SU1311499A1 - Steam disposal system of double-flow atomic power station - Google Patents

Description

(46) 06/15/88. Bnsh. No. 22

(21) 3943202 / 24-23

(22) 07/09/85

(72) B. K. Maltsev, M. L. Marmer Wilner, A. M. Bukrinsky, G.N. Nozdrii, V.P. Tatarnikov, G.V. Zotov, A.A. Sverdlov, G.G. Bessapov and G.M. Polu Novic, (53) 621.039.5 (088.8)

(56) Patent of France No. 2276665, cl. G 21 D 3 / OA, 1976.

Patent of Germany No. 2430724, cl. G 21 D 3/04, 1977. (54) SYSTEM OF RESET OF A PAIR OF A TWO-CURRENT ATATIC ELECTRIC POWER STATION

(57) The invention relates to nuclear steam supply installations of double-circuit nuclear power plants (NPP). The aim of the invention is to improve the safety of a nuclear power plant by preventing the possibility of radioactive steam being released into the atmosphere. The steam exhaust system of a two-circuit NPP contains a steam generating unit 1 located inside the shell 2, including the main steam line 3, passing the pass through the protective shell 2 equipped with steam activity sensors 4, a waste steam line

5 connected to the main steam line 3 via safety devices 6. Shut-off valves 7 are installed on the waste steam line 5 behind safety devices 6, and the bypass steam line 8 is connected to the steam line 5 between devices 6 and shut-off valves 7, communicated with TipptTpaHCTBOM inside the shell 2 and shut off membrane 9. When the pressure rises in the steam line 3, the membrane 9 is ruptured, the burst pressure of which is less than the response pressure of the devices 6, and the radioactive medium enters through the steam line 8 inside the shell 2. When the pressure rises The connections in the steam line 3, which is not accompanied by an increase in activity according to the sensors 4, which are electrically connected to the shut-off valves 11 7, remain open and the steam is released from the steam line 3 to the atmosphere. In this case, the membrane 9 is not destroyed, since the pressure of its rupture is higher than the total hydraulic resistance of the section of the steam line 5 and the open shut-off valves 7. 1 sludge.

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The designation refers to nuclear steam power plants of double-circuit nuclear power plants (NPP).

The aim of the invention is to increase the safety of nuclear power plants due to the possibility of the release of radioactive steam into the atmosphere,

The drawing shows schematically a system for resetting steam at a double-circuit NPP.

The steam exhaust system of a two-circuit NPP contains a steam-generating installation 1, which has been mouthed inside the protective sheath 2, including the main steam line 3, passing through the power supply sheath 2 and equipped with sensors (steam switchboard, waste steam line 3 connected to the main steam line 3 through safety devices 6, shut-off valves 7 installed on the waste steam line 5 behind the safety devices 6, and the bypass steam line 8 connected to the waste steam line 5 between the safety devices 6 and Otce4HMMri K apani 7, wherein the bypass steam pipe 8 communicates with the space inside the shell 2 and zashtnoy plugged 9 ,, membrane rupture pressure is less than the cracking pressure;. 1edohranitelnyh ustroyst 6. Shutoff valves 7 are electrically connected (not shown) with a pair of sensors A activity.

The system works as follows

When the flow of the flow from the primary circuit Yo / mountain, which is formed, for example, by the magnitude of the activity of the steam line 3, closes the shut-off valves 7. : Overlapped t rtaBHb pa1e duct 3 The pressure in the latter increases, and when the pressure increases, open the safety devices 6, Since the burst pressure of the membrane 9 is lower than the opening pressure of the safety devices 6, the membrane 9 is broken, and the radioactive medium flows through the bypass steam line 8 into the inside sheath 2 When the pressure in the main steam line -3 is reduced, the safety devices 6 are automatically matched. In this case, it remains possible to conduct adjustable cooling down) 1 nuclear steam leakage generator by sbr (1gl bet, per oo14992).

The tube 2 through the ruptured membrane 9, the overflow steam line 8 and one of the safety devices 6, if it is adapted for this purpose, for example, is a fast-acting reduction device. When the pressure in the main steam line 3 rises above the actuation value of the safety devices 6, but is not accompanied by an increase in activity according to the data of sensors A, i.e. in the absence of a leak from the first circuit to the second, the shut-off valves 7 remain open and the steam discharge from

5 main steam piping 3 is implemented with the atmosphere. At this time, the membrane 9 is not destroyed, since the pressure of its rupture is significantly higher than the total hydraulic resistance

0 of the section of the waste steam pipe 5 (from the point of connection of the bypass steam pipe 8 to the exhaust into the atmosphere) and open shut-off valves 7. It is possible that the safety devices 6 are placed inside the containment shell 2.

The use of the invention will improve the safety of a nuclear power plant by preventing the release into the atmosphere of a radioactive environment when the pressure in the steam generator increases above the actuation pressure of safety devices associated with the leak between the first and second circuits,

five .

Claims (1)

Invention Formula Dual circuit steam discharge system a nuclear power plant comprising a Q located inside the containment of a steam generating plant including a main steam line passing through. through the protection of the shell and equipped with steam activity sensors, waste f steam pipe connected through safety devices to the main steam line, characterized in that, in order to increase the safety of the power plant by preventing the release of radioactive steam into the atmosphere, cut-off valves are introduced into it) installed on the waste steam pipe for the safety ycrpoiicTRaMH and bypass steam line, half connected to the waste steam line between the safety valve uTTpoiknpnhiH and shut-off valves, more than jupPiV -knoi steampoiuui. co -pon r ;;; -. (The vipancTDOM inside the containment shell is plugged with a membrane whose bursting pressure is lower than the response pressure of the environmental safety devices, but greater than the pressure behind the safety devices when they are triggered when the shut-off valves are open, while the shut-off valves are electrically connected to the steam activity sensors of the main steam line.