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

A boiling critical and test device technology, applied in nuclear reactor monitoring, reactors, nuclear engineering, etc., can solve problems such as cladding burning and radioactive material leakage

CN114121319AActive Publication Date: 2022-03-01XI AN JIAOTONG UNIV
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Patent Information

Authority / Receiving Office
CN · China
Patent Type
Applications(China)
Current Assignee / Owner
Publication Date
2022-03-01

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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.
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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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Embodiment Construction

[0026] The present invention will be described in further detail below in conjunction with the accompanying drawings.

[0027] Such as figure 1 As shown, the present invention is a nuclear reactor single-rod boiling critical test device under six-degree-of-freedom motion conditions. The test device includes a single-rod test section 1, a preheating section 2, a second regulating valve 13, an orifice flowmeter 3, A test circuit composed of a stop valve 4, a heat exchanger 5 and a regulating valve 6 connected through pipelines in turn, the test circuit is placed on a two-ton six-degree-of-freedom motion platform 11, and the relevant research on the influence of ocean conditions on the critical heat flux is completed; The pipeline between the first shut-off valve 4 and the heat exchanger 5 leads to two metal hoses 7, one metal hose 7 is connected to the voltage regulator 8 through the second shut-off valve 14, and the other metal hose 7 is passed through the third The cut-off va...