Cold pool flow channel capable of effectively improving safety of pool type lead-cooled fast reactor

Abstract

The invention provides a cold pool flow channel capable of effectively improving the safety of a pool type lead-cooled fast reactor. The cold pool flow channel is realized by mainly depending on a cold pool secondary partition hole plate. The cold pool secondary partition hole plate comprises a horizontal section hole plate and a vertical section hole plate, and the thickness of the cold pool secondary partition hole plate is the same as that of a heat partition plate. Holes are formed in the horizontal section, so that retention of a lead cooling agent by the secondary partition hole plate can be avoided when a free liquid level drops. Open holes for adjusting the hole plate at the outlet position of the vertical section are circumferentially distributed, so that lead flows upwards uniformly, more lead in the cold pool takes part in whole flow, the thermal inertia safety advantage of the lead pool is exerted to a great extent, and the passive safety performance of the lead-cooled fastreactor is further improved. When a notch occurs in a heat exchange tube of a main heat exchanger, the new cold pool flow channel design enables the cold pool to have more time to perform gas liquidseparation, so that the quantity of water vapor which is entrained by the lead to enter the reactor core is reduced to a great extent and introduction of excessive positive reactivity is avoided. Thecold pool flow channel has one structure and multiple safety functions, simplifies the systematic design of the lead-cooled fast reactor, and can effectively improve the safety and the economic property of the lead-cooled fast reactor.

Description

technical field [0001] The invention belongs to the technical field of lead-cooled fast reactor design, and specifically relates to a cold pool flow channel that can effectively improve the safety of a pool-type lead-cooled fast reactor. The passive safety of the lead-cooled fast reactor ensures the safety of the lead-cooled fast reactor in accident conditions (especially after the break of the heat exchange tube of the main heat exchanger occurs). Background technique [0002] As one of the six typical reactor types of the fourth-generation nuclear energy system, the lead-cooled fast reactor is one of the main hotspots of international advanced nuclear energy system research due to its outstanding advantages in safety and economy. Moreover, the lead-cooled fast reactor was selected as the most promising Generation IV reactor type in the 2013 Generation IV Nuclear Energy System Forum Update Roadmap. Lead-cooled fast reactors usually adopt a pool arrangement, and the key equ...

AI Technical Summary

Problems solved by technology

After the high-pressure water or high-pressure water vapor of the secondary circuit enters the primary circuit, it will depressurize and heat up and turn into a gaseous state. It may be entrained by the lead coolant and enter the core through the main pump (forced circulation lead-cooled fast reactor), introducing positive reactivity to the core. leading to accidents

[0006] Another performance defect of the cold pool structure in the typical scheme of the pool type lead-cooled fast reactor is that the flow of the lead coolant from the outlet of the heat exchanger to the inlet of the core is not affected by the components of the cold pool, and the flow from the heat exchanger The distance from the primary outlet to the core inlet is very short, so the coolant flow in the cold pool is limited to a small area from the heat exchanger outlet to the core inlet

In other words, the thermal inertia corresponding to the amount of lead in the primary circuit cannot be effectively utilized, which will be very detrimental to the safety of lead-cooled fast reactors

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