The effects of initial spin orientation on the final electron beam polarization in laser wakefield acceleration in a pre-polarized plasma are investigated theoretically and numerically.From the results of variation of...The effects of initial spin orientation on the final electron beam polarization in laser wakefield acceleration in a pre-polarized plasma are investigated theoretically and numerically.From the results of variation of the initial spin direction,the spin dynamics of the electron beam are found to depend on the self-injection mechanism.The effects of wakefields and laser fields are studied using test particle dynamics and particle-in-cell simulations based on the Thomas-Bargmann-Michel-Telegdi equation.Compared with transverse injection,longitudinal injection is found to be preferable for obtaining a highly polarized electron beam.展开更多
With the advantages of high reliability, power density, and long life, nuclear power reactors have become a promising option for space power. In this study, the Reactor Excursion and Leak Analysis Program 5(RELAP5), w...With the advantages of high reliability, power density, and long life, nuclear power reactors have become a promising option for space power. In this study, the Reactor Excursion and Leak Analysis Program 5(RELAP5), with the implementation of sodium–potassium eutectic alloy(NaK-78) properties and heat transfer correlations, is adopted to analyze the thermal–hydraulic characteristics of the space nuclear reactor TOPAZ-Ⅱ.A RELAP5 model including thermionic fuel elements(TFEs), reactor core, radiator, coolant loop, and volume accumulator is established. The temperature reactivity feedback effects of the fuel, TFE emitter, TFE collector,moderator, and reactivity insertion effects of the control drums and safety drums are considered. To benchmark the integrated TOPAZ-Ⅱ system model, an electrical ground test of the fully integrated TOPAZ-Ⅱ system, the V-71 unit,is simulated and analyzed. The calculated coolant temperature and system pressure are in acceptable agreement with the experimental data for the maximum relative errors of 8 and 10%, respectively. The detailed thermal–hydraulic characteristics of TOPAZ-Ⅱ are then simulated and analyzed at the steady state. The calculation results agree well with the design values. The current work provides a solid foundation for space reactor design and transient analysis in the future.展开更多
Uranium hexafluoride(UF6)leakage accidents represent one of the most serious classes of accidents in the gasification process in nuclear fuel manufacturing facilities.Common UF6 leakage accidents include various fault...Uranium hexafluoride(UF6)leakage accidents represent one of the most serious classes of accidents in the gasification process in nuclear fuel manufacturing facilities.Common UF6 leakage accidents include various fault conditions,such as pipeline and valve breakages or ruptures and pipeline blockages.By establishing goal-oriented(GO)operators that can represent multi-fault states,this study estimates the probabilities of various fault states corresponding to UF6 leakage accidents in the gasification process using the GO methodology and analyzes the system reliability.This article expands the scope of the GO methodology and provides technical support for reliability analysis using the GO methodology in multi-fault systems.展开更多
The components from spent fuel are discharged from the core and then stored in the framework of the spent fuel pool for cooling. However, it is of great significance to save the storage space of the spent fuel pool by...The components from spent fuel are discharged from the core and then stored in the framework of the spent fuel pool for cooling. However, it is of great significance to save the storage space of the spent fuel pool by shrinkage and shearing work to increase the spare fuel lattice number. In order to solve the problem of shrinkage and shearing work of spent fuel involving the problem of radioactive safety, the radioactive source item is calculated by ORIGEN2 program base on Unit 1 Ⅱ of Lingao Nuclear Power Plant(NPP), and the radiation dose rate of the related component shrinkage operation scene is simulated by the MCNP5 program. In addition, the effectiveness of shielding measures is discussed, and the maximum dose rate is within 0.35 μSv/h at the distance of 2.5 m from component center, and the maximum dose rate is almost 0 at the distance of 3.2 m from the component center. The intensity of the radiation dose produced by the related components is very low and can be neglected, which belong to the green area of NPP. The program calculation system from source term calculation to shielding calculation is established, and an engineering example is referenced, and its application and analysis are carried out. It provides a basis for radioactive safety analysis and evaluation for the shrinkage operation of spent fuel and makes the shrinkage technology of fuel-related components safer and more reliable.展开更多
The fast growth in the size and difficulty of nuclear power plant in the 1970s produced an interest in smaller, modest designs that are intrinsically safe over the usage of design features. With the development of nuc...The fast growth in the size and difficulty of nuclear power plant in the 1970s produced an interest in smaller, modest designs that are intrinsically safe over the usage of design features. With the development of nuclear technology, there is the need for revolution in the Maritime sector, especially the advance marine propulsion. In current years, numerous reactor manufacturers are dynamically improving small modular reactor designs with even superior use of safety features. Several designs integrate the ultimate in greater safety. They totally remove specific accident initiators from the design. Other design features benefit to reduce different types of accident or help to mitigate the accident’s consequences. Although some safety features are mutual to maximum SMR designs, irrespective of the coolant technology, other features are specific to liquid-metal cooled, water, gas, or SMR designs. Results: There have been more reactor concepts investigated in the marine propulsion area by different assemblies and research laboratories than in the power generation field, and much can be learned from their experience for land applications. The extensive use of safety features in SMRs potential to make these power plants extremely vigorous, protecting both the public and the investor. Conclusion: For these two considerations, it is recognized that a nuclear reactor is the ideal engine for naval advanced propulsion. The paper will present the work to analyze the concept design of SMRs and design a modular vessel consisting of a propulsion module.展开更多
A nuclear battery consisting of a beta source,a phosphor layer and a photovoltaic device was prepared.Planar phosphor layers were synthesized through physical precipitation of ZnS:Cu,ZnS:Ag or SrAl_2O_4:Eu^(2+),Dy^(3+...A nuclear battery consisting of a beta source,a phosphor layer and a photovoltaic device was prepared.Planar phosphor layers were synthesized through physical precipitation of ZnS:Cu,ZnS:Ag or SrAl_2O_4:Eu^(2+),Dy^(3+)phosphors.The radioluminescence(RL)spectra were used to analyze the RL effects of the phosphor layers under beta-particle excitation.Feasibility of using the materials as intermediate absorbers in the beta batteries was studied.TheⅠ-Ⅴcharacteristics of beta RL nuclear batteries with different phosphor layers were tested using^(63)Ni or^(l47)Pm beta sources.The output power of zinc sulfide matrix phosphor layer was better than that of rare-earth element oxides.In addition,a thin aluminum reflective layer was vacuum-evaporated on the phosphor layers to improve the efficiency of beta RL nuclear batteries,and the results were discussed.展开更多
With many advantages, hydrogen is considered as the fuel of the future. But there is no natural resourceof hydrogen and it must be produced by other kinds of energy. As for the primary energy, nuclear energy is a prom...With many advantages, hydrogen is considered as the fuel of the future. But there is no natural resourceof hydrogen and it must be produced by other kinds of energy. As for the primary energy, nuclear energy is a promis-ingalternative. Using heat from nuclear reactor to produce hydrogen is receiving more and more concerns in recentyears. This paper mainly emphasizes the study of the direct contact pyrolysis (DCP) of methane using heat from nu-clearreactor. A facility was designed to investigate the efficiency of DCP process in certain conditions. The experi-mentalresults show that this process produces only hydrogen and carbon. The conversion efficiency increases withtemperature and residence time, but decreases as flow rate increases. The highest efficiency of DCP obtained in thisexperiment is about 22%.展开更多
The single-particle potentials in isospin asymmetric nuclear matter is investigated in the framework of the Brueck-ner theory by adopting the realistic Bonn B two-body interaction in combination with a consistent micr...The single-particle potentials in isospin asymmetric nuclear matter is investigated in the framework of the Brueck-ner theory by adopting the realistic Bonn B two-body interaction in combination with a consistent microscopic three-body force.The rearrangement contribution induced by the ground state correlations to single-nucleon potentials is calculated in terms of the hole-line expansion of the mass operator.With the modification of this rearrangement term the symmetry potential is discussed as a function of momentum for several isospin asymme.展开更多
With the complementarity of the nucleonic three-body force,we present the saturation points of symmetric nuclear matter with different interactions adopted within the Brueckner-Hartree-Fock scheme,and a more accurate ...With the complementarity of the nucleonic three-body force,we present the saturation points of symmetric nuclear matter with different interactions adopted within the Brueckner-Hartree-Fock scheme,and a more accurate empirical parameterization function for the equation of state of symmetric nuclear matter and pure neutron matter.On the basis of this fit formula,the symmetry energy and its derivatives are investigated,and ultimately the higher-order coefficient of the isobaric incompressibility for isospin asymmetric nuclear matter is predicted.展开更多
Colloidal dispersions of nanoparticles are known as ＇nanofluids＇. Such engineered fluids offer the potential for enhancing heat transfer, particularly boiling heat transfer, while avoiding the drawbacks （e.g., eros...Colloidal dispersions of nanoparticles are known as ＇nanofluids＇. Such engineered fluids offer the potential for enhancing heat transfer, particularly boiling heat transfer, while avoiding the drawbacks （e.g., erosion, settling, clogging） that hindered the use of particle-laden fluids in the past. At Massachusetts Institute of Technology （MIT）, the authors have been studying the heat transfer characteristics of nanofluids for the past five years, with the goal of evaluating their benefits for and applicability to nuclear power systems （e.g., primary coolant, safety systems, severe accident mitigation strategies）. This paper summarizes the MIT research in this area with particular emphasis to boiling behavior, including, prominently, the Critical Heat Flux limit and quenching phenomena.展开更多
Small modular reactors have received widespread attention owing to their inherent safety,low investment,and flexibility.Small pressurized water reactors(SPWRs)have become important candidates for SMRs owing to their h...Small modular reactors have received widespread attention owing to their inherent safety,low investment,and flexibility.Small pressurized water reactors(SPWRs)have become important candidates for SMRs owing to their high technological maturity.Since the Fukushima accident,research on accident-tolerant fuels(ATFs),which are more resistant to serious accidents than conventional fuels,has gradually increased.This study analyzes the neutronics and thermal hydraulics of an SPWR(ACPR50S)for different ATFs,BeO+UO_(2)−SiC,BeO+UO_(2)−FeCrAl,U_(3)Si_(2)−SiC,and U_(3)Si_(2)−FeCrAl,based on a PWR fuel management code,the Bamboo-C deterministic code.In the steady state,the burnup calculations,reactivity coefficients,power and temperature distributions,and control rod reactivity worth were studied.The transients of the control rod ejection accident for the two control rods with the maximum and minimum reactivity worth were analyzed.The results showed that 5%B-10 enrichment in the wet annular burnable absorbers assembly can effectively reduce the initial reactivity and end-of-life reactivity penalty.The BeO+UO2−SiC core exhibited superior neutronic characteristics in terms of burnup and negative temperature reactivity compared with the other three cases owing to the strong moderation ability of BeO+UO_(2)and low neutron absorption of SiC.However,the U_(3)Si_(2)core had a marginally better power-flattening effect than BeO+UO_(2),and the differential worth of each control rod group was similar between different ATFs.During the transient of a control rod ejection,the changes in the fuel temperature,coolant temperature,and coolant density were similar.The maximum difference was less than 10℃ for the fuel temperature and 2℃ for the coolant temperature.展开更多
In the direct drive inertial confinement fusion(ICF)scheme,a rippled interface between the ablator and the deuterium–tritium ice fuel can feed out and form perturbation seeds for the ablative Rayleigh–Taylor instabi...In the direct drive inertial confinement fusion(ICF)scheme,a rippled interface between the ablator and the deuterium–tritium ice fuel can feed out and form perturbation seeds for the ablative Rayleigh–Taylor instability,with undesirable effects.However,the evolution of this instability remains insufficiently studied,and the effects of high-Z dopant on this instability remain unclear.In this paper,we develop a theoretical model to calculate the feedout seeds and describe this instability.Our theory suggests that the feedout seeds are determined by the ablation pressure and the adiabatic index,while the subsequent growth depends mainly on the ablation velocity.Two-dimensional radiation hydrodynamic simulations confirm our theory.It is shown that targets with high-Z dopant in the outer ablator exhibit more severe feedout seeds,because of their higher ionization compared with undoped targets.The X-ray pre-ablation in high-Z doped targets significantly suppresses subsequent growth,leading to suppression of short-wavelength perturbations.However,for long-wavelength perturbations,this suppression is weakened,resulting in increased instability in high-Z doped targets.The results are helpful for understanding the innerinterface-initiated instability and the influence of high-Z dopant on it,providing valuable insights for target design and instability control in ICF.展开更多
Accurate atomic mass data hold significant application value in various research fields,in which Penning trap mass spectrometry is considered the most precise experimental method.A cryogenic detection system is a key ...Accurate atomic mass data hold significant application value in various research fields,in which Penning trap mass spectrometry is considered the most precise experimental method.A cryogenic detection system is a key component for reading out the image charge of charged particles in Penning traps using the Fourier transform ion cyclotron resonance technique.In this paper,we present the development and characteristics of this detection system,which includes a superconducting resonator and cryogenic low-noise amplifiers.The resonator consists of delicately woven thin NbTi wires configured into a multilayer helical coil,offering a quality factor of 98004 at around 1 MHz.Low-noise amplifiers are developed based on GaAs field effect transistors,exhibiting amplification factors greater than 27 dB with a power consumption of approximately 6 mW in the frequency range of 0.1 to 10 MHz.The lowest input voltage noise is 0.8√Hz at 1 MHz.The fabrication process,operation,and measurements are elucidated in detail.展开更多
In this work,tensile mechanical behavior of 316L steels fabricated by three different processing methods(casting,powder extrusion printing(PEP)and laser powder bed fusion(LPBF))was studied in the presence of liquid le...In this work,tensile mechanical behavior of 316L steels fabricated by three different processing methods(casting,powder extrusion printing(PEP)and laser powder bed fusion(LPBF))was studied in the presence of liquid lead-bismuth eutectic(LBE)and air at 350℃.The results show that all three steels tested in LBE are not subjected to evident degradation of tensile elongation to failure and strength compared to those tested in air,suggesting that LME does not occur regardless of the processing methods.The LPBF 316L steel exhibits the highest yield strength(420-435 MPa),followed by casting 316 L(~242 MPa)and PEP 316L(146-165 MPa).Ultimate tensile strength of three steels is comparable and ranges from 427 to 485 MPa.The PEP and casting 316L steels have similar total elongation to failure(i.e.,40.0%-43.8%),whereas this property decreases markedly to 18.6%-19.5% for the LPBF 316 L steel.The superior strength and relatively low ductility of the LPBF 316L steel can be attributed to nanosized dislocations trapped at cell structures which can produce a remarkable strengthening effect to the steel matrix.By contrast,due to massive residual micropores,the PEP 316L steel has the lowest strength.展开更多
The challenge of sintering ultrafine-grained refractory metals and alloys to full density is hereby addressed by pressureless two-step sintering in tungsten-rhenium alloy and pure molybdenum. Using properly processed ...The challenge of sintering ultrafine-grained refractory metals and alloys to full density is hereby addressed by pressureless two-step sintering in tungsten-rhenium alloy and pure molybdenum. Using properly processed nano powders(~50 nm average particle size), we are able to sinter W-10Re alloy to 98.4% density below 1200 ℃ while maintaining a fine grain size of 260 nm, and sinter molybdenum to 98.3% density below 1120 ℃ while maintaining a fine grain size of 290 nm. Compared to normal sintering,two-step sintering offers record-fine grain sizes and better microstructural uniformity, which translates to better mechanical properties with higher hardness(6.3 GPa for tungsten-rhenium and 4.0 GPa for molybdenum, both being the highest in all pressurelessly sintered samples of the respective material system)and larger Weibull modulus. Together with our previous demonstration in tungsten, we believe that twostep sintering is a general effective method to produce high-quality fine-grained refractory metals and alloys, and the lessons learned here are transferable to other materials for powder metallurgy.展开更多
To better understand the multiphase fluid dynamics and associated transport processes of cavitating flows at the capillary number of 0.74 and 0.54, and to validate the numerical results, a combined computational and e...To better understand the multiphase fluid dynamics and associated transport processes of cavitating flows at the capillary number of 0.74 and 0.54, and to validate the numerical results, a combined computational and experimental investigation of flows around a hydrofoil is studied based on flow visualizations and time-resolved interface movement. The computational model is based on a modified RNG k-ε model as turbulence closure, along with a vapor-liquid mass transfer model for treating the cavitation process. Overall, favorable agreement between the numerical and experimental results is observed. It is shown that the cavi- tation structure depends on the interaction of the water-vapor mixture and the vapor among the whole cavitation stage, the interface between the vapor and the two-phase mixture exhibits substantial unsteadiness. And, the adverse motion of the interface relates to pressure and velocity fluctuations inside the cavity. In particular, the velocity in the vapor region is lower than that in the two-phase region.展开更多
A method based on the cross-sectional relationship between^(10)B(n,α)^(7)Li and^(1)H(n,γ)^(2)H was proposed to detect and reconstruct the three-dimensional boron concentration/dose distribution in vivo during boron ...A method based on the cross-sectional relationship between^(10)B(n,α)^(7)Li and^(1)H(n,γ)^(2)H was proposed to detect and reconstruct the three-dimensional boron concentration/dose distribution in vivo during boron neutron capture therapy(BNCT).Factors such as the neutron energy,fluence rate,and degree of non-uniform distribution of the boron concentration in a voxel may affect the results of this method.A theoretical analysis of the accuracy of the method using a Monte Carlo simulation shows that the determining error is generally less than 1%under different tumor locations and neutron source configurations.When the voxel size is larger than 0.4 cm,the determining error might be higher for a non-uniformly distributed boron concentration in the voxel because of the changes in the neutron energy and fluence rate.In conclusion,the proposed method enables an accurate threedimensional boron determination in vivo during BNCT.展开更多
The limited availability of studies on the natural convection heat transfer characteristics of fluoride salt has hindered progress in the design of passive residual heat removal systems(PRHRS)for molten salt reactors....The limited availability of studies on the natural convection heat transfer characteristics of fluoride salt has hindered progress in the design of passive residual heat removal systems(PRHRS)for molten salt reactors.This paper presents results from a numerical investigation of natural convection heat transfer characteristics of fluoride salt and heat pipes in the drain tank of a PRHRS.Simulation results are compared with experimental data,demonstrating the accuracy of the calculation methodology.Temperature distribution of fluoride salt and heat transfer characteristics are obtained and analyzed.The radial temperature of liquid fluoride salt in the drain tank shows a uniform distribution,while temperatures increase with increase in axial height from the bottom to the top of the drain tank.In addition,natural convection intensity increases with increase in height of the heat pipes in the tank.Spacing between heat pipes has no obvious effect on the natural convection heat transfer coefficient.This study will contribute to the design of passive heat removal systems for advanced nuclear reactors.展开更多
This study evaluated the nuclear data libraries for a small 100 Mega Watt electric(MWe)Molten Salt Reactor with plutonium fuel.The reactor has a power output of 100 MWe,which meets the demand for electricity generatio...This study evaluated the nuclear data libraries for a small 100 Mega Watt electric(MWe)Molten Salt Reactor with plutonium fuel.The reactor has a power output of 100 MWe,which meets the demand for electricity generation in several regions or provinces outside Java Island.Several nuclear data libraries,such as JEFF 3.1,ENDF/B-VII.0,JENDL 3.3,and JENDL 4.0,were used for a more comprehensive evaluation.LiF–BeF_(2)–ThF_(4)–PuF_(4) was used as the initial fuel composition.The thorium and plutonium concentrations in the fuel salt were varied to obtain the optimum fuel composition,leading to critical conditions.The results showed some neutronic parameters,such as the conversion ratio,neutron spectra,and effective multiplication factors,from three different nuclear data libraries.By changing the plutonium concentration in the initial fuel salt composition,the minimum plutonium loaded for the reactor criticality during 2000 days of operation time was determined to be 0.995,0.91,0.87,and 0.90 mol%for JEFF 3.1,ENDF/B-VII.0,JENDL 3.3,and JENDL 4.0,respectively.The differences in the values of each parameter were due to several factors,such as the cross-section values and number of nuclides in the nuclear data libraries.Several safety parameters were also investigated to ensure the possibility of utilizing PuF_(4) in the reactor.展开更多
Absorption rate of CO2 into aqueous solution of N-methyldiethanolamine (MDEA) blended with diethanolamine (DEA) and piperazine (PZ) was studied and a kinetic model was established. It is shown that homogeneous activat...Absorption rate of CO2 into aqueous solution of N-methyldiethanolamine (MDEA) blended with diethanolamine (DEA) and piperazine (PZ) was studied and a kinetic model was established. It is shown that homogeneous activation mechanism could explain this absorption process. The absorption rate coefficients of carbon dioxide into MDEA aqueous solution blended with DEA, PZ or DEA+PZ were compared with each other. The results demonstrated that the different activation effect of DEA, PZ and DEA+PZ on the carbon dioxide absorption comes from the difference in CO2 combination rate, transport of PZ and DEA to MDEA and the regeneration rate of PZ and DEA.展开更多
基金supported by the National Natural Science Foundation of China(Grant Nos.11804348,11775056,11975154,12225505,and 12405281)the Science Challenge(Project No.TZ2018005)+2 种基金supported by the Shanghai Pujiang Program(Grant No.23PJ1414600)the Strategic Priority Research Program of the Chinese Academy of Sciences(Grant No.XDB0890203)supported by the Accelerator Technology Helmholtz Infrastructure consortium ATHENA.
文摘The effects of initial spin orientation on the final electron beam polarization in laser wakefield acceleration in a pre-polarized plasma are investigated theoretically and numerically.From the results of variation of the initial spin direction,the spin dynamics of the electron beam are found to depend on the self-injection mechanism.The effects of wakefields and laser fields are studied using test particle dynamics and particle-in-cell simulations based on the Thomas-Bargmann-Michel-Telegdi equation.Compared with transverse injection,longitudinal injection is found to be preferable for obtaining a highly polarized electron beam.
基金supported by the China National Postdoctoral Program for Innovative Talents(No.BX201600124)China Postdoctoral Science Foundation(No.2016M600796)the National Natural Science Foundation of China(No.11605131)
文摘With the advantages of high reliability, power density, and long life, nuclear power reactors have become a promising option for space power. In this study, the Reactor Excursion and Leak Analysis Program 5(RELAP5), with the implementation of sodium–potassium eutectic alloy(NaK-78) properties and heat transfer correlations, is adopted to analyze the thermal–hydraulic characteristics of the space nuclear reactor TOPAZ-Ⅱ.A RELAP5 model including thermionic fuel elements(TFEs), reactor core, radiator, coolant loop, and volume accumulator is established. The temperature reactivity feedback effects of the fuel, TFE emitter, TFE collector,moderator, and reactivity insertion effects of the control drums and safety drums are considered. To benchmark the integrated TOPAZ-Ⅱ system model, an electrical ground test of the fully integrated TOPAZ-Ⅱ system, the V-71 unit,is simulated and analyzed. The calculated coolant temperature and system pressure are in acceptable agreement with the experimental data for the maximum relative errors of 8 and 10%, respectively. The detailed thermal–hydraulic characteristics of TOPAZ-Ⅱ are then simulated and analyzed at the steady state. The calculation results agree well with the design values. The current work provides a solid foundation for space reactor design and transient analysis in the future.
文摘Uranium hexafluoride(UF6)leakage accidents represent one of the most serious classes of accidents in the gasification process in nuclear fuel manufacturing facilities.Common UF6 leakage accidents include various fault conditions,such as pipeline and valve breakages or ruptures and pipeline blockages.By establishing goal-oriented(GO)operators that can represent multi-fault states,this study estimates the probabilities of various fault states corresponding to UF6 leakage accidents in the gasification process using the GO methodology and analyzes the system reliability.This article expands the scope of the GO methodology and provides technical support for reliability analysis using the GO methodology in multi-fault systems.
基金Supported by the Project of Radiation Shielding Calculation Based on Unit 1 Ⅱ of Lingao Nuclear Power Plant of China
文摘The components from spent fuel are discharged from the core and then stored in the framework of the spent fuel pool for cooling. However, it is of great significance to save the storage space of the spent fuel pool by shrinkage and shearing work to increase the spare fuel lattice number. In order to solve the problem of shrinkage and shearing work of spent fuel involving the problem of radioactive safety, the radioactive source item is calculated by ORIGEN2 program base on Unit 1 Ⅱ of Lingao Nuclear Power Plant(NPP), and the radiation dose rate of the related component shrinkage operation scene is simulated by the MCNP5 program. In addition, the effectiveness of shielding measures is discussed, and the maximum dose rate is within 0.35 μSv/h at the distance of 2.5 m from component center, and the maximum dose rate is almost 0 at the distance of 3.2 m from the component center. The intensity of the radiation dose produced by the related components is very low and can be neglected, which belong to the green area of NPP. The program calculation system from source term calculation to shielding calculation is established, and an engineering example is referenced, and its application and analysis are carried out. It provides a basis for radioactive safety analysis and evaluation for the shrinkage operation of spent fuel and makes the shrinkage technology of fuel-related components safer and more reliable.
文摘The fast growth in the size and difficulty of nuclear power plant in the 1970s produced an interest in smaller, modest designs that are intrinsically safe over the usage of design features. With the development of nuclear technology, there is the need for revolution in the Maritime sector, especially the advance marine propulsion. In current years, numerous reactor manufacturers are dynamically improving small modular reactor designs with even superior use of safety features. Several designs integrate the ultimate in greater safety. They totally remove specific accident initiators from the design. Other design features benefit to reduce different types of accident or help to mitigate the accident’s consequences. Although some safety features are mutual to maximum SMR designs, irrespective of the coolant technology, other features are specific to liquid-metal cooled, water, gas, or SMR designs. Results: There have been more reactor concepts investigated in the marine propulsion area by different assemblies and research laboratories than in the power generation field, and much can be learned from their experience for land applications. The extensive use of safety features in SMRs potential to make these power plants extremely vigorous, protecting both the public and the investor. Conclusion: For these two considerations, it is recognized that a nuclear reactor is the ideal engine for naval advanced propulsion. The paper will present the work to analyze the concept design of SMRs and design a modular vessel consisting of a propulsion module.
基金Supported by the National Natural Science Foundation of China(No.11205088)the Aeronautical Science Foundation of China(No.2012ZB52021)+1 种基金the Fundamental Research Funds for the Central Universitiesthe Foundation of Graduate Innovation Center in NUAA(No.kfjj130125)
文摘A nuclear battery consisting of a beta source,a phosphor layer and a photovoltaic device was prepared.Planar phosphor layers were synthesized through physical precipitation of ZnS:Cu,ZnS:Ag or SrAl_2O_4:Eu^(2+),Dy^(3+)phosphors.The radioluminescence(RL)spectra were used to analyze the RL effects of the phosphor layers under beta-particle excitation.Feasibility of using the materials as intermediate absorbers in the beta batteries was studied.TheⅠ-Ⅴcharacteristics of beta RL nuclear batteries with different phosphor layers were tested using^(63)Ni or^(l47)Pm beta sources.The output power of zinc sulfide matrix phosphor layer was better than that of rare-earth element oxides.In addition,a thin aluminum reflective layer was vacuum-evaporated on the phosphor layers to improve the efficiency of beta RL nuclear batteries,and the results were discussed.
文摘With many advantages, hydrogen is considered as the fuel of the future. But there is no natural resourceof hydrogen and it must be produced by other kinds of energy. As for the primary energy, nuclear energy is a promis-ingalternative. Using heat from nuclear reactor to produce hydrogen is receiving more and more concerns in recentyears. This paper mainly emphasizes the study of the direct contact pyrolysis (DCP) of methane using heat from nu-clearreactor. A facility was designed to investigate the efficiency of DCP process in certain conditions. The experi-mentalresults show that this process produces only hydrogen and carbon. The conversion efficiency increases withtemperature and residence time, but decreases as flow rate increases. The highest efficiency of DCP obtained in thisexperiment is about 22%.
基金Sponsored by the National Natural Science Foundation of China under Grant Nos 11075037,11175219,10875151 and 10905041the Scientific Research Foundation for the Returned Overseas Chinese Scholars,State Education Ministry,the Fundamental Research Funds for the Central Universities of China,Shanghai Leading Academic Discipline Project(B107)the Knowledge Innovation Project of Chinese Academy of Sciences(KJCX2-EW-N01).
文摘The single-particle potentials in isospin asymmetric nuclear matter is investigated in the framework of the Brueck-ner theory by adopting the realistic Bonn B two-body interaction in combination with a consistent microscopic three-body force.The rearrangement contribution induced by the ground state correlations to single-nucleon potentials is calculated in terms of the hole-line expansion of the mass operator.With the modification of this rearrangement term the symmetry potential is discussed as a function of momentum for several isospin asymme.
基金Supported by the National Natural Science Foundation of China under Grant Nos 11075037,11175219 and 10875151the Scientific Research Foundation for the Returned Overseas Scholars,Ministry of Education of China,the Fundamental Research Funds for the Central Universities of China,Shanghai Leading Academic Discipline Project(B107)the Knowledge Innovation Project of the Chinese Academy of Sciences(KJCX2-EW-N01).
文摘With the complementarity of the nucleonic three-body force,we present the saturation points of symmetric nuclear matter with different interactions adopted within the Brueckner-Hartree-Fock scheme,and a more accurate empirical parameterization function for the equation of state of symmetric nuclear matter and pure neutron matter.On the basis of this fit formula,the symmetry energy and its derivatives are investigated,and ultimately the higher-order coefficient of the isobaric incompressibility for isospin asymmetric nuclear matter is predicted.
文摘Colloidal dispersions of nanoparticles are known as ＇nanofluids＇. Such engineered fluids offer the potential for enhancing heat transfer, particularly boiling heat transfer, while avoiding the drawbacks （e.g., erosion, settling, clogging） that hindered the use of particle-laden fluids in the past. At Massachusetts Institute of Technology （MIT）, the authors have been studying the heat transfer characteristics of nanofluids for the past five years, with the goal of evaluating their benefits for and applicability to nuclear power systems （e.g., primary coolant, safety systems, severe accident mitigation strategies）. This paper summarizes the MIT research in this area with particular emphasis to boiling behavior, including, prominently, the Critical Heat Flux limit and quenching phenomena.
基金supported by the National Natural Science Foundation of China (No. 12205150)Natural Science Foundation of Jiangsu Province (No. BK20210304)+1 种基金China Postdoctoral Science Foundation (Nos. 2020M681594 and 2019TQ0148)Jiangsu Province Postdoctoral Science Foundation (Nos. 2020Z231)
文摘Small modular reactors have received widespread attention owing to their inherent safety,low investment,and flexibility.Small pressurized water reactors(SPWRs)have become important candidates for SMRs owing to their high technological maturity.Since the Fukushima accident,research on accident-tolerant fuels(ATFs),which are more resistant to serious accidents than conventional fuels,has gradually increased.This study analyzes the neutronics and thermal hydraulics of an SPWR(ACPR50S)for different ATFs,BeO+UO_(2)−SiC,BeO+UO_(2)−FeCrAl,U_(3)Si_(2)−SiC,and U_(3)Si_(2)−FeCrAl,based on a PWR fuel management code,the Bamboo-C deterministic code.In the steady state,the burnup calculations,reactivity coefficients,power and temperature distributions,and control rod reactivity worth were studied.The transients of the control rod ejection accident for the two control rods with the maximum and minimum reactivity worth were analyzed.The results showed that 5%B-10 enrichment in the wet annular burnable absorbers assembly can effectively reduce the initial reactivity and end-of-life reactivity penalty.The BeO+UO2−SiC core exhibited superior neutronic characteristics in terms of burnup and negative temperature reactivity compared with the other three cases owing to the strong moderation ability of BeO+UO_(2)and low neutron absorption of SiC.However,the U_(3)Si_(2)core had a marginally better power-flattening effect than BeO+UO_(2),and the differential worth of each control rod group was similar between different ATFs.During the transient of a control rod ejection,the changes in the fuel temperature,coolant temperature,and coolant density were similar.The maximum difference was less than 10℃ for the fuel temperature and 2℃ for the coolant temperature.
基金supported by the Strategic Priority Research Program of the Chinese Academy of Science(Grant Nos.XDA25050200 and XDA25010100)the National Natural Science Foundation of China(Grant Nos.12175309,12475252,and 12275356)+2 种基金the Defense Industrial Technology Development Program(Grant No.JCKYS2023212807)the Natural Science Foundation of Hunan Province,China(Grant No.2025JJ20007)the Postgraduate Scientific Research Innovation Project of Hunan Province,China(Grant No.CX20230005).
文摘In the direct drive inertial confinement fusion(ICF)scheme,a rippled interface between the ablator and the deuterium–tritium ice fuel can feed out and form perturbation seeds for the ablative Rayleigh–Taylor instability,with undesirable effects.However,the evolution of this instability remains insufficiently studied,and the effects of high-Z dopant on this instability remain unclear.In this paper,we develop a theoretical model to calculate the feedout seeds and describe this instability.Our theory suggests that the feedout seeds are determined by the ablation pressure and the adiabatic index,while the subsequent growth depends mainly on the ablation velocity.Two-dimensional radiation hydrodynamic simulations confirm our theory.It is shown that targets with high-Z dopant in the outer ablator exhibit more severe feedout seeds,because of their higher ionization compared with undoped targets.The X-ray pre-ablation in high-Z doped targets significantly suppresses subsequent growth,leading to suppression of short-wavelength perturbations.However,for long-wavelength perturbations,this suppression is weakened,resulting in increased instability in high-Z doped targets.The results are helpful for understanding the innerinterface-initiated instability and the influence of high-Z dopant on it,providing valuable insights for target design and instability control in ICF.
基金supported by the National Key R&D Program of China(No.2023YFA1606501)the National Natural Science Foundation of China(Nos.12204110 and 12474251)+2 种基金Shanghai Pujiang Program(No.22PJ1401100)Max-Planck Partner Group Projectthe Fudan University Yan Liyuan-EnSiKai Foundation(JX240003)。
文摘Accurate atomic mass data hold significant application value in various research fields,in which Penning trap mass spectrometry is considered the most precise experimental method.A cryogenic detection system is a key component for reading out the image charge of charged particles in Penning traps using the Fourier transform ion cyclotron resonance technique.In this paper,we present the development and characteristics of this detection system,which includes a superconducting resonator and cryogenic low-noise amplifiers.The resonator consists of delicately woven thin NbTi wires configured into a multilayer helical coil,offering a quality factor of 98004 at around 1 MHz.Low-noise amplifiers are developed based on GaAs field effect transistors,exhibiting amplification factors greater than 27 dB with a power consumption of approximately 6 mW in the frequency range of 0.1 to 10 MHz.The lowest input voltage noise is 0.8√Hz at 1 MHz.The fabrication process,operation,and measurements are elucidated in detail.
基金Project(2024YFB4608600)supported by the National Key Research and Development Program of ChinaProjects(52271063,U21B2066,U24B2024)supported by the National Natural Science Foundation of China+3 种基金Project(JSGG20210713091539014)supported by the Shenzhen Science and Technology Innovation Commission Key Technical Project,ChinaProject(HNGD2025040)supported by the Overseas High-Level Talents Introduction of Henan Province,ChinaProject(240621041)supported by the Fundamental Research Funds of Henan Academy of Sciences,ChinaProject(20231120233925001)supported by Stabilization Support Program for Higher Education Institutions of Shenzhen,China。
文摘In this work,tensile mechanical behavior of 316L steels fabricated by three different processing methods(casting,powder extrusion printing(PEP)and laser powder bed fusion(LPBF))was studied in the presence of liquid lead-bismuth eutectic(LBE)and air at 350℃.The results show that all three steels tested in LBE are not subjected to evident degradation of tensile elongation to failure and strength compared to those tested in air,suggesting that LME does not occur regardless of the processing methods.The LPBF 316L steel exhibits the highest yield strength(420-435 MPa),followed by casting 316 L(~242 MPa)and PEP 316L(146-165 MPa).Ultimate tensile strength of three steels is comparable and ranges from 427 to 485 MPa.The PEP and casting 316L steels have similar total elongation to failure(i.e.,40.0%-43.8%),whereas this property decreases markedly to 18.6%-19.5% for the LPBF 316 L steel.The superior strength and relatively low ductility of the LPBF 316L steel can be attributed to nanosized dislocations trapped at cell structures which can produce a remarkable strengthening effect to the steel matrix.By contrast,due to massive residual micropores,the PEP 316L steel has the lowest strength.
基金supports by the Natural Science Foundation of China(52074032,51974029,52131307,52071013)and“111”Project(No.B170003).Y.D.and J.L.acknowledge the support by Eni S.p.A.through the MIT Energy Initiative.
文摘The challenge of sintering ultrafine-grained refractory metals and alloys to full density is hereby addressed by pressureless two-step sintering in tungsten-rhenium alloy and pure molybdenum. Using properly processed nano powders(~50 nm average particle size), we are able to sinter W-10Re alloy to 98.4% density below 1200 ℃ while maintaining a fine grain size of 260 nm, and sinter molybdenum to 98.3% density below 1120 ℃ while maintaining a fine grain size of 290 nm. Compared to normal sintering,two-step sintering offers record-fine grain sizes and better microstructural uniformity, which translates to better mechanical properties with higher hardness(6.3 GPa for tungsten-rhenium and 4.0 GPa for molybdenum, both being the highest in all pressurelessly sintered samples of the respective material system)and larger Weibull modulus. Together with our previous demonstration in tungsten, we believe that twostep sintering is a general effective method to produce high-quality fine-grained refractory metals and alloys, and the lessons learned here are transferable to other materials for powder metallurgy.
基金supported by the National Natural Science Foundation of China (50679001)NASA Constellation University Institutes Program
文摘To better understand the multiphase fluid dynamics and associated transport processes of cavitating flows at the capillary number of 0.74 and 0.54, and to validate the numerical results, a combined computational and experimental investigation of flows around a hydrofoil is studied based on flow visualizations and time-resolved interface movement. The computational model is based on a modified RNG k-ε model as turbulence closure, along with a vapor-liquid mass transfer model for treating the cavitation process. Overall, favorable agreement between the numerical and experimental results is observed. It is shown that the cavi- tation structure depends on the interaction of the water-vapor mixture and the vapor among the whole cavitation stage, the interface between the vapor and the two-phase mixture exhibits substantial unsteadiness. And, the adverse motion of the interface relates to pressure and velocity fluctuations inside the cavity. In particular, the velocity in the vapor region is lower than that in the two-phase region.
基金This work was supported by the National Natural Science Foundation of China(Nos.11805100 and 11905106)the Fundamental Research Funds for the Central Universities(No.NG2020003).
文摘A method based on the cross-sectional relationship between^(10)B(n,α)^(7)Li and^(1)H(n,γ)^(2)H was proposed to detect and reconstruct the three-dimensional boron concentration/dose distribution in vivo during boron neutron capture therapy(BNCT).Factors such as the neutron energy,fluence rate,and degree of non-uniform distribution of the boron concentration in a voxel may affect the results of this method.A theoretical analysis of the accuracy of the method using a Monte Carlo simulation shows that the determining error is generally less than 1%under different tumor locations and neutron source configurations.When the voxel size is larger than 0.4 cm,the determining error might be higher for a non-uniformly distributed boron concentration in the voxel because of the changes in the neutron energy and fluence rate.In conclusion,the proposed method enables an accurate threedimensional boron determination in vivo during BNCT.
基金supported by the National Key R&D Program of China(No.2019YFB1901100)the National Natural Science Foundation of China(No.11705138)the China National Postdoctoral Program for Innovative Talents(No.BX201600124)。
文摘The limited availability of studies on the natural convection heat transfer characteristics of fluoride salt has hindered progress in the design of passive residual heat removal systems(PRHRS)for molten salt reactors.This paper presents results from a numerical investigation of natural convection heat transfer characteristics of fluoride salt and heat pipes in the drain tank of a PRHRS.Simulation results are compared with experimental data,demonstrating the accuracy of the calculation methodology.Temperature distribution of fluoride salt and heat transfer characteristics are obtained and analyzed.The radial temperature of liquid fluoride salt in the drain tank shows a uniform distribution,while temperatures increase with increase in axial height from the bottom to the top of the drain tank.In addition,natural convection intensity increases with increase in height of the heat pipes in the tank.Spacing between heat pipes has no obvious effect on the natural convection heat transfer coefficient.This study will contribute to the design of passive heat removal systems for advanced nuclear reactors.
文摘This study evaluated the nuclear data libraries for a small 100 Mega Watt electric(MWe)Molten Salt Reactor with plutonium fuel.The reactor has a power output of 100 MWe,which meets the demand for electricity generation in several regions or provinces outside Java Island.Several nuclear data libraries,such as JEFF 3.1,ENDF/B-VII.0,JENDL 3.3,and JENDL 4.0,were used for a more comprehensive evaluation.LiF–BeF_(2)–ThF_(4)–PuF_(4) was used as the initial fuel composition.The thorium and plutonium concentrations in the fuel salt were varied to obtain the optimum fuel composition,leading to critical conditions.The results showed some neutronic parameters,such as the conversion ratio,neutron spectra,and effective multiplication factors,from three different nuclear data libraries.By changing the plutonium concentration in the initial fuel salt composition,the minimum plutonium loaded for the reactor criticality during 2000 days of operation time was determined to be 0.995,0.91,0.87,and 0.90 mol%for JEFF 3.1,ENDF/B-VII.0,JENDL 3.3,and JENDL 4.0,respectively.The differences in the values of each parameter were due to several factors,such as the cross-section values and number of nuclides in the nuclear data libraries.Several safety parameters were also investigated to ensure the possibility of utilizing PuF_(4) in the reactor.
文摘Absorption rate of CO2 into aqueous solution of N-methyldiethanolamine (MDEA) blended with diethanolamine (DEA) and piperazine (PZ) was studied and a kinetic model was established. It is shown that homogeneous activation mechanism could explain this absorption process. The absorption rate coefficients of carbon dioxide into MDEA aqueous solution blended with DEA, PZ or DEA+PZ were compared with each other. The results demonstrated that the different activation effect of DEA, PZ and DEA+PZ on the carbon dioxide absorption comes from the difference in CO2 combination rate, transport of PZ and DEA to MDEA and the regeneration rate of PZ and DEA.
