JP5403308B2 - BWR or ABWR for remote control of dynamic equipment or measuring devices - Google Patents

Description

  The present invention relates to a modification of a boiling water reactor (BWR) or an improved boiling water reactor (ABWR) using light water as a coolant.

  FIG. 1 is a detailed view of the vicinity of the ABWR reactor (1). Supplemented by Non-Patent Document 2 and Non-Patent Document 3, mainly Non-Patent Document 1. The reactor pressure vessel (100) containing nuclear fuel is housed in a containment space (4) consisting of a reinforced concrete containment wall (2) lined with stainless steel and a reinforced concrete foundation (3). ing.

  A control rod housing (including a shaft for transmitting the motion of the FMCRD (6) and FMCRD (6) to the control rod (107) for precisely driving the control rod (107) at the bottom of the reactor pressure vessel (100) 7) There is. In order to drive the control rod (107) urgently, the control rod drive hydraulic system (8) is used, and water flows through the hydraulic pipe (112) in the direction of the arrow to drive the control rod (107) hydraulically.

  An internal pump motor (9) for driving an internal pump (109) for circulating water to cool the heat generated by the nuclear fuel is laid under the reactor pressure vessel (100). .

  In the containment space (4), there is a suppression pool (5) containing a large amount of water surrounded by a pool partition wall (20), which is closed during normal operation when a situation involving a lack of cooling water occurs. The emergency valve (10) is opened, the emergency core cooling pump (11) is activated, and water flows in the direction of the arrow through the emergency pipe (12) and is injected into the reactor (1). The

  The heat generated by the nuclear fuel in the nuclear reactor (1) becomes steam and goes out through the main steam pipe (13) to the turbine in the direction of the arrow. The main steam pipe (13) is laid with an open valve (14) that is open during operation. The steam that has finished work in the turbine is cooled to liquid water and returns to the reactor (1) in the direction of the arrow through the water supply pipe (15). A check valve (16) is laid in the water supply pipe (15) to prevent the water from flowing backward.

  In the upper part of the outside of the containment space (4), the spent fuel pool (18) partitioned by the wall (17) and the equipment for inspection (19) for placing equipment removed when inspecting the reactor (1) ) The spent fuel pool (18) contains water for removing heat generated from the spent fuel.

  An internal pump motor (9) that is driven by an electric motor, an open valve during operation (14) that is operated by a relay, and an emergency open valve (10) that is opened by an electric motor are called dynamic devices. ) Rotate the electric motor or operate the relay with most of the external power source led from outside, and operate the control unit of the dynamic equipment with a part of the external power source led outside from the power cable (21) Control speed adjustment, stop and start.

  The timing of operation of the control unit depends on the signal received from the outside with the signal wire (22).

  For dynamic equipment, external power is sent to the outside of the containment space (4) for the operation timing of the power supply wire (21) and the control unit for leading the external power supply from the outside of the containment space (4). Is connected to a signal wire (22) led from. In the figure, the power supply wire (21) is represented by a solid cut line and the signal wire (22) is represented by a broken broken line.

In addition, power supply wires (21) and signal wires (22) are also used in instrumentation devices that measure and monitor neutron flux, pressure, and the like.
: Nuclear Industry, 1992, Ministry of International Trade and Industry, 3rd Generation, “Improvement of Standardization and Advancement”. : Ohm, 1989, “Nuclear Handbook”. : TEPCO, 1993, “Overview of improved BWR”.

  In order to maintain and manage the reactor safely, inspection of equipment, piping, power cables and control cables is indispensable. In order to continue the inspection of a certain quality, it is necessary to keep the number of personnel with a certain quality. Now that the number of operating nuclear reactors has increased with the development of nuclear power generation, it is becoming difficult to secure personnel. There is an urgent need to simplify inspections.

  We would like to simplify many pipes and electric wires with a long and time-consuming special inspection, without any major changes to the existing BWR with extensive operational experience. In particular, we want to simplify the inspection of complicated and enormous numbers and lengths of wires.

  Dynamic equipment to be installed in the approved ABWR (for example, emergency core cooling pump (11) that receives control signals in the event of an accident and operates with an electric motor, emergency valve opening (14) that operates with a relay, or an electric motor that opens with an electric motor) Open the power supply valve (10)) and the power supply wire (21) and signal wire (22) connected to the measuring device (measure the neutron flux and pressure and contribute to accident determination). Instead, pull out the lead end (400) from the dynamic device or measurement device and connect the battery (31) and the radio with built-in battery (32) with antenna (33) near the dynamic device or measurement device. The dynamic device or the measurement device is remotely controlled via the wireless repeater (34).

  The battery includes a storage battery, an RI battery using a radioisotope, a fuel battery, a subcritical reactor generator battery (300), and a capacitor. A battery in a broad sense also means that a microwave or laser is radiated into space and received by a receiving element to serve as a power source. Microwave-based power transmission is likely to be realized from the time when solar power generation in space is considered to be sent to the earth by microwaves.

  Subcritical reactor power generator battery (300) is a subcritical reactor control rod operating rod that lays a subcritical core (51) loaded with fissionable material fuel so as not to become critical to the subcritical reactor control rod (52). (53) Adjust the degree of subcriticality by operation, continue fission with the aid of a neutron source (54) not derived from fission, generate heat, receive the heat from the heat receiving plate (63), and from the heat sink (64) A type of battery that radiates heat and converts it into electricity by a thermoelectric converter (60) that combines a p-type thermoelectric semiconductor (61) and an n-type thermoelectric semiconductor (62).

  Wireless wireless communication includes PHS, mobile phone, wireless LAN, PAN (Personal Area Network), FWA (Fixed Wireless Access), and digital broadcasting technology. PHS, which has an identification number (telephone number) exceeding 10 digits for each terminal, has a built-in battery, a built-in antenna, and a limited range of radio waves, is inexpensive and highly safe for management and operation. The possibility of realization is high when the home appliances are started to be operated by transmission from PHS.

  Remote control by batteries (31) and PHS can be applied not only to pressurized water reactors (PWR) but also to fast breeder reactors (FBR) and gas-cooled reactors. BWR or ABWR can also be applied to newly constructed reactors of other reactor types.

  A secondary suppression pool lid (210) is attached to the upper part of the equipment storage area (19) at the time of inspection, and the wall (17) is reinforced to form a pressure-resistant wall (223), and water is supplied to the equipment temporary storage sub-suppression pool (219) filled with water ( By laying a feed water communication pipe (222) with an emergency valve (10) that leads to 15), water can be injected into the reactor (1) in the event of an accident, and the emergency core cooling pump (11) has been deleted. Spent fuel sub-suppression pool (218) with a secondary suppression pool lid (210) on the upper part of the spent fuel pool (18) and a wall (17) reinforced to form a pressure-resistant wall (223) and a heater (226). By installing an emergency communication pipe (225) that leads to the emergency pipe (12), it has been modified so that water can be injected into the reactor (1) in the event of an accident, and the water in the suppression pool (5) is drained and stored In ABWR where the internal pump motor (9) is laid down and integrated with the container space (4), the internal pump motor (9 ), The penetration part of the reactor pressure vessel (100) is sealed, the internal pump (109) is removed, and it is improved to natural circulation cooling during normal operation, and it is re-used in the BWR where the recirculation pump motor and jet pump are installed. Remove the circulation pump motor and jet pump, seal the necessary parts, and refurbish to natural circulation cooling during normal operation. For the ABWR in operation, the internal pump motor (9) is not removed, but only the internal pump (109) is removed, and the natural circulation cooling is modified during normal operation.

  In the control rod drive mechanism of BWR or ABWR, coil A (501) and reverse wound coil B (502) are alternately laid in the control rod housing (7), and boron carbide (B4C) sintered plate or boron compound A permanent magnet (503) connected to the lower end of a titanium rod (128) that is connected to a lightweight control rod (127) coated with Ti on a titanium-added plate with titanium (Ti) is lightweight due to the direction of the coil current and the notch (504) The new CRD (46) is used, which is characterized by the fact that the control rod (127) can be operated in the height direction.

  If the device itself is changed or if a new part is laid and integrated in the device, it is necessary to obtain a license, and it takes a lot of time and money to obtain a new license. In addition to refurbishing existing reactors, it is necessary to obtain permission if the equipment itself is changed or new parts are laid and integrated in the equipment to newly install existing designed reactors. It takes a lot of time and money to get permission. According to the present invention, it is only necessary to permit the connection of components of the battery (31) and the battery built-in radio (32) with the antenna (33).

  The battery built-in wireless device (32) has a built-in standard battery suitable for the wireless device, so the power supply battery (31) can be independently selected from the standard suitable for the dynamic device or the measuring device. .

  Since the power supply wires (21) and signal wires (22) that can be connected to dynamic devices or measuring devices that require power and signals have been deleted, batteries connected to dynamic devices or measuring devices and their vicinity The inspection can be greatly simplified since the inspection can be completed at one location for the (31) and the battery built-in radio (32) with the antenna (33). If the battery (31) to be connected to the dynamic device or the measurement device and the radio with built-in battery (32) with antenna (33) are replaced with a pre-adjusted one, further inspection is required. It can be simplified and the cost of inspection is reduced.

  With PHS, the reach of radio waves is limited, so entry from outside the reactor facility and leakage of information to the outside are unlikely to occur and management is easy. With PHS, each terminal has an identification number of 10 digits or more and can be assigned to each device in the reactor. Inexpensive and safe for management.

There is no significant increase in inspection because the so-called second suppression pool tentative, such as the temporary storage sub-suppression pool (219) and the spent fuel sub-suppression pool (218), allows water to be injected into the reactor (1) in the event of an accident. Passive safety is increased.
Since water is drained from the conventional suppression pool (5), the containment space (4) is expanded and the pressure rise in the space at the time of the accident is suppressed.

  The removal of the internal pump motor (9) and internal pump (109) from the above-modified ABWR has increased the safety by providing passive safety, and the accompanying equipment has been reduced from the original power supply. Since the electric wire (21) and the signal wire (22) are also deleted, the cost for inspection is reduced.

  The adoption of the new FMCRD (46) not only deletes the power supply wires (21) and signal wires (22), but also deletes the water pressure piping (112) related to water pressure control, which significantly reduces the cost of inspection.

  The BWR or ABWR was improved and a BWR or ABWR with easy passive inspection and high passive safety could be provided.

  Fig. 2 is a schematic diagram of the ABWR modified for remote control. For example, if an accident occurs and the reactor (1) urgently needs to be shut down and the open valve (14) connected to the main steam pipe (13) needs to be closed, the withdrawal end from the open valve (14) during operation An accident signal is received by the radio with built-in power supply (32) with antenna (33) connected adjacent to line (400), and connected adjacent to lead-out line (400) from valve opening (14) during operation The valve (14) is closed during operation using the battery (31) to be discharged as a power source. When the device is in the containment space (4), a signal is received via the wireless repeater (34).

  As for the control rod drive mechanism, the new CRD (46), which can be inserted at high speed by improving the FMCRD (6), uses the battery (31) as a power source and sends an external control command signal via the radio repeater (34). It is received and operated by the battery built-in radio (32) via the antenna (33). Instead of the control rod (107), a lightweight control rod (127) supported by a titanium rod (128) was used to reduce the weight.

  Figure 3 is an overview of the new CRD (46). The lightweight control rod (127) was operated only up and down without relying on water pressure, and the hydraulic pipe (112) and control rod drive hydraulic system (8) were deleted. When moving the lightweight control rod (127) upward, coil B is wound in the direction opposite to coil A (501) by sucking the permanent magnet (503) connected to the lower end of the titanium rod (128) with coil A (501) In (502), the permanent magnet (503) is pushed up. When moving the lightweight control rod (127) downward, change the direction of the current. The coil A (501) and the coil B (502) are alternately arranged to make it easy to operate the lightweight control rod (127) in the height direction.

  When the lightweight control rod (127) is to be stopped at the same position for a long period of time, the notch (504) is held in place so that it comes under the permanent magnet (503), and when the lightweight control rod (127) is moved, the notch ( 504) is removed and separated from the permanent magnet (503). In the example of this figure, the notch (504) is rotated around the contact point between the control rod housing (7) and the notch (504).

  The lightweight control rod (127) is lightened and can be easily operated up and down by covering a sintered plate of boron carbide (B4C) or a plate obtained by adding a boron compound to titanium (Ti) with Ti.

  The improvement in battery performance in recent years is remarkable. There are batteries for forklift vehicle power, electric vehicle power, submarine power, emergency power unit engine start, communication and the like. A thermoelectric generator that converts the decay heat of plutonium 238 (Pu238) into electricity using a thermoelectric semiconductor can be called a battery in a broad sense. The performance improvement of fuel cells such as solid electrolyte fuel cells and molten carbonate fuel cells is also remarkable.

  In order to drive the internal pump motor (9) for a long period of time without relying on a conventional external power source, it is necessary to devise. FIG. 4 is a conceptual diagram of a subcritical reactor power generator battery (300). Adjusting the degree of subcriticality by operating the subcritical reactor control rod operating rod (53) that lays the subcritical reactor core (51) loaded with fissionable material fuel so as not to become critical to the subcritical reactor control rod (52) P-type thermoelectric semiconductor that generates heat by continuing fission with the aid of a neutron source (54) (for example, spontaneous neutrons) that is not derived from fission, and that heat is received from the heat receiving plate (63) and radiated from the heat radiating plate (64) A thermoelectric converter (60) combining (61) and an n-type thermoelectric semiconductor (62) is converted into electricity to drive the internal pump motor (9). The subcritical reactor stop rod (55) is made of a neutron absorber and makes the subcritical core (51) extremely subcritical and brings the output to almost zero. The reflector (56) is for reducing neutron leakage from the subcritical core (51) and is made of zirconium alloy, carbon or stainless steel.

  Plutonium 238 (Pu238), which is a fissile material equivalent to uranium 235 (U235) and emits spontaneous neutrons and also emits alpha (α) rays, is suitable as a fuel for the subcritical core (51). Spontaneous neutrons become neutron sources (54). If the subcritical reactor control rod (52) is beryllium (Be), fission is activated by the neutron moderation action of Be, so if the Be subcritical reactor control rod (52) is inserted into the subcritical core (51) It is close to the criticality, and many outputs can be taken out. The α ray from Pu238 reacts with Be and emits neutrons, so the output is high regardless of the degree of subcriticality.

  Pu238 is produced when neptunium (Np) absorbs neutrons. If Pu238 and Np are loaded in the subcritical core (51), Pu238 is produced from Np, so that a battery having a long life can be obtained. Examples of fissile materials that emit spontaneous neutrons and alpha rays include americium (Am) and curium (Cm).

  Figure 5 is a schematic diagram of an ABWR that has been modified to improve passive safety by modifying the current approved ABWR. The ABWR that has been modified so that it can be remotely controlled as shown in Fig. 2 was further modified.

  Microwave was transmitted by the microwave transmitter (262), and the microwave power receiver (261) was able to secure an external power supply without a power line. In addition to microwaves, lasers can secure an external power supply without wires.

  Even if the reactor is operated for a predetermined period and the end of the operation is reached and the reactor is shut down for periodic inspection, the heat generation does not immediately become zero. Heat is released from the fission products for several days. In order to drive a cooling pump for removing residual heat for a long period of time without relying on an external power source, securing a power source using microwaves is effective.

  Next, a secondary suppression pool lid (210) is attached to the upper part of the equipment storage area (19) at the time of inspection, and the wall (17) is reinforced to form a pressure-resistant wall (223). To do. In other words, the second suppression pool. A water supply communication pipe (222) leading to the water supply pipe (15) is laid therein. In the event of an accident, even if the open valve (14) during operation that is laid on the main steam pipe (13) is closed and water does not flow from the water supply pipe (15) to the reactor (1), it remains in the temporary storage sub-suppression pool (219) The water is then passed through the water supply pipe (15) by opening the emergency opening valve (10) laid in the water supply communication pipe (222), and then injected into the reactor (1).

  Further, a sub-suppression pool lid (210) is attached to the upper part of the spent fuel pool (18), and the wall (17) is reinforced to form a pressure-resistant wall (223) to form a spent fuel sub-suppression pool (218). An emergency communication pipe (225) with a check valve (16) leading to the emergency pipe (12) is laid therein. The spent fuel sub-suppression pool (218) is constantly pressurized by the heater (226), although lower than the pressure in the reactor (1). When the pressure in the reactor (1) decreases due to an accident, the water in the reactor (1) is poured into the reactor (1) through the emergency communication pipe (225). Water can be injected into the reactor (1) without the emergency core cooling pump (11). The external water injection pipe (224) can be supplied from the outside in consideration of long-term water injection. Instead of the heater (226), the pressure-resistant wall (223) may be directly heated from the outside by a microwave or laser from the microwave transmitter (262). If the pressure in the spent fuel sub-suppression pool (218) is too high, the pressure is lowered by cooling with the cold water from the external water injection pipe (224). Furthermore, if an external water injection pipe (224) is added separately and spray water is sprinkled in the upper space of the spent fuel sub-suppression pool (218), the pressure drops rapidly.

  Remove water from the suppression pool (5) and renovate it into the containment space (4).

  The internal pump motor (9) laid at the bottom of the approved ABWR reactor (1) is removed and sealed, and the internal pump (109) is also removed to provide natural circulation cooling to provide passive safety. If it is renovated, the periodic inspection will be greatly simplified.

  Even in an approved BWR that lays a recirculation pump motor and a jet pump, the recirculation pump motor is removed, the portion that can penetrate the reactor pressure vessel (100) is sealed, the jet pump is removed, and natural circulation cooling is performed during normal operation. Periodic inspections are greatly simplified if they are modified so that they are safe.

  If the nuclear reactor can be remotely controlled by batteries and radio, the wires will be greatly eliminated, and wiring inspection will be easier as well as reduced wiring work.

  The light weight control rod (127) can be fully inserted into the fuel section by natural fall, and the light weight control rod (127) can be fully pulled out from the fuel section so that it is above the fuel section. If it is a fail safe, it will be high. Since the permanent magnet (503) can be moved up and down only by adjusting the current of the coil A (501) and coil B (502), if the notch (504) is not attached, the current loss will be reduced to a lightweight control rod. (127) falls freely and is fully inserted into the fuel section, and the reactor goes to shutdown. If the new CRD (46) is laid on the top of the reactor (1), the free fall of the lightweight control rod (127) will become easier.

Figure 1 shows the details of the ABWR reactor (1) and its vicinity. Fig. 2 is a schematic diagram of the ABWR modified to allow remote control. Figure 3 is an overview of the new CRD (46). FIG. 4 is a conceptual diagram of a subcritical reactor power generator battery (300). Figure 5 is a schematic of the ABWR modified to improve passive safety.

Explanation of symbols

1 is a nuclear reactor.
2 is the containment wall.
3 is the basis.
4 is the containment space.
5 is the suppression pool.
6 is FMCRD.
7 is a control rod housing.
8 is a control rod drive hydraulic system.
9 is an internal pump motor.
10 is an emergency valve open.
11 is an emergency core cooling pump.
12 is emergency piping.
13 is the main steam pipe.
14 is open during operation.
15 is a water supply pipe.
16 is a check valve.
17 is a wall.
18 is a spent fuel pool.
19 is the equipment storage area during inspection.
20 is a pool partition.
21 is a power cable.
22 is a signal wire.
31 is a battery.
32 is a battery built-in radio.
33 is an antenna.
34 is a wireless repeater.
46 is the new CRD.
51 is a subcritical core.
52 is a subcritical reactor control rod.
53 is a subcritical furnace control rod operation rod.
54 is a neutron source.
55 is a subcritical reactor stop rod.
56 is a reflector.
60 is a thermoelectric converter.
61 is a p-type thermoelectric semiconductor.
62 is an n-type thermoelectric semiconductor.
63 is a heat receiving plate.
64 is a heat sink.
100 is a reactor pressure vessel.
107 is a control rod.
109 is an internal pump.
112 is a hydraulic pipe.
127 is a lightweight control rod.
128 is a titanium rod.
210 is the secondary suppression pool lid.
218 is a spent fuel sub-suppression pool.
219 is a temporary storage sub-suppression pool.
222 is a water supply pipe.
223 is a pressure wall.
224 is an external water injection pipe.
225 is an emergency communication pipe.
226 is a heater.
261 is a microwave receiver.
262 is a microwave transmitter.
300 is a subcritical reactor generator battery.
400 is the lead line.
501 is coil A.
502 is coil B.
503 is a permanent magnet.
504 is a notch.

Claims (3)

In BWR or ABWR controlled by an external power supply or signal-driven dynamic equipment and measurement device that has been guided by electric wires from outside the containment space,
Active components and connect both the lead-out end line (400) in the containment around the space for each active component and for each measuring device issues a battery (31) and PHS from the measuring apparatus, is in the containment space equipment BWR or ABWR, characterized in that the wirelessly repeater the active components and measurement device via a (34) to be remotely controlled. In BWR or ABWR in claim 1,
The equipment temporary storage sub-suppression pool (219) is reinforced the equipment storage place during inspection (19), the sub-suppression pool lid (210) laid on the inspection equipment storage place (19), and the wall (17). Pressure barrier (223) and
A water supply communication pipe (222) leading from the equipment temporary storage sub-suppression pool (219) to the water supply pipe (15) is laid,
Laid emergency opening (10) to the water supply communicating pipe (222), connect both the battery and the PHS out of the emergency valve opening (10) the lead-out end line (400), the radio repeater (34 BWR or ABWR characterized in that water can be injected into the reactor (1) in the event of an accident by remotely operating the valve via) . In BWR or ABWR in claim 1 or claim 2,
The spent fuel sub-suppression pool (218) has reinforced the spent fuel pool (18), the sub-suppression pool lid (210) laid on the upper part of the spent fuel pool (18), and the wall (17). It consists of a pressure wall (223) and a heater (226),
An emergency communication pipe (225) that leads to the emergency pipe (12) is installed in the spent fuel sub-suppression pool (218),
Pull out the lead end line (400 ) from the heater (226), connect both the microwave receiver (261) and the PHS, and operate the heater remotely to adjust the pressure in the spent fuel sub-suppression pool (218) normally. Operate remotely to keep it below the core pressure during operation,
BWR or ABWR characterized in that water can be injected into the reactor (1) in the event of an accident.

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