Today, millions of electrocommunication, electric, medical, and industrial devices use battery. Batteries with long life and high energy density seem to be essential in medical, military, oil and mining, aerospace are...Today, millions of electrocommunication, electric, medical, and industrial devices use battery. Batteries with long life and high energy density seem to be essential in medical, military, oil and mining, aerospace areas as well as conditions in which access is difficult and in situations where replacement or recharging of battery is costly.In this regard, the use of radiation energy resulting from radioactive materials and its conversion to electric energy can be effective in making batteries. In the present study,various Mo-99 radioisotope values with a half-life of 65.98 h were used as a soluble radioactive source in two materials of water and aqua regia. Then, by comparing the results of the Monte Carlo simulations program MCNPX for these two solutions, it was found that when the water is used instead of aqua regia(for idealization), the values of the superficial current of electrons, the volumetric flux of electrons, and the deposited energy in the volume containing the radioactive solution increased by 10.80, 4.10,and 13.80%, respectively. Also, the short-circuit current and energy conversion efficiency of this battery with a concentration of 0.01 molar, Mo-99 dissolved in the aqua regia are 0.79μA and 16.47%, respectively.展开更多
^(99)Mo是重要的医用放射性核素,溶剂萃取法是反应堆辐照^(235)U靶生产裂变^(99)Mo的分离方法之一。为探讨离子液体Cyphos IL 101用于裂变^(99)Mo分离的可能性,本研究评价了离子液体Cyphos IL 101在硝酸体系中对Mo(Ⅵ)的萃取行为,重点...^(99)Mo是重要的医用放射性核素,溶剂萃取法是反应堆辐照^(235)U靶生产裂变^(99)Mo的分离方法之一。为探讨离子液体Cyphos IL 101用于裂变^(99)Mo分离的可能性,本研究评价了离子液体Cyphos IL 101在硝酸体系中对Mo(Ⅵ)的萃取行为,重点考察了稀释剂、水相初始pH、萃取时间、温度、离子液体浓度等对萃取Mo(Ⅵ)的影响。结果表明,选用甲苯作为稀释剂时,Cyphos IL 101对Mo(Ⅵ)的萃取效果最好,在pH=3条件下,萃取率高达98.87%;萃取为自发进行的过程,且可在5 min达到平衡;选用1 mol/L Na_(2)CO_(3)作为反萃剂,一次反萃可将负载有机相中96.56%的Mo反萃到水相中。构建的离子液体Cyphos IL 101萃取体系对Mo与主要杂质Sr、Cs、Te等有很好的分离效果,体现了其对Mo(Ⅵ)的高选择性萃取能力。以上结果可为将离子液体Cyphos IL 101引入裂变^(99)Mo的分离工艺流程提供参考。展开更多
Irradiated low-enriched uranium as target plates is used to produce,via neutron radiation and from the molybdenum-99 fission product,technetium-99m,which is a radio-element widely used for diagnosis in the field of nu...Irradiated low-enriched uranium as target plates is used to produce,via neutron radiation and from the molybdenum-99 fission product,technetium-99m,which is a radio-element widely used for diagnosis in the field of nuclear medicine.The behavior of this type of target must be known to prevent eventual failures during radiation.The present study aims to assess,via prediction,the thermal–mechanical behavior,physical integrity,and geometric stability of targets under neutron radiation in a nuclear reactor.For this purpose,a numerical simulation using a three-dimensional finite element analysis model was performed to determine the thermal expansion and stress distribution in the target cladding.The neutronic calculation results,target material properties,and cooling parameters of the KAERI research group were used as inputs in our developed model.Thermally induced stress and deflection on the target were calculated using Ansys-Fluent codes,and the temperature profiles,as inputs of this calculation,were obtained from a CFD thermal–hydraulic model.The stress generated,induced by the pressure of fission gas release at the interface of the cladding target,was also estimated using the Redlich–Kwong equation of state.The results obtained using the bonded and unbonded target models considering the effect of the radiation heat combined with a fission gas release rate of approximately 3%show that the predicted thermal stress and deflection values satisfy the structural performance requirement and safety design.It can be presumed that the integrity of the target cladding is maintained under these conditions.展开更多
文摘Today, millions of electrocommunication, electric, medical, and industrial devices use battery. Batteries with long life and high energy density seem to be essential in medical, military, oil and mining, aerospace areas as well as conditions in which access is difficult and in situations where replacement or recharging of battery is costly.In this regard, the use of radiation energy resulting from radioactive materials and its conversion to electric energy can be effective in making batteries. In the present study,various Mo-99 radioisotope values with a half-life of 65.98 h were used as a soluble radioactive source in two materials of water and aqua regia. Then, by comparing the results of the Monte Carlo simulations program MCNPX for these two solutions, it was found that when the water is used instead of aqua regia(for idealization), the values of the superficial current of electrons, the volumetric flux of electrons, and the deposited energy in the volume containing the radioactive solution increased by 10.80, 4.10,and 13.80%, respectively. Also, the short-circuit current and energy conversion efficiency of this battery with a concentration of 0.01 molar, Mo-99 dissolved in the aqua regia are 0.79μA and 16.47%, respectively.
文摘^(99)Mo是重要的医用放射性核素,溶剂萃取法是反应堆辐照^(235)U靶生产裂变^(99)Mo的分离方法之一。为探讨离子液体Cyphos IL 101用于裂变^(99)Mo分离的可能性,本研究评价了离子液体Cyphos IL 101在硝酸体系中对Mo(Ⅵ)的萃取行为,重点考察了稀释剂、水相初始pH、萃取时间、温度、离子液体浓度等对萃取Mo(Ⅵ)的影响。结果表明,选用甲苯作为稀释剂时,Cyphos IL 101对Mo(Ⅵ)的萃取效果最好,在pH=3条件下,萃取率高达98.87%;萃取为自发进行的过程,且可在5 min达到平衡;选用1 mol/L Na_(2)CO_(3)作为反萃剂,一次反萃可将负载有机相中96.56%的Mo反萃到水相中。构建的离子液体Cyphos IL 101萃取体系对Mo与主要杂质Sr、Cs、Te等有很好的分离效果,体现了其对Mo(Ⅵ)的高选择性萃取能力。以上结果可为将离子液体Cyphos IL 101引入裂变^(99)Mo的分离工艺流程提供参考。
文摘Irradiated low-enriched uranium as target plates is used to produce,via neutron radiation and from the molybdenum-99 fission product,technetium-99m,which is a radio-element widely used for diagnosis in the field of nuclear medicine.The behavior of this type of target must be known to prevent eventual failures during radiation.The present study aims to assess,via prediction,the thermal–mechanical behavior,physical integrity,and geometric stability of targets under neutron radiation in a nuclear reactor.For this purpose,a numerical simulation using a three-dimensional finite element analysis model was performed to determine the thermal expansion and stress distribution in the target cladding.The neutronic calculation results,target material properties,and cooling parameters of the KAERI research group were used as inputs in our developed model.Thermally induced stress and deflection on the target were calculated using Ansys-Fluent codes,and the temperature profiles,as inputs of this calculation,were obtained from a CFD thermal–hydraulic model.The stress generated,induced by the pressure of fission gas release at the interface of the cladding target,was also estimated using the Redlich–Kwong equation of state.The results obtained using the bonded and unbonded target models considering the effect of the radiation heat combined with a fission gas release rate of approximately 3%show that the predicted thermal stress and deflection values satisfy the structural performance requirement and safety design.It can be presumed that the integrity of the target cladding is maintained under these conditions.
