Reactor cladding material high temperature steam oxidation quenching test device and test method

Abstract

The invention belongs to the technical field of nuclear safety control and relates to a high-temperature steam oxidation quenching test device and method for a reactor cladding material. The test device comprises a steam generator, an ordinary resistance furnace, a reaction chamber, a quenching tank, a thermocouple, a hydrogen analyzer and connecting pipes, wherein high-temperature steam provided by the steam generator enters the reaction chamber through the connecting pipe; the reaction chamber is used for accommodating a sample for a high-temperature steam oxidation quenching test; the reaction chamber is heated by a common resistance furnace outside the reaction chamber; the thermocouple is installed in the reaction chamber for measuring and controlling the temperature; the quenching tank is connected to the lower part of the reaction chamber for quenching the sample falling into the water in the quenching tank; the hydrogen analyzer is connected to the reaction chamber through the connecting pipe for analyzing content of hydrogen gas generated in the reaction chamber. With adoption of the test device and method, whether the reactor cladding material meets safety criteria can be evaluated easily and efficiently with the temperature accurately controlled and at a low cost.

Description

technical field [0001] The invention belongs to the technical field of nuclear safety control, and relates to a reactor cladding material high-temperature steam oxidation quenching test device and a test method thereof. Background technique [0002] Reactor cladding is the first barrier for nuclear fuel and an important part to ensure the nuclear safety of reactors. In addition to having various physical, chemical, mechanical, corrosion and radiation properties under normal operating conditions, it should also be protected against dehydration. Under design basis accident conditions such as LOCA, it has sufficient resistance. Especially after the nuclear fuel leakage accident at the Fukushima nuclear power plant in Japan in 2011, countries re-examined the safety issues of nuclear power plants and paid more attention to evaluating the accident resistance of reactor cladding materials. [0003] The loss of water accident is a nuclear power plant design basis accident, and the ...

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Problems solved by technology

[0005] According to prior art literature [1] Y.Yan, T.A.Burtseva, M.C.Billone.High-temperature steam-oxidation behavior of Zr-1Nb cladding alloy E110-breakawayoxidation.J.Nucl.Mater.393(2009)433-448; [2 ] Ma Shuchun, Sun Yuanzhen, Chen Wangchun, et al. Research on the reaction between fuel cladding and water vapor under PWR loss of water accident conditions. Atomic Energy Science and Technology, 1993, 27(4); [3] Jun Hwan Kim, Myoung Ho Lee, Byoung Kwon Choi , et al.Embrittlement behavior of zircaloy-4 cladding during oxidation and water quench.Nuclear Engineering and Design235 (2005) 67-75 report, the existing high temperature steam oxidation quenching test device mainly adopts rapid heating such as radiation, induction or current short circuit The temperature of the sample is raised in this way, because the heating power is large, the temperature rises quickly, the rate is not easy to control, and it is easy to overheat, so the temperature controller must be carefully adjusted; the temperature drop is affected by the heat transfer performance of the furnace body, and it is not easy to adjust arbitrarily

[0006] According to prior art literature [4] Brachet J.C., Pelchat J., Hamon D., et al. Mechanical Behaviour at Room Temperature and Metallurgical Study of Low-Tin Zy-4and M5 TM (Zr-NbO)Alloys after Oxidation at 1100°C and Quenching. Proceeding on Fuel Behaviour and LOCA Conditions, 10-14Sept. 2001, IAEA, Vienna, IAEA-TECDOC-1320 report, there is also a vertical suspension of the sample, obtained by quickly lowering into the furnace Rapid heating effect, then cut off the suspension and let the sample fall into the quenching pool, but this lacks the cooling process

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