Specifics of RBMK reactors

Подпись: 5 Fig. 1. Simplified RBMK-1500 heat flow diagram: 1 - graphite moderator; 2 - fuel channel; 3 - control rod; 4 - Drum Separator (DS); 5 - turbine; 6 - generator; 7 - condenser; 8 - condensate pump; 9 - deaerator; 10 - feedwater pump; 11 - main circulation pump

A simplified heat flow diagram of RBMK reactor is provided in Figure 1 [1]. The reactor cooling water, as it passes through the core, is subjected to boiling in the fuel channels (2) and is partially evaporated. The steam-water mixture then continues to the large drum separator (3), the elevation of which is greater than that of the reactor. The water settles there, while the steam proceeds to the turbines (5). The remaining steam beyond the turbines is condensed in the condenser (7), and the condensate is supplied by the condensate pumps (8) into the deaerator (9). Deaerated water is returned by the feed pump (10) to the drum separator (4). The coolant mixture is returned by the main circulation pumps (11) to the core, where a part of it is again converted to steam. The reactor power is controlled using control rods (3).

This fundamental heat cycle is identical to the Boiling Water Reactor cycle, extensively used throughout the world, and is analogous to the cycle of thermal generating stations. However, compared to BWRs used in Western power plants, the RBMK-1500 and RBMK — 1000 have a number of unique features. The comparison of most important parameters of the reactor is presented in Table 1. As it is seen from the presented table, the values of specific power per fuel quantity are very similar for all reactors. The value of power per fuel rod length is the highest for RBMK-1500 reactor. To reach such high value, additional specifically designed spacers, which operate like turbulence enhancers to improve the heat transfer characteristics, are mounted in the fuel assemblies of RBMK-1500. Specific power per core volume in RBMK-1500 is higher than in RBMK-1000 reactor, but in BWR-type reactors this characteristic is approximately 10 times higher.

No.

Parameter

BWR*

RBMK-1000

RBMK-1500

1.

Thermal power, MW

3800

3840

4800

2.

Core diameter m

5.01

11.80

11.80

3.

Core height, m

3.81

7.0

7.0

4.

Core volume, m3

75

765

765

5.

Mean specific power per core volume, MW/m3

51

5.02

6.27

6.

Mean specific power per fuel quantity, MW/t

24.6

20.8

26.0

7.

Mean power per fuel rod length, kW/m

19.0

18.3

22.9

* General Electric design

Table 1. Comparison of BWR and RBMK reactor parameters

In RBMK-type reactors a part of Reactor Cooling System (RCS) above the reactor core is located outside the leaktight compartments. In the RBMK reactors design, these compartments are called Accident Localization System (ALS). This is different from the typical PWR or BWR plants, which have full containment [1]. The Drum Separators (DS) and a part of downcomers are contained in the DS compartments, which are connected to the reactor hall. Such compartments are not as strong as the leaktight compartments of ALS.