An experimental device for verifying the activation source term of the reactor primary loop coolant

Abstract

The invention discloses an experimental device for verifying the activation source item of the reactor primary circuit coolant, which includes an irradiation area and a detection area, and the irradiation area and the detection area are connected by a coolant pipe, and it is characterized in that the irradiation area The irradiation area includes a radiation source, and a mechanism surrounding the radiation source formed by pipes spirally surrounding the radiation source. Mechanism surrounded by instrumentation probes. In the laboratory environment, simulate the extraction of reactor coolant after activation, realize the controllability of neutron source intensity, coolant type and composition, and coolant flow rate, measure the content of each radionuclide in the primary loop coolant, and evaluate the theoretical calculation results , and provide experimental data to revise the theoretical calculation model to make the source term estimation more reasonable and accurate.

Description

technical field [0001] The invention relates to the field of nuclear reactors, in particular to an experimental device used for verifying the activation source item of a reactor primary circuit coolant. Background technique [0002] In an actual reactor, the nuclear fuel of the reactor itself is the most radioactive, followed by the coolant in the primary circuit. The theoretical calculation of the radioactive source term of the reactor nuclear fuel itself has achieved good calculation accuracy, and the shielding of the reactor itself has generally reached a good state; while the theoretical calculation of the primary circuit coolant radioactive source term has a large uncertainty , and the primary circuit coolant has a wide distribution range, which is an important content in the reactor source term and an important basis for shielding design. [0003] At present, most domestic reactor primary circuit coolants are light water reactors, especially domestic nuclear power pla...

AI Technical Summary

Problems solved by technology

[0004] The technical problem to be solved by the present invention is that in the design of the source term and the shielding, if the actual reactor and the primary circuit coolant activation source term are used for experimental measurement, the intensity of the radioactive neutron source is uncontrollable and the flow of the coolant is not uniform. The purpose of the problem is to provide an experimental device for the verification of the reactor primary circuit coolant activation source item, which simulates the reactor coolant being activated by neutrons in the laboratory environment, and can control the area where the coolant is irradiated, and make the The flow of the coolant is more uniform than that of the bucket design, and then the types and contents of each radionuclide in the coolant in the primary circuit are measured to make the source term estimation more reasonable and accurate

Images