最新刊期

    40 4 2017

      NUCLEAR ENERGY SCIENCE AND ENGINEERING

    • Chen GUO,Ruimin JI,Jingen CHEN,Guimin LIU
      Vol. 40, Issue 4, Article number: 040602(2017) DOI: 10.11889/j.0253-3219.2017.hjs.40.040602
      摘要:Background Thorium molten salt reactor-liquid fuel (TMSR-LF) is a thermal molten salt reactor (MSR) with on-line reprocessing to extract waste and poison elements. Helium bubbling technique is considered to extract waste gas i.e., Xe, Kr, from the reactor core in order to improve neutron economics. Purpose This study aims to implement the MSRE 135Xe poison model, and apply it on TMSR-LF1 of Shanghai Institute of Applied Physics (SINAP) to estimate xenon poison and effective multiplication factor. Methods A 135Xe poison model with helium bubbling technique was built based on the molten salt reactor experiment (MSRE) research conducted at the Oak Ridge National Laboratory (ORNL) in the 1960s. Compared with present simulation which ignores the 135Xe diffusion behaviors in the fluid salt and graphite, this model provides a better description for a MSR. The nuclear reaction from Scale6.1 and diffusion process on the MATLAB platform were combined for 135Xe analysis in TMSR-LF1. Results The result shows that helium bubbling technique can remove 135Xe and reduce xenon poison effectively. Most of 135Xe will stay in graphite. Conclusions Xenon poison model considering 135Xe diffusion and flow effect is reasonable.  
      关键词:Molten salt reactor;Xenon poison;Helium bubbling;On-line reprocessing;Effective multiplication factor   
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      发布时间:2021-05-19
    • Luyu ZHANG,Zhimin WANG,Huaiyong BAI,Jinxiang CHEN,Guohui ZHANG
      Vol. 40, Issue 4, Article number: 040604(2017) DOI: 10.11889/j.0253-3219.2017.hjs.40.040604
      摘要:Background AP1000, developed by the Westinghouse, is a pressurized water reactor with advanced passive safety systems. Two core fuel configuration schemes, D19 and Adv, are available for the AP1000. Purpose This study aims to design a new core configuration scheme for AP1000, and compare it with D19 scheme by using Monte Carlo code Methods First of all, a new core configuration scheme that combines the advantages of the D19 and Adv schemes was put forwarded. Then the D19 core scheme and the new core scheme were modeled by using the MCNP6 code. Finally, main nuclear design parameters of the new core scheme were calculated according to the varied fuel burnup. Results The results indicate that the main physical parameters of the new scheme agree well with the AP1000 nuclear design criterion over the lifetime period of the first cycle. Conclusions With the function of burnup calculation, Monte Carlo code MCNP6 play a good role in the reference process of core physical design by massively parallel computing.  
      关键词:AP1000 reactor;Fuel configuration scheme;MCNP6 code;Nuclear design parameters;Burnup calculation   
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      发布时间:2021-05-19
    • Xuehui LI,Zijing LIU,Jinsen XIE,Tao YU,Zhenping CHEN,Qin XIE,Wenjie ZENG,Lihua HE
      Vol. 40, Issue 4, Article number: 040603(2017) DOI: 10.11889/j.0253-3219.2017.hjs.40.040603
      摘要:Background Geometry preprocessing, such as mesh division, between the characteristic line, polar angle quadrature set, the number of polar and azimuth angles and so on, has a great impact on computational accuracy and efficiency of the method of characteristics (MOC). Purpose This paper based on step characteristics method (SC) has developed a neutron transport calculation code. Methods Through numerical calculations, it has been verified the correctness of the program and has analyzed and compared two characteristic line scan method (fore and aft disconnect loop scanning method, the head-tail circulation scanning method). In addition, based on head-tail circulation scanning method, conducted a series of sensitivity analysis of the calculation accuracy about mesh division, between the characteristic line, polar angle quadrature set, the number of polar and azimuth angles. Results Program is accurate and reliable and the head-tail circulation scanning method has faster convergence rate than fore and aft disconnect loop scanning method. Conclusions Mesh division less than 2.5 cm can meet the calculation accuracy requirements and characteristic line spacing 0.1 cm and four azimuth has the highest calculation precision. More number of polar angle has higher calculation accuracy, two discrete polar angle has enough meet the accuracy requirements; the four arranged azimuth in the first quadrant should be laied out with two angles at both sides of 45·angle; Tabuchi and Yamamodo (TY) quadrature weighted have slightly higher calculation accuracy than Leonard (LO) quadrature set.  
      关键词:MOC;Geometry preprocessing;Circulation characteristic line scan   
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      发布时间:2021-05-19
    • Mudan MEI,Dafu LIN,Xingwei CHEN,Rui YAN,Minghai LI,Yang ZOU
      Vol. 40, Issue 4, Article number: 040605(2017) DOI: 10.11889/j.0253-3219.2017.hjs.40.040605
      摘要:Background Molten salt pebble-bed reactor is one of the six generation Ⅳ reactor types, and is a new reactor, in the thermal-hydraulic design of pebble bed dense experiment facility (PBDE) of molten salt reactor, the uniform flow field distribution of the core is the prerequisites of the experiment, and the distribution plate plays a decisive role in the flow filed distribution of the core. Purpose This study aims to design a reasonable distribution plate to get steady flow field in the core of PBDE, so that the fuel spheres can keep stable floating in the core. Methods To realize uniform flow field distribution of the core, the distribution plates which have different shapes and channel arrangements are designed based on PBDE. The flow field of the core is simulated using the FLUENT software. Results The simulation results showed that the conical distribution plate will produce some non-uniform flow field in the center area of the core, and the flat distribution plate can get the uniform flow field distribution better in the core compared with the conical distribution plate, in addition, the increase of channels or the decrease of apertures of the distribution plates can also make the flow field of the core more uniform. Conclusions The design of the reasonable distribution plate is significant to get the uniform flow field of the core, this study shows the basis for the experiment of PBDE, and provides the technical support and reference for the later design of the core distribution plate to the molten salt reactor.  
      关键词:Molten salt pebble-bed reactor;Experiment facility;Distribution plate;Computational fluid dynamics (CFD)   
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      发布时间:2021-05-19
    • Jiaxu ZUO,Xinli GAO,Chaojun LI,Wei SONG,Kunpeng WANG,Qiaofeng LIU,Jianping JING,Chunming ZHANG
      Vol. 40, Issue 4, Article number: 040601(2017) DOI: 10.11889/j.0253-3219.2017.hjs.40.040601
      摘要:Background ThoriumMolten Salt Reactor (TMSR) project is one of the Strategic Priority Programprojects of Chinese Academy of Sciences. Based on the design of 10-MWThermal Molten Salt Reactor-Solid Fuel (TMSR-SF), the preliminary study on safety analysis of TMSR about the key technology are done. Purpose This study aims to prepare the technology and requirements for TMSR-SF safety review, and show the guidance and support to the design. Methods The study includesfour areas: core nuclear design safety limits, accident analysis and acceptance criteria, the source term and the review methods and acceptance criteria, probabilistic riskassessment (PRA) methods and initiating events.The safety review methods of other type reactors have been studied and compared. The key parameters and important regulations have been summary. From review and summary of the high temperature gas coolant reactor and sodium cooled fast reactor, based on the logic diagram methods, the PRA framework of TMSR-SF and initiating events list are discussed. The Monte Carlo and other methods and models are used to calculate the key core nuclear design safety parameters limits of TMSR-SF. The accident list and classification are studied and discussed from computational fluid dynamics (CFD) calculation. Results The core design of TMSR-SF has sufficient negative reactivity coefficientsunder operating conditions.The temperature limit could reference high temperature gas cooled reactor and could be set to 1495 ·C. The shutdown margin should not be less than 0.2 for TMSR-SF. Conclusions The preliminary accident type and accident event list of design basis have been setup, and the initialingevents listhas been discussed.The study will support the safety review and safety design of TMSR-SF.  
      关键词:TMSR-SF1;Safety analysis;Core design;Accident analysis;Source term;PRA   
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      发布时间:2021-05-19
    • Yanfeng ZHAO,Weiwei FAN,Chen YUAN,Chunyu JIANG,Shan SUN,Wei ZHANG,Zejie YIN
      Vol. 40, Issue 4, Article number: 040402(2017) DOI: 10.11889/j.0253-3219.2017.hjs.40.040402
      摘要:Background The hard X-ray diagnostic system is important for HL-2A Tokamak experimental facility. In order to improve the diagnostic performance, a new hard X-ray detector with better precision is required. Purpose This study aims to design a new type of hard X-ray detector to measure X-ray spatial energy spectrum and radiation intensity distribution for HL-2A. Methods The new hard X-ray detection system is composed of lutetium-yttrium oxyorthosilicate (LYSO) scintillator and silicon photomultiplier (SiPM). Selection of the detector and detector design based on the Monte Carlo particle transport simulation tool GEANT4 are effectuated to meet the application requirements of the project. Corresponding front-end electronics was implemented together with the detector to measure the hard X-ray spatial energy spectrum and radiation intensity distribution on site. Results The hard X-ray spatial energy spectrum with time resolution of 10 ms was successfully obtained in the experimental test using proposed new type of hard X-ray detector on the HL-2A Tokamak facility. Conclusion Experimental results show that the detector array has good time resolution and meets the high-precision measurement demand of hard X-ray dynamic spectrum and intensity distribution in plasma diagnose for HL-2A Tokamak facility. It has the advantages of compact structure and easy to use as well.  
      关键词:LYSO;SiPM;HL-2A Tokamak;Hard X-ray detection   
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      发布时间:2021-05-19
    • Shuang HONG,Yongwei YANG,Lu ZHANG,Yucui GAO
      Vol. 40, Issue 4, Article number: 040502(2017) DOI: 10.11889/j.0253-3219.2017.hjs.40.040502
      摘要:Background OpenMC is an open source Monte Carlo code developed by the Computational Reactor Physics Group (CRPG) of Massachusetts Institute of Technology (MIT). It is convenient to use OpenMC to generate the multigroup cross sections and high order Legendre scattering cross sections based on specific core neutron spectrum, which could be applied to the widely used discrete ordinate transport code ANISN. Purpose This study aims at producing the ANISN multigroup cross section library based on the ENDF/B-Ⅶ.1 and CENDL-3.1 evaluated neutron database using the OpenMC code and validating the accuracy of the calculation results through the benchmark calculation. Methods Since the output of OpenMC is a text file containing the 0-Nth scattering moments, absorption rate, scattering rate, total reaction rate, fission neutron production rate and neutron flux, we wrote a cross section convert code to match the output data with ANISN cross section library format. Results To validate the correction of the cross section libraries, we perform a critical benchmark and calculate the neutron effective multiplication factor keff and the neutron flux F. It shows that the results given by ANISN using the library generated by OpenMC are in good agreement with Monte Carlo calculation. Conclusion The OpenMC code can be used to provide the multigroup cross sections and high order Legendre scattering cross sections for the ANISN code effectively and this can be applied to the two-dimensional and three-dimensional neutron transport calculation in the future.  
      关键词:OpenMC;Multigroup cross section;ANISN;ENDF/B-Ⅶ.1;CENDL-3.1   
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      发布时间:2021-05-19
    • Zhiqiang LI,Detao XIAO,Guizhi ZHAO,Jian SHAN,Xijun WU,Qingzhi ZHOU
      Vol. 40, Issue 4, Article number: 040201(2017) DOI: 10.11889/j.0253-3219.2017.hjs.40.040201
      摘要:Background Rapid measurement of radon exhalation rate is influenced strongly by external environmental factors. Purpose This study aims to scientifically evaluate the accuracy of the measured result of radon exhalation rate according to the concept of uncertainty. Methods A theoretical analytical model was estimated to study the measurement method of radon exhalation rate. The origin of the uncertainty was analyzed and employed to evaluate the accuracy of the result. Results The result of the relative synthesis standard uncertainty diverges within 12% when the rapid measurement is applied on the standard device of the University of South China with a radon exhalation rate of 0.39-2.62 Bq·m-2·s-1 in 105 min. Conclusion This study provides a new method to evaluate the rapid determination of radon exhalation standard device.  
      关键词:Radon exhalation rate;Rapid measurement;Evaluation of uncertainty   
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      发布时间:2021-05-19
    • Guokai YU,Yuhui WEI,Lin LIU,Ping ZHANG,Shuo WANG,Wenjing LIU,Xingfei ZHOU,Bin LI
      Vol. 40, Issue 4, Article number: 040501(2017) DOI: 10.11889/j.0253-3219.2017.hjs.40.040501
      摘要:Background The mechanical mapping mode of atomic force microscopy (AFM) enables to measure mechanical properties of materials while imaging with high-resolution. However, to measure the elastic Young's modulus of biomolecules is still a challenge because they are so small, soft and thin. Purpose This study aims to explore the compression elasticity of DNA origami and the different forces on the effect of Young's measurement on the deoxyribonucleic acid (DNA) origami sample. Methods The peak force imaging mode (Peak Force Quantitative Nanomechanical Mapping, PF-QNM) was used to measure the Young's modulus of DNA origami under various activing forces. Results It was found that by using of 80-100pN peak forces, the elastic Young's modulus measurement results were relatively stable, keeping about 10 MPa for the peak force measurement on DNA origami. Compared with the traditional force volume contract mode (Force volume mapping, FV), the values obtained consisted well with that of FV when the force were limited below 100 pN. Conclusion This method provided a simple and effective way for quantitative measuring the elasticity of DNA molecules.  
      关键词:AFM;DNA origami;Young's modulus;PF-QNM   
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      发布时间:2021-05-19
    • Jingyi XU,Xianglong LI,Jie LI,Jiale WU,Lei TANG,Chengyi GUO,Chunlei HE
      Vol. 40, Issue 4, Article number: 040301(2017) DOI: 10.11889/j.0253-3219.2017.hjs.40.040301
      摘要:Background Ya'an Tibetan tea is one of the earliest dark teas in China. It has been drunk for more than a thousand years in the border, and has become a life tea and the main prescription for disease prevention of the ethnic minority. Purpose The aim is to investigate the protective effect of the theabrownines (TB) of Ya'an Tibetan tea on the damage of 60Co γ-ray radiation by establishing injury mice model caused by 60Co γ radiation. Methods 48 male SPF mice were randomly divided into normal control group, radiation model group, and positive control group, low, medium and high-dose groups of the TB of Ya'an Tibetan tea. The mice were continuously fed for 15 d. On the 6th day of intragastric administration, all of the mice except for the normal group were subjected to 60Co γ-ray irradiation with a dose of 5 Gy. On the 16th day after weighing, the mice were taken for blood from eyeballs and anatomy. The related indicators of the number of peripheral blood cells, deoxyribonucleic acid (DNA) content of bone marrow, chest spleen index, and total antioxidant capacity of liver tissues were determined. Results Compared with radiation control group, the TB of Ya'an Tibetan tea could significantly improve the number of white blood cells, platelets and lymphocytes in the blood of radiation-injured mice, and significantly enhance cell activity of blood superoxide dismutase and catalase (p < 0.01), and could significantly increase total antioxidant capacity (T-AOC), total superoxide dismutase (T-SOD) activity of liver tissue of the mice ( p < 0.01) and bone marrow DNA content of the femur. At the same time, the content of malondialdehyde (MDA) in liver was significantly decreased ( p < 0.01). TB could significantly relieve the atrophy of thymus and spleen gland of the immune organs of the mice, and the effect increases with the increase of TB concentration. The effect of high dose group is comparable to or better than the effect of positive drug. Conclusion The TB of Ya'an Tibetan tea has a good protective effect on the antioxidant system and hematopoietic system of the mice irradiated with 60Co γ-ray, where high-dose group has the most obvious effect.  
      关键词:TB;Ya'an Tibetan tea;60Co γ radiation;Antioxidant system;Hematopoietic system;Protection   
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      发布时间:2021-05-19
    • Weiwei XIE,Lingzhi HU,Xuexiang CAO,Xu CHU,Qun CHEN
      Vol. 40, Issue 4, Article number: 040302(2017) DOI: 10.11889/j.0253-3219.2017.hjs.40.040302
      摘要:Background Simultaneous position emission tomography (PET) /magnetic resonance imaging (MRI) plays an important role in diagnosis of many brain diseases. However, brain motion caused by epilepsy, Parkinson's disease or muscle contraction and relaxation in head and neck is inevitable during the scanning. Motion artifact is one of the key factors that affect the quality of PET brain imaging. With PET/MRI, it becomes possible to use motion information obtained with MRI to correct for the PET image artifacts due to the high resolution of MRI. Purpose This study aims to verify line of response (LOR) based motion correction method is more accurate than frame-based motion correction method in PET/MRI brain imaging, considering more precise information from MRI than previous methods. Methods Rigid motions of NEMA (National Electrical Manufacturers Association) phantom and XCAT (the 4D extended cardiac-torso) phantom were simulated by using Monte Carlo method, i.e., the medical imaging simulation software GATE (GEANT4 application for tomographic emission). PET data was corrected using the two methods within open source reconstruction software STIR (software for tomographic image reconstruction). The reconstructed images of NEMA imaging quality (IQ) phantom were evaluated by contrast recovery coefficient (CRC) curves and the images of XCAT phantom were evaluated using full width at half maximum (FWHM) measurement of the lesion. The rigid phantom motion information was corrected by registering MRI images using gradient echo quick 3D sequence during PET/MRI scanning simultaneously, because MRI features high speed in imaging and high spatial resolution. Then, PET data was reconstructed using MRI derived motion vector to verify and evaluate the accuracy of these two motion correction methods. Results FWHM values of reconstruction results compensated by both methods were significantly lower than the ones without motion correction. LOR based FWHM values were lower than those corrected by the frame-based methods both in XCAT simulation data and experiment data. Similarly, for NEMA IQ simulation data, the CRC curves had a higher upward tendency of both hot and cold spheres than the ones without motion correction, and the CRC curves of all spheres from LOR based method were higher than frame-based ones. Conclusion By quantitative and qualitative analysis of both simulation and experiment corrected data, we concluded that both methods can compensate motion artifacts, and the LOR based method outperforms frame-based method for PET data compensation in simultaneous PET/MRI scanning.  
      关键词:PET/MRI;Brain motion correction;Gradient echo quick 3D sequence   
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      发布时间:2021-05-19
    • Yawen LI,Zhe NING,Sen QIAN,Na ZHU,Feng GAO,Xiaoshan JIANG,Yinhong ZHANG,Hao CAI
      Vol. 40, Issue 4, Article number: 040401(2017) DOI: 10.11889/j.0253-3219.2017.hjs.40.040401
      摘要:Background Large-scale scientific facilities need bunch test for their key devices, and need the special database to manage the test results. Purpose This study aims at the practical requirements of data management for experimental devices, such as photomultiplier tube (PMT) and readout electronics cable, etc. and the design of related database based on the Ionic development platform for scientific facility. Methods Angular.js, Ionic, HTML5 are employed to implement the front-end, whilst Node.js, Express are used for the back-end services. Combine with the MySQL, a data management system is generated to run across various platforms such as the mobile client and the Web side. Results The database software can execute in different browsers (Chrome, IE, Safari) via various operating systems (Windows Phone, Android, IOS) with the same code. Conclusion With functionality of track, record and query the variety of test data for all experimental devices, this database provides effective protection for the conduct of the experimental project.  
      关键词:Ionic;Database;Angular.js;Express;MySQL   
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      发布时间:2021-05-19

      NUCLEAR PHYSICS, INTERDISCIPLINARY RESEARCH

    • Rui CHEN,Lijuan HAO,Jing SONG,Bin WU,Peng HE
      Vol. 40, Issue 4, Article number: 040503(2017) DOI: 10.11889/j.0253-3219.2017.hjs.40.040503
      摘要:Background As temperatures are constantly changing in nuclear reactor operation, on-the-fly Doppler broadening methods are commonly adopted for generating nuclear cross section for various temperatures in transport simulation. Among the existing methods, the SIGMA1 approach is exact but inefficient due to involving of error function and Taylor series expansion. Purpose In this paper, we proposed a piecewise Gauss quadrature method for on-the-fly Doppler broadening based on SuperMC to improve efficiency with given accuracy. Methods According to the cross section features of different energy regions, Gauss-Legendre quadrature was used in low-energy region, while the Gauss-Hermite quadrature used in high-energy region. Results The comparison of typical nuclides cross section and benchmarking with Godiva and Doppler coefficient of reactivity were presented in detail, which indicated that the new method could generate neutron cross section rapidly and precisely at various temperatures. Compared with SIGMA1 method, the proposed method improved the computing efficiency by an average of 5 times, and higher temperature could promote the broadening efficiency. Conclusions It showed the method could be applied in multi-physical coupling calculation of reactor.  
      关键词:Neutron cross section;Gauss quadrature;On-the-fly;Doppler broadening;SuperMC   
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