Safety analysis calculating device for transient nuclear heat coupling of supercritical water reactor

Abstract

The invention discloses a safety analysis calculating device for transient nuclear heat coupling of a supercritical water reactor, and belongs to the field of nuclear power plant design and reactor safety analysis. The safety analysis calculating device for transient nuclear heat coupling of the supercritical water reactor is applicable to the supercritical water reactor. According to the safety analysis calculating device, a transient physical analysis program is built by using the space-time disperse solution of a double-group space-time kinetic equation, a transient heat engineering analysis program is built through calculation of flow distribution among channels and the solution of flowing heat exchange inside the channels, on this basis, a physical calculation program is embedded into a transient system analysis program to build a supercritical transient coupling analysis program so as to analyze safety of a system. Particularly, due to the fact that a space-time kinetics quasi-static solution model built through the double-group neutron space-time kinetic equation is combined with a multi-channel analysis method, compared with a sub-channel model, the calculation time is shortened on the basis that precision is ensured, then economy of the supercritical water reactor design is improved, and the safety analysis calculating device accords with the development trend of safety analysis.

Description

technical field [0001] The invention relates to the field of nuclear power plant design and reactor safety analysis, in particular to a safety analysis method and device for supercritical water reactor transient nuclear heat coupling. Background technique [0002] The supercritical water reactor is one of the six types of reactors selected by GIF (Generation IV International Nuclear Energy Forum) as a long-term development goal at the International Symposium on the Fourth Generation Nuclear Energy System, and it is also the only selected light water reactor type. After absorbing the heat of nuclear fission, the circulating working fluid directly enters the steam turbine to do work, so as to realize the transformation process from nuclear energy to thermal energy, and then to power energy. In order to ensure the safe conversion of nuclear energy and fluid kinetic energy into kinetic energy, the energy conversion and flow heat transfer inside the core are very critical, and t...

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Problems solved by technology

[0008] Among the above methods, the Monte Carlo calculation model has powerful geometric processing functions and the application of the continuous energy neutron section library, but the main reason affecting its wide application is its long calculation time and low efficiency

Although the calculation of the sub-channel model is accurate, it also has the problems of long calculation time and too complicated program.

Although the single-channel calculation model has a simple program and high calculation speed, its calculation accuracy is lacking, which makes the safety analysis method and device for supercritical water reactor transient nuclear thermal coupling still lacking.

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