Abstract: Provided are a method and a device for acquiring a temperature and a computer-readable storage medium. The method for acquiring a temperature includes: building a temperature acquisition model, wherein the temperature acquisition model is configured to acquire, based on an operating parameter of the radioactive substance treatment system input to the temperature acquisition model, a temperature of different parts of the radioactive reactant in the radioactive substance treatment system under a condition of the parameter; inputting a current operating parameter of the radioactive substance treatment system into the temperature acquisition model during the treatment for the radioactive substance; and acquiring a current temperature of different parts of the radioactive reactant in the radioactive substance treatment system output by the temperature acquisition model.

Abstract: A method including: manufacturing a standard transmission object; simulating a transmission measurement process using simulation calculation method, to establish a database with respect to a transmission thickness, an equivalent water density, an original reconstruction density of the standard transmission object, a space angle cosine of the transmission source and an energy of a ? ray, fitting a corresponding relationship of the space angle cosine of the transmission source with respect to parameters of the standard transmission object and the energy of the ? ray based on the database; selecting a corresponding standard transmission object for transmission measurement for a transmission source to be characterized, to obtain an original reconstruction density of the standard transmission object; reading the space angle cosine of the transmission source to be characterized from the database according to fitted corresponding relationship of known parameters of the standard transmission object and the energy of

Abstract: A method for treating retained plutonium in a waste organic phase of a plutonium uranium reduction extraction (PUREX) process is provided. The waste organic phase of the PUREX process contains an organic solvent and plutonium, and the method includes contacting the waste organic phase of the PUREX process with an aqueous back extraction solution containing 2,6-pyridinedicarboxylic acid for back extraction to obtain a plutonium back extraction product; and the plutonium in the back extraction solution may be loaded onto the column for adsorption, transformation and desorption by an anion exchange column, ultimately recovering plutonium in the back extraction solution.

Abstract: Provided are a method and a device for acquiring a temperature and a computer-readable storage medium. The method for acquiring a temperature includes: building a temperature acquisition model, wherein the temperature acquisition model is configured to acquire, based on an operating parameter of the radioactive substance treatment system input to the temperature acquisition model, a temperature of different parts of the radioactive reactant in the radioactive substance treatment system under a condition of the parameter; inputting a current operating parameter of the radioactive substance treatment system into the temperature acquisition model during the treatment for the radioactive substance; and acquiring a current temperature of different parts of the radioactive reactant in the radioactive substance treatment system output by the temperature acquisition model.

Abstract: There is provided a method of tracking a characteristic line, a method and apparatus of calculating core neutron physics, and a computer-readable storage medium. The method of tracking the characteristic line includes: determining, sequentially from the uppermost level to the lowest level, whether an intersection of the sub-model meeting a first preset condition in each of the plurality of levels and the characteristic line segment meets a second preset condition or not; and obtaining an intersection, that meets the second preset condition, of the sub-model meeting the first preset condition in the lowest level and the characteristic line, so as to obtain a segment correspondence between the characteristic line and the material of the core according to the intersection obtained.

Abstract: The disclosure relates to a method and a system for predicting the operation time of sparse matrix vector multiplication. The method comprises constructing a convolutional neural network comprising an input layer, a feature processing layer, a data splicing layer and an output layer for outputting prediction results. The method further comprises acquiring a plurality of groups of sparse matrices with known sparse matrix vector multiplication operation time as sample data, inputting the sample data into the convolutional neural network to train the convolutional neural network, and inputting the sparse matrix to be classified into the trained convolutional neural network to realize the prediction of the operation time of sparse matrix vector multiplication.

Abstract: A method and device for simulating microstructure evolution of a material based on solution in an exponential time-difference format. The method includes: establishing a reaction rate theory model for substance defects, wherein the model is expressed with equations that comprise linear terms having coefficients characterized with matrixes; and iteratively solving the equations by using an exponential time-difference format, wherein during the iterative solving, the linear terms with exponential powers of the matrixes as the coefficients are integrated. Since a rate theory is not limited by spatial-temporal scales, the advantages of the rate theory can be significantly reflected when the microstructure evolution is simulated under a high damage dose condition; and then, the equations are solved by using the exponential time-difference format, with a solved result better in accuracy and higher in precision.

Abstract: A method including: manufacturing a standard transmission object; simulating a transmission measurement process using simulation calculation method, to establish a database with respect to a transmission thickness, an equivalent water density, an original reconstruction density of the standard transmission object, a space angle cosine of the transmission source and an energy of a ? ray, fitting a corresponding relationship of the space angle cosine of the transmission source with respect to parameters of the standard transmission object and the energy of the ? ray based on the database; selecting a corresponding standard transmission object for transmission measurement for a transmission source to be characterized, to obtain an original reconstruction density of the standard transmission object; reading the space angle cosine of the transmission source to be characterized from the database according to fitted corresponding relationship of known parameters of the standard transmission object and the energy of

Abstract: The present invention relates to a spent fuel dry reprocessing method for directly obtaining a zirconium alloy nuclear fuel, comprising: determining components and a ratio of a molten salt composition used for melting a spent fuel according to a requirement of reactor design on a zirconium alloy fuel and contents of actinium series metals in the spent fuel; melting the spent fuel in the above molten salt composition; and selecting an electrode pair for electrodeposition so that zirconium in the molten salt composition and uranium ions in the spent fuel or uranium and other actinium series metal ions are subjected to co-deposition, thereby obtaining the zirconium alloy nuclear fuel meeting a design requirement. The spent fuel dry reprocessing method provided by the invention is suitable for oxide spent fuel and metal spent fuel, and is simple and controllable in process, low in energy consumption, low in cost and easy to industrialize.

Abstract: The present invention provides an accelerator mass spectrometry device for simultaneously measuring isotopes. In one embodiment, the device comprises a sputtering negative ion source for generating negative ions; the sputtering negative ion source being connected to an accelerating tube for simultaneously accelerating a plurality of isotopic ions; an output end of the accelerating tube being connected to an isotope mass resolution system; the isotope mass resolution system being connected to a charge conversion analysis and multi-receiving measurement system; the charge conversion analysis and multi-receiving measurement system being connected to an ion detection system. The present invention is capable of accelerating a plurality of isotopic negative ions simultaneously. The accelerated isotopic negative ions are separated. Stable isotopic negative ions are measured by a stable isotope receiver. Unstable isotope negative ions are converted to positive ions and then measured by a detector.