3 results about "Nuclear density" patented technology

The invention discloses a nuclear reactor core power capability verification method and device, and the method comprises the steps: obtaining first xenon atomic nucleus density distribution data of a reactor core according to a target reactor core working condition point corresponding to a typical burnup condition for any typical burnup condition of a plurality of typical burnup conditions of the reactor core; performing order reduction processing on the first xenon atomic nucleus density distribution data to obtain a plurality of low-order primary functions corresponding to the typical burnup condition and a target range of expansion coefficients corresponding to the plurality of low-order primary functions; obtaining second xenon atomic nucleus density distribution data corresponding to the typical burnup condition according to a plurality of recovery expansion coefficients corresponding to the typical burnup condition and a plurality of low-order basis functions; determining reactor core power distribution data corresponding to the typical burnup condition according to the second xenon atomic nucleus density distribution data; and performing power limit value verification on the reactor core power distribution data corresponding to each typical burnup condition to obtain a power capability verification result. According to the invention, the power capability verification calculation efficiency can be improved.

The present invention belongs to the field of calculation technology of fission product nuclear variation, and specifically relates to an analytical calculation method for fission yield variation in a strong neutron field, comprising the following steps: Step S1, determining initialization parameters, including product nuclear ID, burnup depth R, neutron energy E n In step S2, the spectral average cross section is read from the database; in step S3, the change in product nuclear density due to a nuclear reaction channel i is calculated relative to the change in the independent yield; in step S4, the contributions of each nuclear reaction channel calculated in step S3 are summed to obtain the change in product nuclear density. The analytical calculation method for strong neutron field fission yield variation provided by the present invention can rapidly calculate the change in strong neutron field fission yield and reveal the physical mechanism of yield variation, providing important technical support for strong neutron field research in nuclear testing.

The application discloses a neutron flux measurement method and device and a neutron flux calibration method and system, and relates to the technical field.The measurement method is applied to a neutron flux measurement system, and the neutron flux measurement system comprises a fuel rod sleeve of a micro reactor core critical device; M grooves are arranged on the fuel rod sleeve, and the grooves are used for accommodating detection activation sheets; M is a positive integer; the method comprises the following steps: acquiring a first correction factor, a first nuclear density, a first detection efficiency and M first information corresponding to the M grooves; and determining M absolute neutron fluxes corresponding to the M grooves according to the first correction factor, the first nuclear density, the first detection efficiency and the M first information.According to the embodiment of the application, the method not only meets the structural requirements of a compact reactor core, but also avoids the disturbance of carriers and supports to the neutron field in the reactor core, and the number of times of starting the reactor can be reduced.