JPS62198789A - Gas cooling type nuclear power plant - Google Patents

Abstract

(57) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.

Description

DETAILED DESCRIPTION OF THE INVENTION (Field of Industrial Application) The present invention relates to a gas-cooled nuclear power plant.

(Prior Art) A conventional example of a nuclear power plant using a high-temperature gas reactor, which is one type of gas-cooled nuclear reactor, will be explained with reference to FIGS. 1 to 18.
In Figure 5, (1) is the fuel exchanger, (2) is the reactor vessel, (
3) is the multiple standpipes installed above the reactor vessel (1), and (4) is the containment vessel building.

(5) is the auxiliary building, (6) is the fuel relay equipment that connects the inside of the containment vessel building (4) and the inside of the auxiliary building (5), (7)
is a fuel transfer device in the auxiliary building (5), (8) is a spent core component storage pool, and the spent core component storage pool (8) is a spent fuel storage pool (9) that stores spent fuel. ) and a movable reflector storage pool (10) for storing movable reflectors and the like. Furthermore, in Fig. 6 showing the spent core component storage pool (8), (11) is the spent fuel storage pool container, (12) is the spent fuel storage container, and (13) is the spent fuel storage pool. Storage container (12)
(14) is the supporting frame for the spent fuel storage container (1).
(2) is the shielding plug, (15) is the cooling water in the spent fuel storage pool container (11), and (16) is the movable reflector, etc. storage container in the movable reflector, etc. storage pool (lO).

(17) is a support frame for the movable reflector storage container (16).

(18) is the shielding plug of the storage container (16) for movable reflectors, etc., and the spent core components in the reactor vessel (2) are taken out through the stand pipe (3) by the fuel exchanger (1). Next, the fuel exchanger (1) is connected to the fuel relay equipment (6).
), and the spent core components are then sent to the auxiliary building (5) through the fuel relay facility (6).
Next, the fuel transfer machine (7) in the auxiliary building (5) takes out the spent core components and transfers them to a position above the spent core component storage pool (8).
The spent core components are loaded into the spent core component storage pool (8) (spent fuel storage pool (9) and movable reflector storage pool (10) ”) for storage and cooling. At this time, the spent fuel storage container (
12) is determined so that the spent fuel does not reach criticality. In addition, the spent fuel assembly is cooled with cooling water (15) so that the temperature of the spent fuel assembly does not exceed the allowable temperature due to decay heat.

Next, the purification equipment for the cooling water (15) will be explained with reference to FIG. 7. (9) is the spent fuel storage pool, (19) is the surge tank for adjusting the water level of the spent fuel storage pool (9), (20) ) are two circulation pumps, (21) are two coolers, and (22) are two purifiers that circulate the cooling water (15) in the spent fuel storage pool (9) to the above system. .

Cooling water (15) in the spent fuel storage pool (9) is maintained at a predetermined temperature or lower to cool the spent fuel bodies in the spent fuel storage container (12) so as not to exceed a permissible temperature.

Next, the cooling equipment for the reactor vessel (2) is installed as shown in Figures 8 to 1.
To explain with reference to Figure 8, (24) in Figure 8 is the water-cooled panel on the upper head plate side of the reactor vessel (2), (25) is the water-cooled panel on the side side of the reactor vessel (2), and (26) is the reactor side water-cooled panel. The radiated heat of the reactor vessel (2) and the residual heat of the reactor core are transferred to the water-cooled panel on the lower head side of the vessel (2) by the water-cooled panel on the upper head side (2).
4), the side water-cooled panel (25), and the lower end plate-side water-cooled panel (26).

The above upper end plate side water cooling panel (24) is
As shown in Figure 1, it is composed of a cooling pipe (28) passing between the stand vibes (3), a support beam (29), a heat insulating material (30), a cooling water header (31), etc.

Supported by an upper shielding concrete wall. There are multiple cooling water headers (31) per system.

Cooling pipes (28) connected to each cooling water header (31)
) are arranged so as not to cross each other, and each system has the same heat removal performance. Above side water cooling panel (
25), cooling pipes (
32), a support beam (33), a heat insulator (34), a cooling water header (35), etc., and is supported by a side shielding concrete wall. The same side water cooling panel (25) is divided into a plurality of parts in the axial direction and the circumferential direction in consideration of manufacturing, installation, and transportation. In addition, the lower end plate side water cooling panel (26) is arranged inside the support skirt (36) as shown in Fig. 15.16. and cooling water header (40
), supported by a bottom shielding concrete wall. There are multiple cooling water headers (40) per system, and the cooling pipes (37) connected to each cooling water header (40) are arranged so as not to cross each other, and each system is the same. It has heat removal performance.

Next, each water cooling panel (24) (25) (26)
The cooling water supply system that supplies cooling water to the reactor vessel (2) is explained using Fig. 18. (24) is the water cooling panel on the upper head plate side of the reactor vessel (2), (25) is the water cooling panel on the side side of the reactor vessel (2). panel, (26) is the water-cooled panel on the lower end plate side of the reactor vessel (2), (41) is each of the above water-cooled panels (24) to
(26) is a hold-up tank that constantly stores cooling water to be supplied to (42), two circulation pumps, (4)
3) is a cooler having a water-water heat exchange function; (44) is a cooling water holding tank that supplies cooling water to the hold up tank (41) when the water level in the hold up tank (41) decreases; (45) is the same cooling water holding tank (
44) The cooling water in the above hold up tank (41)
The make-up water pump supplies cooling water to each of the water-cooled panels (24) to (26), and the dissipated heat of the reactor vessel (2) and the residual heat of the reactor core are transferred to the upper head side water-cooled panel. panel(
24), the side water-cooled panel (25), and the lower end plate-side water-cooled panel (26).

(Problems to be Solved by the Invention) In the gas-cooled nuclear power plant shown in FIGS. 5 to 18, the system for the spent core component storage pool and the cooling system for the reactor vessel are independent from each other. In particular, the system for the spent core component storage pool requires a very large installation area, which poses the problem of increasing the size of the building and increasing equipment costs.

(Means for Solving the Problems) The present invention addresses the above-mentioned problems by installing a reactor vessel in a containment chamber, and forming a cooling water holding pool surrounding the reactor vessel in the containment chamber. death.

This relates to a gas-cooled nuclear power plant characterized by installing a core component storage vessel for storing core components in the cooling water holding pool, and its purpose is to reduce the size of the building and reduce equipment costs. The object of the present invention is to provide an improved gas-cooled nuclear power plant that can reduce the

(Function) As described above, the gas-cooled nuclear power plant of the present invention has a reactor vessel installed in the containment chamber, a cooling water holding pool surrounding the reactor vessel within the containment room, and a cooling water holding pool formed in the containment room surrounding the reactor vessel. A core component storage container is installed inside the containment chamber to store the core components, and spent core components are stored in the core component storage container in the same containment room (inside the cooling water holding pool).

There is no need for a core component storage container in the auxiliary building, and the only building required is the containment vessel building, making the building more compact and reducing equipment costs.

(Embodiment) Next, the gas-cooled nuclear power plant of the present invention will be explained using an embodiment shown in FIGS. 1 to 4.

In Figure 1.2.3, (50) is the containment room that stores the reactor vessel, (51) is the spent core component storage pool and reactor vessel cooling pool, and the pool (51) is the inner vessel (51).
2) and an outer container (53). The reason why the pool (51) is made double is that even if the inner container (52) is damaged, the outer container (53) receives the cooling water and prevents it from flowing out. Further, inside the inner vessel (52), there is a reactor vessel (54).
are arranged, and a plurality of core component storage containers (55) are arranged in the circumferential direction inside the inner container (52),
It is supported by a support plate (56). In addition, (57) is a reinforcing ring attached to the inner circumferential surface of the outer vessel (53) on the reactor vessel side, and (60) is a header installed on the upper part of the containment chamber (50) in which the reactor vessel (54) is stored. , (58) is an upper end plate side cooling water panel, and (59) is a lower end plate side cooling water panel, and each of the cooling water panels (5B) and (59) is constructed in the same manner as the conventional one. Further, (61) is a shielding plug provided at the upper part of the core component storage container (55). Also, (62) in Figure 4 is the cooling tower.
) has the function of cooling the heated bones of the cooling water whose temperature has increased due to the dissipated heat of the reactor vessel (54), the radiant heat due to the residual heat of the reactor core, and the heat possessed by the spent core components. Also, (63) is two purifiers, (64) is two purifiers, and (64) is two purifiers.
The main circulation pump, (65) is the holding water tank, (66
) are the two make-up water pumps, and (67) is the holding water tank, whose valves open only when all power is lost.

The evaporated cooling water is supplied from the holding water tank (67) to the cooling water circulation system. In this embodiment, the spent core component storage pool and reactor vessel cooling pool (51) has a double structure.

A multiplex structure of three or more layers may be used.

(Effects of the Invention) As described above, the gas-cooled nuclear power plant of the present invention has a reactor vessel installed in the containment chamber, a cooling water holding pool surrounding the reactor vessel in the containment chamber, and a cooling water holding pool formed in the containment chamber. A core component storage container for storing core components is installed in the holding pool, and spent core components are stored in the core component storage container in the same containment room (inside the cooling water holding pool).

There is no need for a core component storage container installed in the auxiliary building, and the only building required is the containment vessel building, making it possible to downsize the building and reduce equipment costs.

[Brief explanation of drawings]

FIG. 1 is a longitudinal sectional side view showing an embodiment of a gas-cooled nuclear power plant according to the present invention, and FIG. 2 is a view taken along arrow m-n in FIG.
3 is a longitudinal sectional side view taken along the line shown by the arrows ■-■ in FIG. 2; FIG. 4 is a system diagram showing the cooling water supply system;
Figure 5 is a longitudinal side view showing a conventional gas-cooled nuclear power plant, Figure 6 is an explanatory diagram showing the core component storage vessel pool in the auxiliary building, and Figure 7 is the flow of cooling water to the core component storage vessel pool. A system diagram showing the supply system, Fig. 8 is a side view showing the cooling water panel around the reactor vessel, Fig. 9 is a cross-sectional plan view taken along the arrow IX-IX line in Fig. 8, and Fig. 10 is the FIG. 11 is a longitudinal cross-sectional side view taken along the line XI-XI in FIG. 10, FIG. 12 is a cross-sectional plan view taken along the line Its enlarged plan view, FIG. 14 is a longitudinal sectional side view taken along the arrow line XIV-XIV in FIG. 13,
15 is a cross-sectional plan view taken along the line XV-XV in FIG. 8, FIG. 16 is an enlarged plan view thereof, and FIG. 17 is a longitudinal side view taken along the line X--X in FIG. 16. , FIG. 18 is a system diagram showing a cooling water supply system to the cooling water panel. (50)...Storage room, (51)...Cooling water holding pool. (54)...Reactor vessel, (55)...Core component storage vessel. Sub-Agent Patent Attorney Okamoto List of 2 Non-Important Literature 1 Figure 2 Figure 3 Figure 9 Figure 15

Claims (1)

[Claims] A reactor vessel was installed in the containment room, a cooling water holding pool was formed surrounding the reactor vessel within the containment room, and a core component storage vessel was installed to store the core components within the cooling water holding pool. A gas-cooled nuclear power plant characterized by: