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Three-loop reactor coolant system suitable for ultra-large pressurized water reactor

A coolant system and reactor technology, applied in the direction of reactors, cooling devices, and reduction of greenhouse gases, can solve the problems of high design, manufacture, and production costs of ultra-large pressurized water reactors, high design, manufacture, and production costs, and achieve manufacturing costs Low cost, lower cost, and simplified system design

Inactive Publication Date: 2020-08-07
NUCLEAR POWER INSTITUTE OF CHINA
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

When we design and upgrade steam generators and reactor pressure vessels to ultra-large pressurized water reactor nuclear power units, we face the need to redesign the reactor coolant pumps with corresponding matching parameters; therefore, the design, manufacture, and production costs of new reactor coolant pumps are very high , making the design, manufacture, and production costs of the entire ultra-large pressurized water reactor too high

Method used

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  • Three-loop reactor coolant system suitable for ultra-large pressurized water reactor

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Embodiment 1

[0029] Such as figure 1 Shown:

[0030] A three-loop reactor coolant system suitable for super-large PWRs, including three heat transfer loops connected to the reactor pressure vessel (000BA); figure 1 Among them, the three heat transfer loops include the first heat transfer loop, the second heat transfer loop, and the third heat transfer loop;

[0031] Each heat transfer loop includes a steam generator and two reactor coolant main pumps. The suction ports of the two reactor coolant main pumps in each heat transfer loop and the corresponding steam generators in the heat transfer loop The outlet water chamber of the primary side of the reactor is connected, and the discharge outlets of the two reactor coolant main pumps are connected to the cold section return water interface of the reactor pressure vessel 000BA. The primary inlet water chamber of the steam generator in each heat transfer loop is connected to The hot section drainage interface of the reactor pressure vessel 000BA ...

Embodiment 2

[0035] On the basis of the above-mentioned embodiment, preferably, a further implementation structure is: since each heat transfer loop is provided with two reactor coolant main pumps, it means that there are two cold sections. Therefore, for the present invention The capacity of the reactor coolant main pump does not need to be too large for the ultra-large pressurized water reactor nuclear power unit, and the current mature main pump design and manufacturing technology of the million-kilowatt nuclear power unit can be fully utilized; therefore, the optimal heat transfer loop The two reactor coolant main pumps adopt the mature main pumps of mega-kilowatt nuclear power generating units.

Embodiment 3

[0037] On the basis of the above-mentioned embodiment, preferably, a further implementation structure is: In order to be more beneficial to the safety of the reactor, the reactor pressure vessel 000BA corresponds to the six cold section return ports of the three heat transfer loops at the same water level B, The reactor pressure vessel 000BA corresponds to the three hot section drainage interfaces of the three heat transfer loops at the same water level A, where the water level A is higher than the water level B.

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Abstract

The invention discloses a three-loop reactor coolant system suitable for an ultra-large pressurized water reactor. The three-loop reactor coolant system comprises three heat transfer loops connected to a reactor pressure vessel, each heat transfer loop comprises a steam generator and two reactor coolant main pumps, suction inlets of the two reactor coolant main pumps in each heat transfer loop areconnected with a primary side outlet water chamber of the steam generator in the corresponding heat transfer loop, discharge outlets of the two reactor coolant main pumps are connected with a cold section water return connector of a reactor pressure vessel (000BA), and a primary side inlet water chamber of the steam generator in each heat transfer loop is connected with a hot section drainage interface of a reactor pressure vessel (000BA). Each heat transfer loop comprises the steam generator and the two reactor coolant main pumps, so that one loop is constructed with one outlet and two inlets, and three outlets and six inlets are formed in total. Compared with a four-series safety system corresponding to four loops, the system of the invention obviously reduces the cost of the nuclear power unit and improves the economy.

Description

Technical field [0001] The invention relates to the design of a reactor coolant system in the direction of an ultra-large pressurized water reactor, in particular to a three-loop reactor coolant system suitable for an ultra-large pressurized water reactor. Background technique [0002] At present, the reactor coolant system of ultra-large PWR nuclear power plants (such as EPR and N4 nuclear power plants in France) generally adopts four coolant loop designs in the world. Each coolant loop is equipped with a steam generator and a reactor coolant pump, and the reactor pressure vessel is designed as "four out and four in". [0003] The nuclear power plants in service and under construction in my country are mainly one million kilowatts and six hundred thousand kilowatts, and most of the reactor coolant loops are three loops and two loops. Each coolant is equipped with a steam generator and a reactor coolant pump, and the reactor pressure vessel is designed to be "three out and three i...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21C15/12G21C15/14
CPCG21C15/12G21C15/14Y02E30/30
Inventor 赵禹任云崔怀明胡幼明刘向红赖建永苏荣福余小权
Owner NUCLEAR POWER INSTITUTE OF CHINA