Nuclear reactor single rod boiling critical test device and method under six-degree-of-freedom motion condition

Abstract

The invention discloses a nuclear reactor single rod boiling critical test device and method under the condition of six-degree-of-freedom motion, the test device can carry out closed forced circulation and natural circulation flow heat exchange tests, and the test device comprises a shield pump, a voltage stabilizer, an orifice plate flowmeter, a preheating section, a test section, a heat exchanger, a metal hose, a make-up pump and the like. A test section adopts an electric heating mode, and a main loop is integrally placed on a two-ton six-degree-of-freedom motion platform, so that related research on the influence of ocean conditions on critical heat flux density can be completed. Deionized water is selected as a flowing working medium, enters the horizontal snakelike preheating section from a voltage stabilizer and a shield pump (natural circulation does not pass through the shield pump), then enters the test section, passes through a heat exchanger and finally returns to the voltage stabilizer to form closed circulation.

Description

technical field [0001] The invention relates to the field of research on the influence mechanism of CHF on the fuel rod surface under static conditions and ocean conditions, in particular to a nuclear reactor single-rod boiling critical test device and method 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 the surface of nuclear fuel elements undergoes heat transfer deterioration. 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...

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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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