Device and method for single-rod boiling criticality test of nuclear reactor under six-degree-of-freedom motion conditions

Abstract

The invention discloses a single-rod boiling critical test device and method of a nuclear reactor under the condition of six-degree-of-freedom motion. The test device can carry out a closed forced circulation and natural circulation flow heat transfer test, and includes a shield pump, a voltage stabilizer and an orifice flow rate. meter, preheating section, test section, heat exchanger, metal hose, make-up pump, etc. The test section adopts the method of electric heating, and the main circuit is placed on a two-ton six-degree-of-freedom motion platform as a whole, which can complete the relevant research on the influence of ocean conditions on the critical heat flux density. Deionized water is used as the flowing working medium, and the deionized water enters the horizontal serpentine preheating section from the stabilizer and the shield pump (natural circulation without the shield pump), then enters the test section, and then passes through the heat exchanger, and finally returns to the steady state. Pressurizer to form a closed loop.

Description

technical field [0001] The invention relates to the research field of the CHF influence mechanism on the surface of a fuel rod under static conditions and ocean conditions, in particular to a single rod boiling critical test device and method of a nuclear reactor under six-degree-of-freedom motion conditions. Background technique [0002] Critical heat flux (CHF), as one of the important thermal safety criteria for reactor thermal-hydraulic design, is the heat flux when heat transfer deteriorates on the surface of nuclear fuel elements. Once the surface of the fuel element of the reactor is boiling critical, the surface temperature of the fuel element will be too high, which will cause the cladding to burn, the radioactive material leaks, and cause a serious nuclear accident. Theoretical research, but the experimental research on the CHF influence mechanism under ocean conditions is less, so it is necessary to focus on the CHF characteristics of the core fuel rod surface und...

AI Technical Summary

Problems solved by technology

Once critical boiling occurs on the surface of the reactor fuel element, the surface temperature of the fuel element will be too high, resulting in burning of the cladding, leakage of radioactive substances, and serious nuclear accidents. At present, a large number of scholars have carried out experiments and research on the characteristics of CHF under static conditions. Theoretical research, but there are few experimental studies on the mechanism of CHF under ocean conditions, so it is necessary to focus on the CHF characteristics of the core fuel rod surface under ocean conditions

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