摘要:Background: Quick-scanning X-ray Absorption Fine Structure (QXAFS) is a powerful tool for measuring and determining the environmental structure of specific absorption atoms. It has been widely applied in the fields of solid state physics, catalyst and protein molecules. Double Crystal Monochromator (DCM) is a key device at XAFS beamline of Shanghai Synchrotron Radiation Facility (SSRF). It is used to change the certain wavelength of white light to monochromatic light and pass it to follow-up optical elements. The Bragg motor of the DCM is a step motor and its control system adopts Experimental Physics and Industrial Control System (EPICS) while the data acquisition system (DAQ) of QXAFS is developed in LabVIEW. Purpose: The present QXAFS control system at the XAFS beamline is using LabVIEW based DAQ which contains some drawbacks, such as the energy drift and spectrum distortion. It is running in the Windows operating system environment while the DCM control system is running in Linux. The network transmission delay occurs at the communication between the two different kinds of system. The aim of this study is to design and implement fast time-resolved QXAFS data acquisition system based on EPICS that can solve these defects. Methods: Two 1-MHz hardware trigger signal is generated and used to collect the signals of ionization chambers and the step motor synchronously in the new design. The software of the system is developed in EPICS and runs in the Linux operating system environment. The experimental method is implemented by python routine which is also integrated into the Graphical User Interface (GUIG). Results: Conventional XAFS spectrum and four QXAFS spectra with an energy range of 1.2 keV at the Cu K-edge have been collected in less than 8 s at the XAFS beamline. The experimental results indicate the QXAFS system can ensure a good signal-to-noise ratio (SNR), as well as a perfect stability and repeatability. Conclusion: The QXAFS data acquisition system based on EPICS is achieved at the XAFS beamline at SSRF. It has great practical significance for carrying out fast time-resolved QXAFS experiment at SSRF.Cited
摘要:Background: Synchrotron radiation is a special light produced by synchrotron radiation facility, and has been widely used in many fields because of its properties of broad spectrum, high brilliance and excellent collimation. The beam spot size is one important feature of the beamline. The current method used for measuring the spot size is scanning knife-edge technique, which is accurate but time consuming. Purpose: The aim is to find an effective method to get the spot sizes more quickly and more intuitively based on the image processing. Methods: Basic image processing method and adaptive threshold binarization method are employed to resolve the problem. Results: The results show that the image processing program can get the spot size correctly, although the spot size varies in a large range, and what’s more, the new method can show the information about the spot center and spot symmetry simultaneously. Conclusion: The new method is faster and more intuitive compared with the others currently used and it can be considered as an effective diagnosis tool during beamline operation.
Abstract
摘要:Background: Measurement of the fill pattern of synchrotron storage rings is important for several reasons, including checking the quality of the injection system and the generation of special fill patterns for time-resolved experiments. User experiments on these synchrotron radiation sources typically require the pattern to be as exact as possible, with ideally no electrons in unwanted bucket/bunch positions: a typical ratio of 10?5:1 between unwanted/wanted populations is desired. This ratio is often referred as the bunch purity. Purpose: In order to establish a bunch cleaning system, a bunch purity of storage ring has to be set up. Methods: For the time-resolved facility based on the electron storage ring, it is planned to measure the beam quality in a short time of several minutes by using a time-correlated single photon counting method. Results: The purity measurement results show that a purity of 10?5 for BEPCII declines to 10?4 in dozens of hours after injection. Conclusion: A bunch purity measurement system has been set up in BEPCII storage ring using synchrotron light, which can give the bunch purity in tens of seconds. The bunch purity measurement results show the purity of BEPCII is better than 10?4.
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摘要:Background: The upgrade project of Hefei Light Source (HLS) was started in 2009. Improving radiation monitoring system is an important part of the upgrade project. Purpose: This study aims to design and implement a web-based dynamic release system for a real-time and remote multipoint radiation monitoring of HLSII. Methods: Data acquisition and storage section were implemented by using LabVIEW, moreover, the system was integrated into EPICS database with the interface designed by CA Lab. Java combining with Java Server Page (JSP) technique was adopted to complete the design and implementation of the data query system based on Brower/Server. Results: This system is easy to operate and has run stably for several months, meeting the designing requirement. Conclusion: With this system, real-time monitoring and historical data query can be more efficient and convenient for administrators and users. It also provides a good reference for other nuclear devices in the aspect of radiation monitoring data opening to the public.
Abstract
摘要:Background: A new method, energy selective neutron radiography, has been presented to be an advanced technique for determination of the crystalline structures in engineering materials. Numerous studies about the advanced technique were reported by the international well-known neutron scattering research centers. Purpose: The aim is to master the basic principles, instrument configuration optimization scheme and the application field. Methods: We analyzed the basic principles of the energy selective neutron radiography, compared different methods for achieving the monochrome neutron beam, and presented the application field which showed the data analysis methods. Results: When achieving the monochrome neutron beam, the velocity selector could get a much higher intensity but with a coarse resolution, the time of flight (TOF) method could get a much better resolution but with a lower intensity, and by using the double crystal method, the intensity and the resolution could realize the balance. So this technique could be used to enhance the in image contrast, measure the residual stress distribution, analysis the texture and study the phase transition of the materials. Conclusion: Energy selective neutron radiography is a very valuable experimental technique, which has an important application prospect.
Abstract
摘要:Background: Environment gaseous radioactive iodine monitoring is important for nuclear power plant safety. 131I reference source is used as the measurement standard of reference response for environment gaseous radioactive iodine monitoring equipment, which uses glass fibrous filter, active carbon filter and impregnated activated carbon filter cartridge as carriers. Purpose: It is essential to calibrate the reference response for gaseous radioactive iodine monitoring equipment to ensure accurate gaseous radioactive iodine monitoring. Methods: Gaseous radioactive iodine was produced from Na131I solution with ferric sulfate through redox reaction, and collected under environment sampling condition for preparing the 131I reference source. The detection efficiency of high-purity germanium gamma spectrometer for 131I in collection device was determined. Therefore, the 131I reference source was prepared and quantified as a reference standard for field calibration. Results: The experimental results show that the activity of the 131I reference source will be about 10 kBq while the 1 MBq Na131I solution is prepared to get it, the radioactivity value could be adjusted by regulating the activity of the Na131I solution. The detection efficiency of gamma spectrometer for 131I reference source ranged from 4.90% to 6.82%, while the distribution parameter changed from 0.09 mm?1 to 0.34 mm?1. Conclusion: The preliminary experiment shows good practicability of proposed method for the calibration of reference response for gaseous radioactive iodine monitoring equipment.
Abstract
关键词:Gaseous radioactive iodine;Reference response;Iodine collection device;Measurement standard
摘要:Background: The sample preparation system of 14C is necessary for measuring the radioactive contents of 14C and 3H for the decommissioning of nuclear reactor. Previous works were concentrated on the glass container and heating furnace which is not suitable for automatic sample process and exists safety risk. Purpose: In order to resolve the difficulty in main materials of nuclear reactor samples preparation of 14C, an intellectual preparation system of 14C samples was designed and developed. Methods: The system is designed to consist of buffer, decomposition chamber, catalysis bed, adsorption bed and absorbing bed. Samples were decomposed at high temperature in oxygen whilst the generated gas was translated to CO2 by catalysis oxidation. The activity of 14C was measured by liquid scintillation counter using suspension method. Results: The radiochemical recovery rate of 14C was above 70%. The calculated detection limit for 14C was 0.033 1 Bq?g?1 for graphite and 0.021 8 Bq?g?1 for concrete, respectively. Conclusion: This system was stable enough to be used for preparing graphite and concrete samples which contain low level or medium level radioactivity in nuclear reactor.
Abstract
关键词:14C;Intellectualization;Graphite;Concrete;Reactor body material
摘要:Background: The key technology of digital multi-channel pulse amplitude analyzer (DMCA) has been surmounted in China, however, with the increasing of the translation gain increases of DMCA, one of the difficulties is how to make the nonlinear performance index of the system reach the standard. Technology of Dither has been used to realize “Bit Gain” in overseas research while it is still a deficiency in DMCA study in China. Purpose: This study aims to study the application of Dither technology in DMCA and discuss relevant digital Dither technology for DMCA. Method: Based on DMCA architecture characteristics, Dither signal is produced and removed in field programmable gate array (FPGA) by linear feedback shift register (LFSR), and is added to DMCA by the circuit of base line. Energy resolution and differential nonlinearity (DNL) of DMCA system has been measured to study the effect of Dither on DMCA. The mechanism of how the Dither affects DMCA has been analyzed. Results: Experimental tests showed that DNL of DMCA is improved by adding Dither while keep the same the energy resolution, verifying the applicability of this method. Conclusion: The technology method of digital Dither adding for DMCA is of practical significance to the further research to improve the precision of DMCA.
Abstract
摘要:Background: China Spallation Neutron Source (CSNS) is a scientific facility used for studying neutron characteristics and detecting the micro structure of materials. Purpose: This study aims to obtain the position and charge information of incident neutrons for the multipurpose reflectometer of CSNS. Methods: An electronic readout system is designed to detect and handle the signals from a two-dimensional Multi-Wire Proportional Chamber (MWPC). An Application Specific Integrated Circuit (ASIC) chip VA64tap2.1, made by IDEAS company, is applied to get the position and charge information in MWPC. The readout system is comprised of a VA64tap2.1-based readout board, a firmware for Field-Programmable Gate Array (FPGA) and an application program in PC. Results: The tests results show that the system can fulfill the readout requirements, and the ASIC chip is of low noise (less than 0.35fC when connected the MWPC detector), low power dissipation (less than 0.3 mW per channel), large dynamic range (?200?+160fC) and high integration (64 channels/board). Conclusion: This electronic readout system can be used in particle position detection.
Abstract
摘要:Background: Capture-gated neutron detector has been doped by the higher thermal cross section elements, such as 6Li, 10B or natGd, for a fast neutron incident detector signal with n-p recoil impulse and pulse neutron capture associated characteristics. Purpose: The aim is to study the double pulse waveform spectra and to analyze the n-p recoil impulse of the EJ339A capture-gated neutron detector. Methods: Through the analysis of energy spectra and the double pulse waveform spectra, the characteristics of EJ339A capture-gated detector are studied. Results: Capture-gated detector from the energy spectra and PSD spectra measurement is effective for neutron and gamma ray. The wave of digital technology could well analyze the n-p recoil impulse and give the τ value of the EJ339A in the experiment. Conclusion: EJ339A really has captured-gated detector characteristics, pulse neutron capture and n-p associated characteristics of recoil impulse. The capture time of EJ339A is 0.44 μs, which is consistent with the theoretical calculation results.
Abstract
摘要:Background: Fe3O4 nanoparticles have wide applications in biomedical researches. Purpose: The aim is to study the Fe3O4 nanoparticle-protein interactions and their bioeffects. Methods: Transmission electron microscope (TEM), light microscopy, SDS-PAGE (Sodium Dodecyl Sulfonate-Polyacrylamide Gelelectrophoresis), Bradford and MTT (3-(4,5-dimethyl-2-thiazolyl)-2,5-diphenyl-2-H-tetrazolium bromide) methods were used to investigate the Fe3O4 nanoparticle-protein interactions and their bioeffects. Results: The adsorption capacities of Fe3O4 nanoparticle for different proteins were different, and the order was fibrinogen>immunoglobulin>albumin. The adsorption of proteins on the Fe3O4 surface resulted in much reduced cytotoxicity for these protein-coated Fe3O4 nanoparticles. Conclusion: These findings suggest that we should take the Fe3O4 nanoparticle-protein interactions into consideration when designing safe Fe3O4 nanoparticles for biomedical applications.
Abstract
摘要:Background: Segmented Gamma Scanning (SGS) device for radioactive waste barrel has complex structure and many kinds of measurement objects different in their constitution, distribution, range of radioactivity, bulk density, etc. Purpose: If the device for each sample was individually scaled, usually multiple different compositions and cumbersome calibration sources were required, which would cost a lot of time and money. So a reference source with appropriate design is required at first. Methods: Based on the study of calibration methods and Monte Carlo (MC) calculations for waste drums scanning devices, the basic model of reference source for radioactive waste barrels was established. Results: Reference source is composed of a waste barrel rotating in measurement and a linear source which inserted in it and the same height as the barrel. It is the advantage that radioactive material is separated from filling matrix in the barrel and of flexible structure as well as high security. Conclusion: The experimental measurements and MC simulation results are in great agreement especially in high energy point above 344.3 keV. It proves that the reference source can be used in value transfer for SGS devices.
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摘要:Background: The slow neutron capture (s-) process plays a very important role in the nucleosynthesis, which produces about half of the elements heavier than iron. 94Zr is mainly from 93Zr(n,?)94Zr in the s-process, and can be used to study the s-process. And the direct component of the 93Zr(n,?)94Zr capture reaction can be derived from the neutron spectroscopic factors of 94Zr. Purpose: As the existing neutron spectroscopic factors of 94Zr differ from each other up to 60%, a new work should be adopted to measure them exactly. Methods: In the present work, the angular distribution of 94Zr(13C,13C)94Zr, 94Zr(12C,12C)94Zr and 94Zr(12C,13C)93Zr were obtained using the high-precision Q3D magnetic spectrograph. In addition, distorted-wave Born approximation (DWBA) calculations of the transfer differential cross sections were performed. Results: The calculated result was in good agreement with the experiment data, and a value of 2.60±0.20 for the neutron spectroscopic factor of 94Zr was extracted. Conclusion: With the neutron spectroscopic factor of 94Zr obtained in the work, the direct component of the 93Zr(n,?)94Zr reaction can be derived in the near future.
Abstract
摘要:Background: Thorium-uranium fuel cycle is attracting more and more attention because of its unique physical and chemical characteristics. Purpose: Realizing the utilization of thorium fuel in thermal reactors can save the valuable natural uranium resources and produce more fissile fuel, which is conducive to the nuclear energy sustainable development. Methods: ORIGEN code was used to simulate the build-up characteristics of 232Th, 233Th, 233Pa and 233U in neutron fluency rates and neutron spectra of typical Boiling Water Reactor (BWR), Pressurized Water Reactor (PWR) and Canada Deuterium Oxide Uranium (CANDU) reactor, and the effects of multiple “irradiation-cooling” cycles on the thorium uranium conversion rate under various irradiation time were analyzed by numerical comparison. Results: Simulation results showed that the maximum inventory of 233Th and 233Pa is irrelevant to the neutron fluency rates when neutron spectrum is fixed. When the neutron fluency rates are preset, the harder the neutron spectrum is, the larger the maximum inventory of 233U will be obtained. Multiple “irradiation-cooling” cycles can improve the conversion rate of 232Th-233U, but the relative increment is becoming smaller and smaller, compared to the continuous irradiation conversion rate. Conclusion: This work provides relevant theoretical basis for thermal reactors thorium-uranium fuel cycle research.
Abstract
关键词:Neutron fluence rate;Neutron spectrum;Conversion rate of 232Th-233U
摘要:Background: The 10-MWt TMSR-SF (Thorium-based Molten Salt Reactor-Solid Fuel) uses TRISO (Tri-structural isotropic) fuel and the fluoride salt is taken as a primary coolant. The molten salt could attach at the fuel element when the fuel was discharged from the core, which may consequently affect the reactivity of the spent nuclear fuel storage system. Purpose: This study aims to analyze the effects of the molten salt attached at the fuel element to the criticality safety of the spent nuclear fuel storage system. Methods: First of all, the TRITON (Transport Rigor Implemented with Time-dependent Operation for Neutronic depletion) module in SCALE was employed to calculate the burn-up results of the TRISO fuel in TMSR-SF reactor core, then in the premise of the maximum impregnated amount that the molten salt’s volume is 13.9% of the graphite’s volume, the criticality analysis of the spent nuclear fuel storage system was carried out by using MCNP code. Finally, the effects on the reactivity of spent fuel under conditions of molten salt infiltrated the fuel element and coated on the fuel element were compared separately. Results: Computational results showed that the reactivity in the situation that molten salt infiltrated the fuel element would be 5% greater than the molten salt coated the fuel surfaces, but is still in sub-criticality. The reactivity would be even smaller than that of the fuel elements contained only. Conclusion: Molten salt attached at the fuel element would affect the reactivity of the storage system, but the spent nuclear fuel storage system keeps in sub-criticality, which indicates the spent nuclear fuel storage system for TMSR-SF would remain in safety state.
Abstract
关键词:TMSR;Spent nuclear fuel element;Molten salt infiltrate;Criticality calculation;Criticality safety analysis
摘要:Background: Due to an inverse factor to D-T fusion reaction, protium (H) content in D-T fuels is restricted for fuel quality control during Inertial Confinement Fusion (ICF) D-T cryogenic target fabrication. Purpose: This study aims to separate protium from a deuterium-tritium mixture in order to control protium content in DT fuels which is an important issue to support ICF related research work. Methods: A 2-m Palladium/kiesulghur (Pd/k) packed column with outer diameter of 6.4 mm is applied to filter protium, and a micro Thermal Cycling Absorption Process (TCAP) separation system is designed for protium enrichment in the column. When the feed gas (10% of total absorption amount) was input from the top end, the protium was accumulated and enriched in the column, resulting in the product gas from the bottom end purified after one heating-cooling cycle which is powered by a temperature control system-huber Unistat 912w. Results: After 33 automatic enrichment cycles in one testing batch, protium concentration in the column rised from 12% to 52% whilst the protium content in the product gas reduced to 3% compared with 12% protium content in the feed gas. The recycle rate of D-T by this batch was 82.5%. Conclusion: Protirm gets effective enriched in Pd/k filled column, and D-T mixture purification is effective by this enrichment system.
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