35 results about "Nuclear science" patented technology

The invention belongs to the technical field of nuclear science and engineering, and relates to a device and method for controlling the oxygen content in liquid lead bismuth alloy. The device for controlling the oxygen content in the liquid lead bismuth alloy is mainly characterized in that a heating cavity is formed in front of the liquid inlet end of an oxygen content control chamber, the heating cavity is connected with a liquid metal mechanical pump through the oxygen content control chamber, a liquid inlet end oxygen probe is arranged at the liquid inlet end of the oxygen content control chamber, and a liquid outlet end oxygen probe is arranged at the liquid outlet end of the oxygen content control chamber; a liquid metal flow meter is arranged at the outlet end of the liquid metal mechanical pump, an outlet of the liquid metal flow meter is connected with a liquid lead bismuth alloy valve, and a reflux inlet of the liquid lead bismuth alloy valve is communicated with a liquid storage tank through a reflux pipeline and is communicated with the heating cavity; vacuum pumping and measuring systems are arranged in the liquid storage tank and the oxygen content control chamber. The device and method have the advantages that Ar-H2 mixed gas and reactive oxygen in the liquid lead bismuth alloy conduct chemical reaction in the oxygen content control chamber, and then the oxygen content can be controlled.

The invention belongs to the field of devices for controlling oxygen / corrosion for high-temperature lead-bismuth melt in nuclear science, and relates to a device and a method for automatically controlling oxygen corrosion for high-temperature lead-bismuth melt. The device for automatically controlling the oxygen / corrosion for the high-temperature lead-bismuth melt is characterized by comprising a storage tank; a vacuum system, a temperature control system, a cooling system, an oxygen concentration control system, a sample corrosion experiment system and an automatic control and data processing system are arranged on the storage tank. The device and the method have the advantages that the vacuum of 1*100<-2> Pa can be generated by the vacuum system and is matched with a gas inlet pipeline of an upper cover, a tank can be repeatedly washed by the aid of high-purity Ar gas, and accordingly oxidation of lead and bismuth in early running stages and shutdown phases of the device can be effectively relieved; a water jacket is arranged on an upper cover structure, a plurality of layers of heat-insulation plates are arranged below the upper cover structure, the water jacket, the heat-insulation plates and the cooling system are combined with one another, accordingly, influence of heat conduction and heat radiation of the high-temperature lead and bismuth on the upper cover can be effectively relieved, and components of the upper cover can assuredly normally work in safety ranges when the lead-bismuth melt is operated at the high temperatures of 650 DEG C.

The invention provides a conversion algorithm from a CAD model to an MCNP geometric model based on an STEP text, and the algorithm relates to the technical fields of physics and nuclear science. The algorithm is based on the STEP text generated by CAD software, information extraction is carried out on the STEP text, then a geometric algorithm is used for restoring a real model structure, finally conversion is carried out on an INP text format which can be recognized by the MCNP. In order to solve complex model problems, all lattice cell information of a model is stored in a lattice cell tree by adopting a method for constructing the lattice cell tree by the algorithm, and by means of the traverse lattice tree, the INP text format which can be recognized by the MCNP can be output. Outputs of a hook face card and a lattice cell card are free from omission, the position is accurate, and the treatment is flexible.

The invention discloses a leakless glove replacing device for a nuclear science glovebox. The leakless glove replacing device comprises gloves, and fixing rings which are arranged in the position of a glovebox opening, wherein one glove is arranged on the corresponding two fixing rings; the glovebox opening is provided with a vacuumizing port and / or an air supplementing port. The leakless glove replacing device for the nuclear science glovebox provided by the invention has the advantages that the sealing performance is good, and the situation that nuclear leakage and liquid oxygen leakage are not caused in the process of replacing the gloves through the glovebox in the nuclear science research application can be effectively guaranteed.

The invention relates to a method for preparing zirconium deuteride by a high-temperature direct process and belongs to the crossed field of material science and nuclear science. The zirconium deuteride is generated through the reaction of metal zirconium and deuterium at a high temperature. The problems of an industrial large-scale zirconium deuteride preparing technology and preparing purity problems are solved, no complicated production devices are required, required preparing devices are simple and easy to purchase, and the safe construction of a zirconium deuteride production line can be realized under existing factory conditions. The preparing technology is simple and easy to operate, no high-temperature pressurization devices are required in the preparing process, and safe and reliable inert gas protection is provided. The yield, purity and stability of the product are great. The product can be stored for a long time. No three wastes are produced in the production process, so that no damage to the human body and the environment is caused. The method is environment-friendly and green and has great significance in the industrial large-scale safe preparation of the high-purity zirconium deuteride and large-scale application.

The invention discloses a combined accelerating structure belonging to the fields of nuclear science and nuclear technology. The combined accelerating structure comprises a radio-frequency quadrupole field part and a separation function radio-frequency quadrupole field part. The radio-frequency quadrupole field part and the separation function radio-frequency quadrupole field are directly connected in the same resonant cavity and center lines of the radio-frequency quadrupole field part and the separation function radio-frequency quadrupole field are coaxial. The radio-frequency quadrupole field part and the separation function radio-frequency quadrupole field adopt the same support mode. The invention not only can save another set of high-powder transmitter and relevant high-frequency control systems so that the total high-frequency power is greatly lower than the summation of the power of two transmitters, but also save matched elements of a high-power electromagnetic lens and the like, so that the overall dimension and the cost of an accelerator can be reduced; in addition, the overall delivery efficiency of beam current can be improved because of avoiding the unbalance of longitudinal and transverse matching of the beam current.

A device and method stably regulating and controlling radon progeny state parameters relate to the nuclear science technical field; the device stably regulating and controlling radon progeny state parameters comprises a monodispersion aerosol generation unit, a small volume radon chamber, a source filling regulation and control loop, a radon progeny state parameter regulation and control loop, anda sampling monitoring loop; the sampling monitoring loop can intake a sampling flow rate of the sampling measuring device into a radon chamber total air-exchange flow rate, so the sampling measuringdevice cannot affect the radon progeny state parameters in the radon chamber; the radon progeny state parameter regulation and control loop can continuously and stably regulate and control the radon progeny concentration, radon progeny balance factors and radon progeny uncombined state fraction, thus providing continuous and complete radon progeny parameters for a radon progeny monitor scale calibration test and an artificial radioactivity aerosol monitor radon progeny compensation validity test; the device and method are suitable for field scale calibration tests of the radon progeny monitor.

The invention relates to a method for inducing the defect annealing based on ionization irradiation, and aims at solving a problem that the particle radiation will cause the displacement damage to a device. The method comprises the steps: calculating the ionization / displacement absorbed dose and range of unit fluence incident particles based on a Monte Carlo computing method; determining the typeof incident particles according to the proportional relation between the ionization and the displacement absorbed dose and the features of a sample, thereby guaranteeing that the incident particles can promote the annealing of existing defect in the sample in a conveying process of the sample. The method is simple in steps, and is easy for operation. The method is used for the technical field of spatial environment effects, nuclear science and application technologies.

The invention relates to a method for preparing titanium deuteride by a high-temperature direct process, belonging to the cross fields of material science and nuclear science. Metal titanium and deuterium gas react at high temperature to generate the titanium deuteride. The method solves the problems of titanium deuteride industrial-scale preparation technique and preparation purity, does not need complex production devices, only needs simple and accessible preparation devices, and thus, can implement safe construction of the titanium deuteride production line under existing plant conditions. The preparation technique is simple and easy to operate, does not need any high-temperature pressurizing or depressurizing device in the preparation process, and is safe and reliable under the protection of inert gas. The product has the advantages of favorable yield, favorable purity and high stability, and can be stored for a long time. The method does not generate three wastes in the production process, is harmless to the human body and environment, is environment-friendly and green, and thus, has important meanings for industrial large-scale safe preparation of high-purity titanium deuteride and large-scale application thereof.

The invention discloses a photocathode microwave electronic gun automatic aging system and a method and belongs to the nuclear science and nuclear technology field. In the invention, through monitoring phenomena of photocathode microwave electronic gun adsorption gas release, spark discharge and the like, and measuring parameters of a high voltage, input power, reflection power, a vacuum degree, an ion flow, a dark current and the like of a modulator, power increase during an aging process is automatically adjusted, a cavity is prevented from being damaged by high power, inconsistency of manual aging operation personnel is avoided and aging time is shortened. According to a measurement result, a cavity aging state is controlled. During the aging process, a program timely reads the aging state, a correlation parameter is automatically controlled, the spark discharge and generation of the dark current are reduced, and performance and a service life of the cavity are increased and prolonged. By using the method and the system, complete recording of the aging process can be achieved. Simultaneously, a lot of manpower, material resources and time can be saved.

The invention discloses a nuclear science material replacement anti-corrosion system which is characterized in that a connecting pipe is slidably mounted in a feeding pipe, a tank cover is mounted at one end of a storage tank through a cover sealing mechanism, a repairing mechanism is arranged in the storage tank, and a fixing block is fixedly mounted on the inner side of the storage tank, so that a rotating rod is rotatably mounted; when the inner side needs to be replaced, a fixing bolt is loosened, limitation on a rotating rod is relieved, the rotating rod is rotated to be removed from a fixing clamping base, accordingly limitation on the position of a T-shaped block is relieved, a pull rod is pulled, the lining is driven to move, then a sliding column is driven to move, a mounting plate drives the T-shaped block to move, and therefore the lining is pulled out of a storage tank. The liner is more convenient to disassemble, convenient to replace and convenient to replace and repair, synchronous replacement of the tank body and the liner during replacement and repair is avoided, the service life of the tank body is prolonged, and coating failure caused by long-time use is avoided.

The invention provides an irradiation particle energy selection method capable of simultaneously generating ionization and displacement defects, and belongs to the technical field of space environmental effects, nuclear science and applications. The application objects of the irradiation particle energy selection method include various key materials and devices for spacecrafts. The ionization / displacement absorption dose and range of incident particles per unit injection are calculated under specific material state conditions on the basis of a Monte Carlo calculation method. The energy of theincident particles can be determined according to the proportional relationship between the ionization absorption dose and the displacement absorption dose, so that the condition that stable ionization and displacement defects can be simultaneously generated is ensured.

The invention provides the Magnetoelectric Effect Material consisted of a single isotope, the alloy of isotopes, or the compound of isotopes. The invention applies enrichment and purification to increase the isotope abundance, to create the density of nuclear exciton by irradiation, and therefore increase the magnetoelectric effect of the crystal of single isotope, the alloy crystal of isotopes and the compound crystal of isotopes. The invention provides the manufacturing method including the selection rules of isotopes, the fabrication processes and the structure of composite materials. The invention belongs to the area of the nuclear science and the improvement of material character. The invention using the transition of entangled multiple photons to achieve the delocalized nuclear exciton. The mix of selected isotopes adjusts the decay lifetime of nuclear exciton and the irradiation efficiency to generate the nuclear exciton.

The invention provides a reactor fuel element performance parallelization processing method which can achieve parallelization processing of fuel element performance and is high in processing speed andshort in consumed time. The method comprises the following steps: allocating processes, wherein each process is used for carrying out performance analysis on a single fuel rod; reading a path of an input file through a main process, broadcasting the read path to a sub-process, wherein the input file comprises parameter information of a plurality of fuel rods; allowing each process to read parameter information of a corresponding fuel rod in the input file according to the received path, performs performance analysis on the corresponding fuel rod according to the read parameter information, and outputs a performance analysis file of each process; and allowing a host process to read the performance analysis files of all the processes and write the performance analysis files into the same performance analysis file. The invention relates to the field of computational material science, nuclear science and technology.

The invention provides an irradiation particle energy selection method capable of simultaneously generating ionization and displacement defects, and belongs to the technical field of space environmental effects, nuclear science and applications. The application objects of the irradiation particle energy selection method include various key materials and devices for spacecrafts. The ionization / displacement absorption dose and range of incident particles per unit injection are calculated under specific material state conditions on the basis of a Monte Carlo calculation method. The energy of theincident particles can be determined according to the proportional relationship between the ionization absorption dose and the displacement absorption dose, so that the condition that stable ionization and displacement defects can be simultaneously generated is ensured.

The invention relates to a method for directly preparing zirconium deuteride by using a high temperature direct method, belonging to the field of material science and nuclear science. According to the method, metal zirconium is reacted with deuterium gas, and thus zirconium deuteride is generated. By adopting the method, the problems of industrial-scale zirconium deuteride preparation techniques and preparation purity are solved, no complex production device is needed, the necessary preparation devices are simple and easy to purchase, and safety construction of a zirconium deuteride production line can be achieved under the existing factory conditions; the preparation process is simple and easy to operate, no high temperature pressurizing / depressurizing device is used in the preparation process, and due to protective inert gases, the production is safe and reliable; the zirconium deuteride product is relatively good in yield and purity, good in stability and can be stored for a long time; the production process is free of three wastes, is harmless for human bodies and the environment, is environment-friendly, and is significant for safe industrial scale preparation and large-scale application of high-purity zirconium deuteride.

The invention discloses a non-leakage glove replacement device for a nuclear science glove box. . The invention provides a non-leakage glove replacement device for a nuclear science glove box. The device has good sealing performance and can effectively ensure that the glove box used in nuclear science research has no nuclear leakage and no water and oxygen leakage during glove replacement.

The invention provides a method for calculating the ionization absorbed dose of a radiation sensitive part based on absorbed dose depth distribution, and belongs to the technical field of spatial environment effect and nuclear science and application. The method comprises the steps: selecting a material with the known one-dimensional ionization absorbed dose depth distribution, and converting theabsorbed dose depth distribution of the material into the distribution of absorbed dose with equivalent depth; carrying out the regional dividing of a structure where the radiation sensitive part is located, determining the material types of all regions, the material thicknesses of all regions and the maximum degree of the connection lines between the radiation sensitive part and the regions; converting the thicknesses of the materials of all regions into equivalent thicknesses, determining the absorbed dose and unidirectional absorbed dose at each equivalent thickness, and finally calculatingand obtaining the ionization absorbed dose of a sensitive part in the structure. The method solves problems in the prior art that the calculation of the ionization absorbed dose of the radiation sensitive part is complex and the consumed time is long. The method can be used for quickly evaluating the ionization absorbed dose of complex structures, such as a spacecraft.

The invention provides a device for simultaneously generating ionization and displacement defect signals for characterizing the formation and annealing state of different types of particle radiation-induced ionization and displacement defects, and a preparation method thereof, belonging to the field of nuclear science and technology. The present invention includes a collector region, a base region, n emitter regions, an emitter, a base and a collector; the doping concentration of the collector region is less than 1E15 / cm 3 The distance d from the long side of the outer edge of the base region to the outer edge of the collector region is in the range of 0.1 to 300 μm, and the distance e from the wide side of the outer edge of the base region to the outer edge of the collector region is in the range of 0.1 to 300 μm; the base region is doped The concentration is 1E15 / cm 3 ~1E17 / cm 3 ; The ratio of the long side a to the wide side b of the emission region is in the range of 500:1 to 1:500, and the depth of the diffusion junction is between 0.1 μm and 3.0 μm; the distance between two adjacent emission regions is not less than a / 2, Not more than 5a; the doping concentration of the emitter region is 5E15 / cm 3 ~1E20 / cm 3 .

A method for inhibiting the formation of oxide trapped charges based on displacement damage is provided. The invention relates to the field of space environmental effects, nuclear science and appliedtechnology, and solves the radiation damage performance of electronic devices by oxide trapped positive charges and an interface state. The method comprises determining the farthest distance b and theclosest distance c from a passivation layer in an electronic component to the surface; calculating the range t1 of a pre-irradiated incident particle; calculating the ionizing absorbed dose Id1 and the displacement absorbed dose Dd1 of the incident particle in the passivation layer; calculating the value of Log[(Id+Dd) / Dd]; perofrming pre-irradiation and determining the irradiation injection amount [phi]1; calculating the incident depth t2 of an ionizing radiation incident particle; calculating the ionizing absorbed dose Id2 and the displacement absorbed dose Dd2 of the incident particle in the passivation layer; calculating the value of log[(Id2+Dd2) / Dd2];and perform ionizing irradiation. The method changes the inherent displacement defect state in a sample, inhibits the formation of oxide trapped positive charges, and is simple in steps and easy to operate. The method is applied to the research of space environmental effects of electronic components and the anti-radiation reinforcement technology.

The invention relates to a bipolar transistor ELDRS (Enhanced Low Dose Rate Sensitivity) suppressing method and belongs to the technical field of space environment effect, nuclear science and application. The method provided by the invention is proposed aiming at a defect of lack of a bipolar transistor ELDRS suppressing means in the prior art. The method includes putting a transistor into a sealed container, vacuumizing the container or filling with protective gas, wherein the transistor is a bipolar transistor; heating the transistor with an electric furnace and performing thermal insulation; cooling the transistor to a room temperature after thermal insulation ends. The method is suitable for anti-radiation treatment on components and parts in electric systems in a spacecraft cabin.

The invention provides a method for calculating the radiation sensitive part displacement absorption dose based on absorption dose depth distribution, and belongs to the technical field of space environment effect, nuclear science and application. The method includes selecting a material with known one-dimensional displacement absorption dose depth distribution, converting the displacement absorption dose depth distribution into the absorption dose equivalent thickness distribution; performing the area division on the structure where the radiation sensitive part is located, determining the types of materials in each region and the thickness of each material; and then converting the thickness of the material in each region into the equivalent thickness, determining the absorption dose of each equivalent thickness and the one-way absorption dose, and finally, calculating and obtaining the displacement absorption dose of the sensitive part in the structure. The problems that a radiation sensitive part of the prior art is complex in displacement absorption dose calculation and long in time consumption are solved. The method can be used for rapidly evaluating the displacement absorptiondose of complex structures such as a spacecraft.

The invention belongs to the technical field of nuclear science and engineering, and relates to a device and method for controlling the oxygen content in liquid lead bismuth alloy. The device for controlling the oxygen content in the liquid lead bismuth alloy is mainly characterized in that a heating cavity is formed in front of the liquid inlet end of an oxygen content control chamber, the heating cavity is connected with a liquid metal mechanical pump through the oxygen content control chamber, a liquid inlet end oxygen probe is arranged at the liquid inlet end of the oxygen content control chamber, and a liquid outlet end oxygen probe is arranged at the liquid outlet end of the oxygen content control chamber; a liquid metal flow meter is arranged at the outlet end of the liquid metal mechanical pump, an outlet of the liquid metal flow meter is connected with a liquid lead bismuth alloy valve, and a reflux inlet of the liquid lead bismuth alloy valve is communicated with a liquid storage tank through a reflux pipeline and is communicated with the heating cavity; vacuum pumping and measuring systems are arranged in the liquid storage tank and the oxygen content control chamber. The device and method have the advantages that Ar-H2 mixed gas and reactive oxygen in the liquid lead bismuth alloy conduct chemical reaction in the oxygen content control chamber, and then the oxygen content can be controlled.

The invention relates to a method for calculating an energy spectrum behind a charged particle protection layer, and aims at solving the problems in the prior art that the calculation speed of an energy spectrum after an orbital charged particle protection layer is slow, the calculation time is long and the spatial particle radiation will cause the shortening of the service life of an electronic device and then cause big loss. The process comprises the steps: determining a differential energy spectrum of orbital incident particles; determining a protection material and the thickness of the protection material; determining the incident angle of the incident particles; calculating the relation between E'1 and the range and thickness of the protection material if the incident particles are electrons; calculating the relation between each of E'2, E'3, E'4 and E'5 and the range and thickness of the protection material if the incident particles are protons or ions; and calculating an unelastic cross section of the incident particles and the protection material; and respectively calculating the differential energy spectrums behind electron, proton and ion protection layers. According to the invention, the method is used in the technical field of spatial environment effects, nuclear sciences, and application technologies.

The invention relates to a bipolar transistor ELDRS (Enhanced Low Dose Rate Sensitivity) suppressing method and belongs to the technical field of space environment effect, nuclear science and application. The method provided by the invention is proposed aiming at a defect of lack of a bipolar transistor ELDRS suppressing means in the prior art. The method includes putting a transistor into a sealed container, vacuumizing the container or filling with protective gas, wherein the transistor is a bipolar transistor; heating the transistor with an electric furnace and performing thermal insulation; cooling the transistor to a room temperature after thermal insulation ends. The method is suitable for anti-radiation treatment on components and parts in electric systems in a spacecraft cabin.

Bipolar device heterogeneous radiation source ionization damage equivalent evaluation test method, involving radiation tests of materials and devices, belongs to the field of nuclear science and technology, in order to realize the prediction of performance degradation characteristics of bipolar transistors under different types of particle irradiation conditions . The invention is based on a radiation source to establish a performance degradation model to equivalently simulate the ground equivalent simulation test method of radiation damage of other radiation sources, and its application objects include bipolar transistors and other types of bipolar process devices; only by selecting a certain The performance degradation model of bipolar devices can be established by carrying out irradiation experiments with specific energy and types of charged particles under appropriate irradiation flux conditions; by combining the Monte Carlo method to calculate and analyze the damage ability of other types of irradiation sources, you can The radiation damage of different types of radiation sources is normalized to achieve the purpose of predicting the degradation of on-orbit performance. The beneficial effect is that the on-rail ionization damage performance degradation rule of the bipolar transistor can be accurately predicted, and the steps are simple and easy to operate.

The invention belongs to the field of devices for controlling oxygen / corrosion for high-temperature lead-bismuth melt in nuclear science, and relates to a device and a method for automatically controlling oxygen corrosion for high-temperature lead-bismuth melt. The device for automatically controlling the oxygen / corrosion for the high-temperature lead-bismuth melt is characterized by comprising a storage tank; a vacuum system, a temperature control system, a cooling system, an oxygen concentration control system, a sample corrosion experiment system and an automatic control and data processing system are arranged on the storage tank. The device and the method have the advantages that the vacuum of 1*100<-2> Pa can be generated by the vacuum system and is matched with a gas inlet pipeline of an upper cover, a tank can be repeatedly washed by the aid of high-purity Ar gas, and accordingly oxidation of lead and bismuth in early running stages and shutdown phases of the device can be effectively relieved; a water jacket is arranged on an upper cover structure, a plurality of layers of heat-insulation plates are arranged below the upper cover structure, the water jacket, the heat-insulation plates and the cooling system are combined with one another, accordingly, influence of heat conduction and heat radiation of the high-temperature lead and bismuth on the upper cover can be effectively relieved, and components of the upper cover can assuredly normally work in safety ranges when the lead-bismuth melt is operated at the high temperatures of 650 DEG C.

A method for inhibiting the formation of oxide trapped charges based on displacement damage is provided. The invention relates to the field of space environmental effects, nuclear science and appliedtechnology, and solves the radiation damage performance of electronic devices by oxide trapped positive charges and an interface state. The method comprises determining the farthest distance b and theclosest distance c from a passivation layer in an electronic component to the surface; calculating the range t1 of a pre-irradiated incident particle; calculating the ionizing absorbed dose Id1 and the displacement absorbed dose Dd1 of the incident particle in the passivation layer; calculating the value of Log[(Id+Dd) / Dd]; perofrming pre-irradiation and determining the irradiation injection amount [phi]1; calculating the incident depth t2 of an ionizing radiation incident particle; calculating the ionizing absorbed dose Id2 and the displacement absorbed dose Dd2 of the incident particle in the passivation layer; calculating the value of log[(Id2+Dd2) / Dd2];and perform ionizing irradiation. The method changes the inherent displacement defect state in a sample, inhibits the formation of oxide trapped positive charges, and is simple in steps and easy to operate. The method is applied to the research of space environmental effects of electronic components and the anti-radiation reinforcement technology.