to analyze the different rod bundle structures for five different kinds of turbulent-Prandtl-number models. The analysis results were compared with the recommended heat transfer correlation, which had been verified by experiment in the sub-channels for liquid lead-bismuth. The applicability of various turbulent-Prandtl-number models under different rod diameters and pitch diameter ratios was analyzed in details.ResultsThe results show that the global turbulent-Prandtl-number model is not only related to the Reynolds number Re and Peclet number Pe, but also related to the pitch-to-diameter ratio (P/D). In the entire region of (1.3≤P/D≤1.7), simulation results of turbulent-Prandtl-number model proposed by Kays are in good agreement with the values calculated by Mikityuk equation. All sorts of turbulent-Prandtl-number models have the best P/D scope of application.ConclusionsThe related turbulent-Prandtl-number models can be used to predict the heat transfer characteristics of liquid lead-bismuth in the triangular rod bundles under different pitch diameter ratios.  
        关键词：Lead-cooled fast Reactor;Triangular rod bundles;Low Prandtl number fluid;Turbulent-Prandtl-number model;CFD numerical simulation   
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