摘要:Background: Alignment is carried out in BEPCII storage ring every year by using laser tracker, and planimetric adjustment and vertical adjustment are respectively conducted on the measurement data. Purpose: The aim is to figure out the position error of control network in BEPCII storage ring. Methods: The mean square error of the survey points in BEPCII storage ring of every other year from 2006 to 2012 is calculated and analyzed by the method of alignment and data processing of the survey points, which is introduced in this paper. Results: The geometric mean of absolute mean square error is less than 0.10 mm in the radial and tangential direction, and less than 0.25 mm in the elevation direction, while the geometric mean of relative mean square error is less than 0.06 mm. Conclusion: The geometric mean of slope distance error, horizontal angle error and vertical angle error which calculated from the measurement data can be used as the prior error in data adjustment, and the actual position accuracy of the control network in BEPCII storage ring is higher than the design value, and it can be a reference for the control network design and measurement of other accelerator devices.
Abstract
摘要:Background: The effect of irradiation degradation of polytetrafluoroethylene (PTFE) was studied in recent years. Most of irradiation source is 60Co. Purpose: The effect of electron beam irradiation on the degradation of PTFE in different atmosphere and dose rate was investigated in this study. Methods: The irradiated PTFE samples were analyzed by Fourier transform infrared spectroscopy (FTIR), electron spin resonance (ESR) and X-ray diffraction (XRD). Results: It is found that the PTFE samples were degraded by electron beam effectively. Conclusion: The radiation decomposition of the sample is mainly the rupture of C-C bond. The samples irradiated in low dose rate are better effective than the samples in high dose rate in the same absorbed dose and gas atmosphere, and the samples’ degradation in air is superior to the samples in N2 when they are in the same absorbed dose and radiation dose rate.
Abstract
摘要:Background: Flash memory is a critical part of electrical system on satellite, its characteristics of antiradiation is of great significance for system design. Purpose and Methods: we need to investigate the ionizing irradiation damage and sensitive parameters through testing date logic state, power current, output voltage level, leakage current and Alternating Current parameters. Results: Date logic state appears some errors along with increasing of total radiation dose. Also power current on reading, erasing and holding status increase as radiation dose rising. The failure level on dynamic bias is one-order-magnitude higher than that on static and no power biases. Logic state and power current are sensitive parameters through the experiment results. Conclusion: Results analysis and discussion on the radiation damage phenomenon would provide a theoretical basis and method on comprehensive radiation evaluation of flash memories.
Abstract
摘要:Background: The total dose effect studies for the Silicon-Oxide-Nitride-Oxide-Silicon (SONOS) have not been mainly focused on fail mechanism in circuit. Purpose: A commercial SONOS-based Nitride-Read-Only- Memory (NROM) was irradiated by 60Co γ rays and annealed, Total Ionizing Dose (TID) failure mechanism and annealing characteristics of the device were analyzed. Methods: DC, AC and function parameters of this memory were tested in radiation and annealing by VLSI test system, the radiation-sensitive parameters were obtained through analyzing the test data, and the reason for function failure was analyzed. Results: The study showed that: the threshold of MOS in charge pump and the sense amplifier were drift because of the interface trap charge, and the circuit module performance deterioration led to functional failure of the device. The current parameters were raised rapidly because leakage paths formed in Shallow Trench Isolation (STI). Conclusion: A little of interface trap charge was annealed during annealing, resulting in incomplete recovery of circuit module performance, and insignificant drop of the current parameters.Cited
摘要:Background: Nuclear disaster rescue robots are of earnest desire for on-site rescue and post processing. The electronic devices of robots are quite sensible to operation condition, which could be suddenly destroyed by the γ-ray. Shielding is one of the effective methods that can enhance the anti-radiation properties of the protected content. Purpose: This paper sets up three types of combination models, W-Ni, Ni-W and their alloys, aiming at the protection effect towards γ-ray. Methods: The transmission and energy spectrum under γ-ray were simulated on the models with various thicknesses, W:Ni volume ratios and layer numbers based on Monte Carlo method. Results and Conclusion: Ni-W and alloys showed better shielding performance than the W-Ni, especially at short wave range (0?0.6 MeV). The increase of W amount weakened the difference among the three models. Less variation was found with layer numbers and the unidirectional disc source or point one.
Abstract
摘要:Background: Amorphous alloy has special application prospects in nuclear reactors and electromagnetic fields because of its excellent shielding properties. Purpose: This paper attempts to study the effects of minor addition Sm on the microstructure, glass-forming ability and thermal stability of the Cu-based Cu50Zr45Al5 bulk metallic glass (BMG) and the ?-ray shielding properties of the Cu-Zr-Al-Sm amorphous alloys. Methods: (Cu50Zr45Al5)100?xSmx (x?0, 1, 2, 3 and 4) alloys plates are prepared by copper mold suction casting. The microstructure, thermal stability and the ?-ray shielding properties of the prepared samples are carried out by X-ray diffraction (XRD), differential scanning calorimeters (DSC), differential thermal analysis (DTA) and NaI(T1) scintillation gamma spectrometer. Results: The experimental results show that the Cu10Zr7 and ZrCu phases are precipitated when Sm addition exceeds 3%(at%), otherwise the alloys are fully amorphous state. Minor addition Sm improved the thermal stability of the base alloy. The linear absorption coefficient of (Cu50Zr45Al5)99Sm1 amorphous alloys against 137Cs and 60Co ?-ray are 0.49cm?1 and 0.69cm?1, respectively. Conclusion: The shielding property of (Cu50Zr45Al5)99Sm1 BMG is between Pb and Al, and has potential application value.
Abstract
摘要:Background: Radon protection is particularly important in underground uranium mining, and the migration regularity of radon and radon ventilation reliability are the base to solve the problem. Therefore, it is of practical significance to study the reliability of ventilation of uranium and radon migration. Purpose: The aim is to explore the radon diffusion regularity of seepage in porous media with system reliability and mechanism of radon exhalation. Methods: The exhalation and distribution of radon in the tunnel under the steady state and unsteady state were analyzed and the numerical simulation of the tunnel for radon migration was developed using MATLAB PDE toolbox. Results: Radon concentration within the tunnel increased with the length of flowing under both unstable and stable conditions with a period of time of ventilation. Calculation of reliability of tunnel based on the mechanism of radon exhalation reflected the exhalation and distribution of radon concentration of tunnel well. Conclusion: The results show that the understanding of the law on the radon exhalation provides reference for radon-prevention in underground space and ventilation and safe operation of uranium mine.Cited
摘要:Background: In recent years, a new amyloid-?-peptide (A?) protein imaging agent 18F-AV-45 which can be used to diagnose Alzheimer’s disease (AD), was developed. Whereas single-photon emission computed tomography (SPECT) was widely applied in medical clinic in China, a two function compound BAT was connected to the end of AV-45 to successfully synthesize a new compound BAT-AV-45, and its chemical kinetics of labeling reaction with 99mTc was studied. Purpose: 99mTc-BAT-AV-45 was synthesized via direct reaction and ligand exchange for obtaining high labeling yield. Methods: The labeling reactions were performed with three modes: (1) adding BAT-AV-45, GH and 99mTc; (2) adding BAT-AV-45 and 99mTc but non GH; (3) adding GH and 99mTc but non BAT-AV-45. Reactants were incubated at 4°C, 25°C and 100°C, respectively. Samples were taken with capillary from vials at 2 min, 5 min, 10 min, 20 min and 30 min, respectively. Labeling yields were determined by thin layer chromatography (TLC). Order of reaction n, rate constant k, average activation energy Ea and reaction half life t1/2 of labeling reaction were calculated with chemical kinetics software compiled by ourselves. Results: The results expressed that the labeling yields of 99mTc-BAT-AV-45 with direct reaction and ligand exchange were proportional to reaction temperature and reaction time. The highest labeling yields with direct reaction and ligand exchange were 3.45%±0.05% and 93.81%±0.91%, respectively. The parameters of chemical kinetics were calculated. n was 1. k were 2.00×10?4 min?1, 3.00×10?4 min?1, 1.40×10?3 min?1 with direct reaction and 0.108 min?1, 0.115 min?1, 0.265 min?1 with ligand exchange at 4°C, 25°C and 100°C, respectively. Ea were 17.11 kJ?mol?1 with direct reaction and 6.84 kJ?mol?1 with ligand exchange, respectively. t1/2 were 3 890.60 min, 2779.51 min, 481.39 min with direct reaction and 6.43 min, 6.00 min, 2.62 min with ligand exchange at 4 °C, 25 °C and 100°C, respectively. Conclusion: The results indicated that the high labeling yield of 99mTc-BAT-AV-45 could be obtained by using ligand exchange to reduce activation energy Ea of labeling reaction so as to accelerate the reaction.
Abstract
摘要:Background: Neutron flux density is an important parameter related to nuclear power of the reactor. Digitized processing of neutron flux density in a wide measurement range of fission chamber detector has more advantages than the traditional analog circuits. Purpose: The aim is to improve the accuracy of neutron counting in the pulse mode, as well as mean square value calculation in the Campbell mode. Methods: The waveform of the output signal of fission chamber with various electronic noise was simulated, and then a trapezoidal shape filtering and digital adaptive filtering were employed to deal with digitized waveform signal of fission chamber in both low neutron flux density (pulse mode) and high neutron flux density (Campbell mode) circumstances. Results: By using these two methods, the accuracy of both the pulse counting and mean square value calculation was improved. Conclusion: Trapezoidal shape filtering and digital adaptive filtering can be applied to process digitized fission chamber output signal to achieve precise measurement of the neutron flux density in a wide range.
Abstract
摘要:Background: In neutron radiation protection applications, the spectrometric neutron dosimeter has almost isotropic response and can cover the energy from thermal to GeV neutrons, and the radiation filed information such as neutron spectrum and neutron dose can be calculated more accurately. Purpose: A spectrometric neutron dosimeter which has high precision and high counting rate is developed. Methods: By optimizing the parameters of the readout circuit, the position resolution of the detector system is improved and the geometric division of the spherical moderate is more accurate. Using digital pulse processing technology, the dead-time of the system is reduced. Results: The position resolution of the neutron dosimeter has good linearity, and the average resolution is about 6 mm. The high counting rate of the data acquisition system is 200 k?s?1. Conclusion: We developed a neutron dosimeter based on neutron sphere spectrometer which has high position resolution and high counting rate. The performance of the dosimeter is expected to be improved for further optimization design after the test in the radiation field.
Abstract
摘要:Background: Heavy ion therapy accelerator is introduced to reconstruct a dedicated synchrotron for medical treatment based on HIRFL-CSR (Heavy Ion Research Facility in Lanzhou-Cooling Storage Ring). Synchronous transmission of HIRFL-CSR uses the 400 kHz baseband signal with optical fiber. Purpose: The bandwidth and reliability of heavy ion therapy accelerator need to be improved for practical application. Methods: Differential phase shift keying (DPSK) modulation and demodulation method has been adopted, combined with the parity check, BCH codec, scrambling and frame synchronization system, to improve the reliability of system. Further improvement on both hardware and software implementation is taken to avoid any error in transmission process. Results: Experimental results show that the error times reduced to zero by using two boards to send and receive data. It is proved that the system can transmit data correctly and effectively. Conclusion: The system can accurately finish the data transmission with high reliability for the high-speed data transmission system of the heavy ion therapy accelerator. It has been directly applied to the scene of the heavy ion therapy accelerator.
Abstract
关键词:Heavy ion therapy accelerator;Data transmission;DPSK (Differential Phase Shift Keying) modulation and demodulation;Phase change point;FPGA
摘要:Background: By use of backscattering neutrons from human body, Albedo neutron dosimeters can improve the response, which is normally dependent on the type of the neutron field, such as the energy spectrum of neutrons and the scattering. Therefore, calibrations need to be carried out to determine the relation between the reading of dosimeters and the dose value. Purpose: Experiment based calibration of albedo dosimeters is complicated and time consuming. Monte Carlo method can be applied to make the calibration in order to lower the cost and time. Methods: Monte Carlo code was used to make the calculation for the response of dosimeters in different neutron fields. In comparison with the response in a reference neutron filed, a relative calibration factor in a measured neutron field can be calculated. Results: The calibration was performed for an Alnor albedo dosimeter in the neutron fields of interim storage facilities both in Germany and in China, and the relative calibration factors to a reference neutron field were calculated. The relative response ranges from 10 to 20, and the reading ratio of field neutron to albedo neutron is about 2 to 3. Conclusion: Based on the results, calibration factor for reactors and linacs can be applied for Alnor albedo dosimeter in the neutron fields of interim storage facilities.
Abstract
关键词:Neutron filed;Thermoluminescence Detector (TLD);Albedo;Alnor;Calibration;Monte Carlo
摘要:Background: Hariza polymetallic ore district is located in eastern section of East Kunlun Mountains, Qinghai Province and belongs to multicycle magmatic arc belt in Middle of East Kunlun. A total of seven large scale mineralizing zones have been discriminated and mainly fall into tectonic alterated rock type. The IV metallogenic zone is composed of two branches, NE- and NW-trending, of zones. The mineralization was close related to magmatic activities and was controlled by both NE- and NW- trending fault zones. Purpose: This paper applies the zircon fission track nuclear technique to probe the mineralizing ages and epochs for IV metallogenic zone in Hariza polymetallic ore district. Methods: The conservation temperature of zircon fission track is about 250 oC that coincides with the metallogenic temperature in this district and so the zircon fission track dating technique could reveal the mineralization age and epoch. Results: The six zircon fission track results are achieved, ranging from 120 Ma to 204Ma, which could be divided into three groups of 204 Ma, 153?168 Ma and 120 Ma. Conclusion: The three groups of ages reveal three periods of mineralization that correspond with three tectonic activities. The mineralizing time in the SE-trending branch belt was earlier than that in the SW-trending branch.
Abstract
摘要:Background: The advanced high-temperature reactor (AHTR) is conceptional designed by Oka Ridge National Laboratory (ORNL) for a central generating station type of 3400 MWt fluoride-salt-cooled high-temperature reactor (FHR). The design employs an innovative plate-type coated particle fuel assembly with uranium enrichment of 9%?20%. The initial core excess reactivity is too large to be handled by the control blades alone. Purpose: This study aims to eliminate the problem of high excess reactivity by analyzing the use of spherical burnable particles. Methods: First of all, according to the physical properties and burn-up chain of burnable poison (BP) materials, six potential candidates were analyzed, and four of them, i.e. B4C, Gd2O3, CdO and Er2O3 were chosen for further study. Then, the MCNP and Origen2 coupling program were employed to optimize the BP loading using single fuel assembly calculations. Finally, the keff, which changes with burn-up time, was used as optimization parameter to attain the optimal radius and mass. Results: Simulation results showed that the reactivity swing reduced from 39% to about 4.4%, 6.8%, 7.3% and 13.1% respectively, when loading 176 g Er2O3 with a radius of 740 μm, 3 g B4C with a radius of 100 μm, 120 g Gd2O3 with a radius of 1 500 μm and 160 g CdO with a radius of 2 000 μm separately. Conclusion: Er2O3 is recommended as the best BP material to eliminate the problem of high excess reactivity in plate-fuel type AHTR.
Abstract
关键词:Advanced high temperature reactor (AHTR);Plate-type fuel element;Burnable poison (BP)
摘要:Background: Vortex diode is a kind of uniflow component, and a simple vortex diode contains a vortex chamber, a tangential nozzle and an axial nozzle. Purpose: The aim is to investigate the effect of chamfered vortex chamber structure on vortex diode performance. Methods: Computational Fluid Dynamics (CFD) simulations were used on vortex diodes with four different chamfered structures. Standard k-ε model was selected for forward flow, while RNG (Renormalization Group) k-ε model was selected for reverse flow. Results: The results show that compared with standard structure, all the other three chamfered structures can reduce the positive flow resistances at relatively high Reynolds number, while the reverse flow resistances are also reduced. Among them, the chamfered structure of 3/4 vortex chamber height, can reduce the forward flow resistance to the greatest extent while keeping minimum impact on the reverse flow resistance. Conclusion: The chamfered structure of 3/4 vortex chamber height improves the overall performance of a vortex diode most significantly. The results of the simulation can provide some basis for optimizing the vortex diode performance.
Abstract
摘要:Background: One advantage of liquid fluoride thorium reactor is that it can separate almost all of fission products including its own transuranic products due to the on-line removing. The removing process can be defined as bubble generation-mass transfer-gas separation. Purpose: A gas-liquid separator is a core component in the removing system. In this paper, a kind of gas-liquid separator adopted to remove the fission gases for Thorium Molten Salt Reactor (TMSR) is studied. The air core formation, which is heavily depending on the back pressure, plays a significant role for separation efficiency. Methods: To illustrate the effect of back pressure on the evolution process of the air core, the air core behavior variation with the back pressure under different swirling numbers (S) and Reynolds numbers (Re) were recorded by visualization technique. Results: The flow pattern indicates that the air core evolution can be defined as four stages with respective characteristics. However, the air core can shape under different swirling numbers and Reynolds numbers differ a lot. Conclusion: It is proven that there is a critical back pressure which contributes an economic and high efficient separation. Thus, the critical back pressures were summarized for all the swirling numbers and Reynolds numbers involved, which can provide a guideline for the application of the separator.
Abstract
摘要:Background: Beam interruption and beam overpower are two typical transient accidents for accelerator-driven system. Purpose: To investigate the safety characteristics of the lead-bismuth cooled Accelerator Driven Sub-critical System (ADS) under beam transient accident, the steady state, beam trip and beam overpower accident of lead-bismuth cooled accelerator-driven system were simulated by using NTC-2D. Methods: NTC-2D is a two-dimensional version of neutronics and thermo-hydraulics coupled simulation program NTC developed by FDS team. Results: As for the beam interruptions, the temperature variations of cladding and fuel pellet at different time (1s, 3s, 6s, 12s) were given. The longer the beam interruptions, the lower temperature of cladding and fuel. After beam overpower occurred, core power finally stabilized at 192.2% of the initial power value. The temperatures of the fuel, cladding and coolant were all smaller than the safety limits. The fuel and cladding would not melt and the coolant would not boil. Conclusion: The reactor was safe under two accidents. The transient response of the power for ADS under beam transient accidents is instantaneous. Delayed neutron has less effect on neutron generation time. Natural circulation can reach new steady under two accidents.
Abstract
关键词:Accelerator Driven Sub-critical System (ADS);Beam trip;Beam overpower;Neutronics and thermal-hydraulics coupled