3 results about "Nuclear data" patented technology

This invention discloses a monolithic, high-performance integrated nuclear and chemical gas detector, belonging to the field of nuclear and chemical detection technology. The invention includes a nuclear radiation detection module, a chemical gas detection module, and a central control and processing module. The nuclear radiation detection module and the chemical gas detection module are integrated and both connected to the central control and processing module. The nuclear radiation detection module includes a sampling module and a nuclear data output module, while the chemical gas detection module includes a chemical gas sampling module, a gas analysis module, and a gas data output module. This invention achieves integrated detection of both nuclear radiation and chemical gases. Through modular design and central control coordination, it enables simultaneous acquisition and analysis of nuclear radiation and chemical gases, achieving efficient and integrated monitoring of nuclear and chemical substances. Simultaneously, the integrated detection modules significantly reduce size and power consumption, making it more suitable for portable applications and improving the efficiency and comprehensiveness of early warning in hazardous scenarios.

The application discloses a kind of production methods of delayed photon ACE format database, first, the fission yield sublibrary and decay sublibrary of evaluation nuclear database are used to calculate the delayed photon production cross section;The delayed photon energy distribution can be obtained by processing the decay photon spectrum into the form of equal-probability energy band;To ensure that the average energy of the delayed photon obtained by calculation is the same as the average energy of the delayed photon given in the evaluation nuclear database, the delayed photon production cross section is corrected;Finally, the delayed photon production cross section, the delayed photon energy angle distribution information is stored in the ACE format database.The application proposes a kind of production method of delayed photon ACE format database, and the method has the advantages of high calculation accuracy and fast calculation speed in Monte Carlo program.

A method for calculating multi-group data of nuclear fuel considering resonance upscattering effects includes: 1. For nuclides in the nuclear fuel with resonant scattering cross-sections, a nuclear data processing program generates a resonance upscattering correction factor table for their total cross-section, fission cross-section, and absorption cross-section; 2. A fuel assembly calculation program performs resonance calculations to obtain the average multi-group cross-section of the nuclides, and interpolates the average multi-group cross-section in a traditional multi-group cross-section table that does not consider resonance upscattering to obtain the corresponding dilution cross-section; 3. Using the dilution cross-section, interpolation in the resonance upscattering correction factor table yields a correction factor, which is used to correct the average multi-group cross-section, resulting in a nuclear fuel multi-group cross-section considering resonance upscattering effects. This method solves the problem that fuel assembly calculation programs using ultrafine group methods for resonance calculations cannot consider resonance upscattering effects, providing accurate multi-group data for neutron transport calculations and improving the calculation accuracy of nuclear reactor safety parameters such as the effective multiplication coefficient and fuel temperature coefficient.