Experiment device for verifying activation source item of primary loop coolant of reactor

Abstract

The invention discloses an experiment device for verifying an activation source item of a primary loop coolant of a reactor. The experiment device comprises an irradiation zone and a detection zone, wherein the irradiation zone and the detection zone are connected through a coolant pipe. The experiment device is characterized in that the irradiation zone comprises a radiation source and a mechanism which is formed by spirally winding a pipeline around a radiation source to surround the radiation source; the detection zone comprises a gamma energy spectrometer and a mechanism which is formed by spirally winding a pipeline around a probe of the gamma energy spectrometer to surround the probe of the gamma energy spectrometer. Leading-out after activating of a reactor coolant is simulated in a lab environment, controllability of neutron source strength, coolant variety and ingredients and coolant flow is realized, the contents of radionuclides in the primary loop coolant can be measured, a theoretical calculation result is evaluated, and experimental data are provided for correcting a theoretical calculation model, so that source item estimation is more reasonable and more 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...

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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

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