Natural circulation and forced circulation experiment loop system

Abstract

The invention discloses a natural circulation and forced circulation experiment loop system. The system includes a forced circulation loop, a natural circulation loop 1 and a natural circulation loop 2; the forced circulation loop comprises a main circulating pump, a main heat exchanger, an auxiliary heat exchanger, a coagulation device, a voltage stabilizer, a test section, a preheater, a flowmeter and corresponding pipelines, valves and measuring instruments. The forced circulation experiment branch consists of a measuring section, a preheater, an experimental body, a coagulation device, a voltage stabilizer and corresponding pipelines and valves. The natural circulation loop 1 comprises a main circulating pump, a core simulator, a steam generator, a voltage stabilizer and corresponding pipelines, valves and measuring instruments. The natural circulation loop 2 comprises a steam generator, a heat exchanger, a heat-exchange water tank and corresponding pipelines and valves. The system improves the reliability of the measures set beyond design basis accident and the diversification of the nuclear power plant safety system, and has high engineering value.

Description

technical field [0001] The invention belongs to the field of reactor thermal water conservancy, in particular to a natural circulation and forced circulation experiment loop system. Background technique [0002] The reactor can use the ability of natural circulation to export heat without relying on external power to realize the operation of the passive safety facilities of the reactor under accidents, thereby improving the safety of the reactor. [0003] Since the Fukushima incident in Japan, the international and domestic communities have put forward higher requirements for nuclear energy safety, and more and more attention has been paid to the reliability of mitigation measures for beyond-design basis accidents such as power outages and complete loss of cooling chains. . In the "General Technical Requirements for Nuclear Power Plant Improvement Actions after the Fukushima Nuclear Accident (Trial)" issued by the National Nuclear Safety Administration in June 2012, it has ...

AI Technical Summary

Problems solved by technology

[0005] The purpose of the embodiments of the present invention is to provide a natural circulation and forced circulation experimental loop system, aiming at solving the problems that the reliability of the measures set for accidents beyond the design basis is not high enough, and the diversification of the safety system of the nuclear power plant is relatively lacking.

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