WO2010119840A1 - 原子炉 - Google Patents
原子炉 Download PDFInfo
- Publication number
- WO2010119840A1 WO2010119840A1 PCT/JP2010/056528 JP2010056528W WO2010119840A1 WO 2010119840 A1 WO2010119840 A1 WO 2010119840A1 JP 2010056528 W JP2010056528 W JP 2010056528W WO 2010119840 A1 WO2010119840 A1 WO 2010119840A1
- Authority
- WO
- WIPO (PCT)
- Prior art keywords
- reactor
- nuclear
- primary coolant
- fuel
- concentration
- Prior art date
Links
Images
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
- G21C7/06—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
- G21C7/02—Control of nuclear reaction by using self-regulating properties of reactor materials, e.g. Doppler effect
- G21C7/04—Control of nuclear reaction by using self-regulating properties of reactor materials, e.g. Doppler effect of burnable poisons
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
- G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
- G21C3/326—Bundles of parallel pin-, rod-, or tube-shaped fuel elements comprising fuel elements of different composition; comprising, in addition to the fuel elements, other pin-, rod-, or tube-shaped elements, e.g. control rods, grid support rods, fertile rods, poison rods or dummy rods
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
- G21C7/06—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
- G21C7/08—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of solid control elements, e.g. control rods
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
- G21C7/06—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
- G21C7/08—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of solid control elements, e.g. control rods
- G21C7/10—Construction of control elements
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
- G21C7/06—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
- G21C7/22—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of a fluid or fluent neutron-absorbing material, e.g. by adding neutron-absorbing material to the coolant
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/28—Arrangements for introducing fluent material into the reactor core; Arrangements for removing fluent material from the reactor core
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Definitions
- the present invention relates to a nuclear reactor that can reduce environmental load.
- a nuclear reactor obtains thermal energy by nuclear reaction of nuclear fuel.
- Some nuclear reactors adjust the reactivity of the nuclear reactor by adding boron as a neutron absorber to the coolant (for example, Patent Document 1).
- the present invention has been made in view of the above, and an object of the present invention is to provide a nuclear reactor capable of reducing the environmental load.
- the present invention provides a nuclear reactor having a fuel rod in which nuclear fuel is sealed and a control rod for controlling a nuclear reaction of the nuclear fuel, and starts the operation of the nuclear reactor.
- This is a nuclear reactor characterized by As a result, the amount of neutron absorbing material added to the primary coolant during operation of the nuclear reactor can be reduced, thereby reducing the environmental burden.
- a burnable poison is added to the fuel constituting the fuel rod, and the concentration of the burnable poison on at least one end side of the fuel rod is more than The concentration of the burnable poison in the central portion of the fuel rod is preferably high.
- the control rod has a reactivity control capability capable of cold-stopping the operating nuclear reactor without introducing a neutron absorber into the primary coolant. It is preferable to have.
- the primary coolant is water
- a hydrogen to heavy metal atomic ratio in the nuclear reactor is 4.5 or more
- boron is added to the primary coolant. If not, it is preferably not more than a value that maximizes the nuclear reactivity of the core.
- the present invention provides a burnable in a nuclear fuel in a nuclear reactor having a fuel rod sealed with nuclear fuel and a control rod for controlling a nuclear reaction of the nuclear fuel.
- a nuclear reactor characterized by adding a poison and having a concentration of the burnable poison in a central portion of the fuel rod higher than a concentration of the burnable poison on at least one end side of the fuel rod.
- the present invention provides a nuclear reactor having a fuel rod in which nuclear fuel is sealed and a control rod for controlling a nuclear reaction of the nuclear fuel, wherein the control rod is It is a nuclear reactor characterized by having a reactivity control capability capable of cold-stopping the operating nuclear reactor without introducing boron into the primary coolant.
- the reactor can be shut down at a low temperature only by the reactivity control ability of the control rod, so that it is not necessary to add a neutron absorber to the primary coolant during the cold shutdown operation of the reactor.
- the amount of neutron absorbing material added to the primary coolant can be reduced, so that the environmental load can be reduced.
- the present invention includes a fuel rod in which nuclear fuel is sealed and a control rod for controlling the nuclear reaction of the nuclear fuel, and the primary coolant is an atom using water.
- the atomic ratio of hydrogen to heavy metal is 4.5 or more and not more than a value that maximizes the nuclear reactivity of the core when boron is not added to the primary coolant. It is a furnace. Increasing the hydrogen to heavy metal atom ratio can reduce the addition reactivity when the reactor is cooled.
- the present invention can provide a nuclear reactor that can reduce the environmental load.
- FIG. 1 is a schematic diagram showing a nuclear power plant.
- FIG. 2 is a diagram showing a breakdown of the reactivity control of the nuclear reactor.
- FIG. 3A is a schematic diagram showing the concentration of burnable poison in the fuel rod.
- FIG. 3-2 is a schematic diagram showing the concentration of burnable poison in the fuel rod.
- Figure 4 shows the primary coolant during rated power operation from the BOC (Beginning Of Cycle) at the time of reactor shim control to EOC (End Of Cycle: at the end of reactor operation). It is a schematic diagram which shows the change of the boron concentration in it.
- FIG. 5 is a diagram illustrating an example of improving the reactivity control ability of the control rod.
- FIG. 1 is a schematic diagram showing a nuclear power plant.
- FIG. 2 is a diagram showing a breakdown of the reactivity control of the nuclear reactor.
- FIG. 3A is a schematic diagram showing the concentration of burnable poison in the fuel rod.
- FIG. 3-2 is a schematic
- FIG. 6 is a diagram illustrating an example of improving the reactivity control ability of the control rod.
- FIG. 7 is a diagram illustrating an example of improving the reactivity control ability of the control rod.
- FIG. 8 is a diagram showing the relationship between the effective multiplication factor and the primary coolant density.
- FIG. 9 is a diagram showing the relationship between the effective multiplication factor and the hydrogen to heavy metal atom number ratio H / HM.
- FIG. 10 is a diagram showing the relationship between the effective multiplication factor and the hydrogen to heavy metal atom number ratio H / HM.
- FIG. 11 is a diagram showing the arrangement pitch of the fuel rods.
- FIG. 1 is a schematic diagram showing a nuclear power plant.
- the nuclear power plant 1 is a nuclear power generation facility.
- the nuclear reactor 2 constituting the nuclear power plant 1 is a PWR (Pressurized Water Reactor).
- a nuclear reactor 2 constituting the nuclear power plant 1 is a PWR (Pressurized Water Reactor).
- a nuclear reactor 2 a nuclear reactor 2, a steam generator 3, a pressurizer 4, a primary coolant pump 5, and a regenerative heat exchanger 11 are disposed in a containment vessel 1W.
- the turbine 8, the condenser 9, and the generator 10 are arrange
- the fuel portion 2C is disposed inside the pressure vessel 2P. Further, the pressure vessel 2P is filled with a primary coolant C1 (corresponding to cooling water, and light water is used in the present embodiment).
- the primary coolant pump 5 and the nuclear reactor 2 are connected by a primary coolant first supply passage 6A, and the nuclear reactor 2 and the steam generator 3 are connected by a primary coolant second supply passage 6B.
- the steam generator 3 and the primary coolant pump 5 are connected by a primary coolant recovery passage 6C.
- the primary coolant C1 discharged from the primary coolant pump 5 is supplied into the pressure vessel 2P of the reactor 2 through the primary coolant first supply passage 6A. Then, the primary coolant (light water in this embodiment) C1 is heated by the thermal energy generated by the fission reaction of the fuel (nuclear fuel) constituting the fuel portion 2C disposed inside the pressure vessel 2P.
- the fuel nuclear fuel
- uranium and plutonium as nuclear fuel constituting the fuel assembly release fission
- light water functioning as a moderator and primary cooling water reduces the kinetic energy of the released fast neutrons to reduce thermal neutrons.
- the heat generated by nuclear fission is taken away and cooled.
- the fuel portion 2C is configured by bundling a plurality of fuel rods each having a plurality of fuel pellets sealed in a cladding tube to form a fuel assembly, and arranging the plurality of fuel assemblies.
- the core is constituted by the fuel portion 2C and the primary coolant present around the fuel portion 2C.
- the primary coolant C1 heated by the thermal energy generated by the fuel fission reaction is supplied to the steam generator 3 through the primary coolant second supply passage 6B. Then, after passing through the heat transfer tube 3T of the steam generator 3, the primary coolant C1 flows out of the steam generator 3, returns to the primary coolant pump 5 through the primary coolant recovery passage 6C, and again returns to the primary coolant.
- the gas is discharged from the first supply passage 6A into the pressure vessel 2P of the nuclear reactor 2.
- a plurality of control rods 2L are arranged.
- the control rod 2L is driven by the control rod drive device 2A.
- the control rod driving device 2A controls the nuclear fission of the fuel constituting the fuel portion 2C by inserting or withdrawing the control rod 2L from the fuel portion 2C.
- the number of neutrons generated in the core is adjusted by inserting the control rod 2L into the fuel portion 2C.
- the steam generator 3 includes a plurality of the heat transfer tubes 3T described above, and the secondary coolant C2 outside the heat transfer tubes 3T is heated and boiled by the primary coolant C1 flowing in the heat transfer tubes 3T, and the secondary coolant C2 is boiled. High temperature and high pressure steam is generated.
- the steam generator 3 and the turbine 8 are connected by a steam supply passage 7S, and the condenser 9 and the steam generator 3 are connected by a secondary coolant recovery passage 7R.
- the high-temperature and high-pressure steam of the secondary coolant C2 generated by the steam generator 3 is supplied to the turbine 8 through the steam supply passage 7S and drives it.
- electric power is generated by the generator 10 connected to the drive shaft of the turbine 8.
- the secondary coolant C2 after driving the turbine 8 becomes liquid in the condenser 9, and is sent again to the steam generator 3 through the secondary coolant recovery passage 7R.
- the pressurizer 4 for pressurizing the primary coolant is connected to the primary coolant second supply passage 6B.
- the pressurizer 4 applies pressure to the primary coolant C1 in the primary coolant second supply passage 6B.
- the primary coolant C1 does not boil even when heated by the thermal energy generated by the nuclear fission reaction, and circulates in the reactor 2 and its cooling system in a liquid phase.
- the cooling system of the nuclear reactor 2 includes a primary coolant pump 5, a primary coolant first supply passage 6A, a primary coolant second supply passage 6B, a steam generator 3, and a primary coolant recovery passage 6C. This is a system through which the primary coolant C1 flows.
- a desalting tower 16 is provided to remove impurities contained in the primary coolant C1.
- the desalting tower 16 includes a first desalting tower 16A and a second desalting tower 16B, and is provided outside the storage container 1W.
- the first desalting tower 16A is a coolant hot bed desalting tower
- the second desalting tower 16B is a coolant cation desalting tower.
- the primary coolant C1 taken out from the inlet side (upstream side) of the primary coolant pump 5 is supplied from the cooling system of the reactor 2 to the desalting tower 16 to be subjected to desalination, and the primary after desalting is performed.
- the coolant C1 is returned to the outlet side (downstream side) of the primary coolant pump 5.
- the demineralization treatment system for the primary coolant C1 includes a primary coolant take-out passage 13A, a regenerative heat exchanger 11, a primary coolant passage 13B, a non-regenerative heat exchanger 12, a primary coolant passage 13C, a desalting tower 16, and a primary cooling. It is composed of a material passage 13D, a volume control tank 14, and primary coolant return passages 13E and 13F.
- the primary coolant take-out passage 13 ⁇ / b> A connects the primary coolant recovery passage 6 ⁇ / b> C and the regenerative heat exchanger 11 constituting the cooling system of the nuclear reactor 2.
- the regenerative heat exchanger 11 and the non-regenerative heat exchanger 12 are connected by a primary coolant passage 13B, and the non-regenerative heat exchanger 12 and the desalting tower 16 are connected by a primary coolant passage 13C.
- the desalting tower 16 and the volume control tank 14 are connected by a primary coolant passage 13D, and the volume control tank 14 and the regenerative heat exchanger 11 are connected by a primary coolant return passage 13E.
- the regenerative heat exchanger 11 and the primary coolant first supply passage 6A are connected by a primary coolant return passage 13F.
- a filling pump 15 is provided in the primary coolant return passage 13E.
- the primary coolant C1 is taken out from the primary coolant take-out passage 13A, that is, the inlet side (upstream side) of the primary coolant pump 5.
- the primary coolant C1 taken out from the cooling system of the reactor 2 is guided to the regenerative heat exchanger 11, and then desalted through the primary coolant passage 13B, the non-regenerative heat exchanger 12, and the primary coolant passage 13C. It is led to the tower 16 where it is desalted.
- the desalted primary coolant C1 is temporarily stored in the volume control tank 14 through the primary coolant passage 13D and then regenerated by the regenerative heat exchanger 11 by the filling pump 15 provided in the primary coolant return passage 13E. Sent to.
- the primary coolant C1 that has passed through the regenerative heat exchanger 11 is returned to the primary coolant first supply passage 6A, that is, the outlet side (downstream side) of the primary coolant pump 5 through the primary coolant return passage 13F.
- a neutron absorber is usually added to the primary coolant for the purpose of controlling the reactivity of the reactor 2.
- the neutron absorber for example, boric acid that absorbs neutrons well is added to the primary coolant and dissolved. Boric acid absorbs neutrons well because it contains boron atoms, which are neutron absorbers. The reactivity is controlled by adjusting the boron concentration in the primary coolant. This is called chemical shim control (boron concentration adjustment).
- boric acid is added so that boron, which is a neutron absorber, is about 2000 ppm (mass ppm), and boron is continuously diluted as the operation progresses, resulting in a long-term reaction of the core. Compensate for degree changes.
- the chemical shim control is executed by the chemical volume control facility of the primary cooling system that constitutes the reactor 2, and is used when, for example, it is desired to change the reactivity due to the combustion of the fuel or to gradually change the output of the reactor 2. .
- boron is uniformly distributed throughout the reactor, there is an advantage that local change in the power distribution in the reactor hardly occurs.
- a boron injection device 20 is provided to inject boron into the primary coolant C1.
- boron is injected into the primary coolant C1 in the form of boric acid from between the volume control tank 14 and the filling pump 15 constituting the desalination processing system of the primary coolant C1.
- the boron injection device 20 is provided in a boric acid tank 21, a boric acid injection pump 22 that is a boron injection means, a boric acid supply passage 24 that connects the boric acid tank 21 and the boric acid injection pump 22, and a boric acid supply passage 24.
- a flow control valve 23 is provided.
- Boric acid is stored in the boric acid tank 21 in the form of an aqueous boric acid solution adjusted to a predetermined concentration. Further, the flow rate adjusting valve 23 adjusts the boric acid injection speed.
- the boric acid injection speed may be adjusted by controlling the boric acid injection pump 22. In this embodiment, the boric acid injection speed is adjusted using at least one of the boric acid injection pump 22 and the flow rate adjusting valve 23.
- the boric acid injection pump 22 and the primary coolant return passage 13E are connected by a boric acid injection passage 25.
- An open / close valve 26 is provided in the boric acid injection passage 25.
- the on-off valve 26 is opened when boric acid injection is required, and is closed when boric acid injection is not required.
- the boric acid injection passage 25 is provided with a flow meter 28 for measuring the flow rate of boric acid injected into the primary coolant C1. Thereby, the flow rate of boric acid injected into the primary coolant C1 is measured.
- a primary coolant sample collection point 29 for measuring the concentration of boric acid in the primary coolant C1 is provided in the primary coolant passage 13C constituting the desalination processing system of the primary coolant C1. Thereby, the concentration of boric acid contained in the primary coolant C1 is measured.
- the operations of the boric acid injection pump 22, the flow rate adjustment valve 23, and the on-off valve 26 are controlled by manual operation by an operator, for example. Further, the flow rate of boric acid measured by the flow meter 28 and the concentration of boric acid measured at the primary coolant sample collection point 29 are used for the operation of the nuclear power plant.
- the opening degree of the flow rate adjusting valve 23 and the driving conditions of the boric acid injection pump 22 are set so that boric acid can be injected at a set injection speed. Then, by manual operation, the on-off valve 26 is opened, the flow rate adjusting valve 23 is adjusted to the set opening degree, and the boric acid injection pump 22 is driven under the set driving conditions. As a result, boric acid in the boric acid tank 21 passes through the boric acid supply passage 24 and the boric acid injection passage 25 and is injected into the primary coolant C1 in the primary coolant return passage 13E.
- the boric acid injected into the primary coolant C1 is sent to the regenerative heat exchanger 11 together with the primary coolant C1 by the filling pump 15. Then, the boric acid and the primary coolant C1 flow into the primary coolant first supply passage 6A, that is, the outlet side (downstream side) of the primary coolant pump 5 through the primary coolant return passage 13F, and then the reactor. 2 throughout.
- boric acid waste (boric acid waste) is generated because boric acid, which is a neutron absorber, is injected into the primary coolant.
- the boric acid waste discharged from the nuclear reactor 2 is radioactive waste and requires a predetermined treatment.
- the proportion of the chemical shim control shared by the reactivity control of the nuclear reactor 2 is reduced both during the operation of the nuclear reactor 2 and when the nuclear reactor 2 is stopped.
- FIG. 2 is a diagram showing a breakdown of the reactivity control of the nuclear reactor.
- FIGS. 3A and 3B are schematic diagrams showing the concentration of burnable poison in the fuel rod.
- L in FIG. 3-2 is a dimension (length) in the longitudinal direction of the fuel rod 2CLb1 shown in FIG. 3-2, and a symbol C indicates the center of the fuel rod 2CLb1.
- BP burnable poison
- gadolinium (Gd) is used as a burnable poison, and a large amount thereof is added to the fuel (for example, 0 mass% or more and 20 mass% or less).
- the boron concentration in the primary coolant can be reduced by the reactivity of the burnable poison. Therefore, as shown in FIG.
- the share of chemical shim control in the case of controlling the reactivity can be reduced (F1 in FIG. 2). As a result, in controlling the reactivity of the nuclear reactor, the share of chemical shim control can be reduced.
- the burnable poison is a poisonous substance whose concentration of the poisonous substance itself is remarkably changed by a neutron absorption reaction as a poisonous action.
- flammability shows the property which lose
- poison means neutron absorption ability
- poison means a substance having large neutron absorption ability, which is different from the meaning of poison or poison.
- the increase range of the hydrogen to heavy metal atom number ratio H / HM can be increased, which is advantageous for optimization of the fuel assembly design.
- the hydrogen to heavy metal atom ratio H / HM is defined by the ratio of the number of hydrogen atoms in the fuel assembly to the number of heavy metal (nuclear fuel such as uranium) atoms, and the hydrogen to heavy metal atom ratio H / HM.
- the ratio of the primary coolant to the fuel becomes larger in the reactor pressure vessel.
- the fuel rod diameter is 9.5 mm
- the fuel rod pitch width is 12.6 mm
- the fuel pellet diameter is 8.2 mm
- the heavy metal (UO 2 ) density in the pellet is 10 .97 g / cm 3 , theoretical density converted value of pellet 97% TD, UO 2 molar mass 270.03 g / mol, moderator (water) density 0.71 g / cm 3 during rated output operation, moderator (water) mol
- the mass is 18.015 g / mol
- the control rod and the guide thimble outside diameter for in-core instrumentation are 12.2 mm
- the hydrogen to heavy metal atomic ratio H / HM is about 4.1.
- the concentration of burnable poison in the central portion of the fuel rod 2CLb1 is made higher than the concentration of burnable poison on both ends T1 and T2 of the fuel rod 2CLb1, thereby the center in the longitudinal direction of the fuel rod 2CLb1.
- the output of the part is suppressed.
- distortion of the power distribution in the core can be suppressed.
- the distribution of the concentration of burnable poisons in the fuel rods may be changed according to the specifications of the nuclear reactor and the core.
- the concentration of burnable poison in the central portion of the fuel rod may be higher than the concentration of burnable poison on one end side of the fuel rod.
- the concentration of burnable poison in the central portion of the fuel rod is set higher than the concentration of burnable poison in at least one end side of the fuel rod, so that the power distribution in the core is increased. Suppresses distortion.
- Figure 4 shows the primary coolant during rated power operation from the BOC (Beginning Of Cycle) at the time of reactor shim control to EOC (End Of Cycle: at the end of reactor operation). It is a schematic diagram which shows the change of the boron concentration in it.
- N in FIG. 4 indicates a change in boron concentration in the primary coolant in a nuclear reactor that performs chemical shim control without adding burnable poison to the fuel
- F in FIG. 4 indicates a nuclear reactor according to the present embodiment ( This shows the change in the boron concentration in the primary coolant when a large amount of burnable poison is added to the fuel.
- the boron concentration (the concentration of the neutron absorber) in the primary coolant in the BOC is D2 (for example, 1700 ppm). Further, the boron concentration in the primary coolant during the rated power operation at EOC is approximately 0 ppm even when the burnable poison is not added to the fuel and in the nuclear reactor according to the present embodiment.
- the boron concentration in the primary coolant necessary to achieve a low temperature shutdown by chemical shim control and maintain the state, and the boron concentration is Db (for example, 700 ppm), EOC in BOC. In De, it is De (for example, 1000 ppm) (Db ⁇ De).
- the boron concentration De in the primary coolant is required in EOC, so the nuclear reactor must have the ability to process the primary coolant with the boron concentration in the primary coolant De become.
- the boron concentration D1 in the primary coolant during the rated output operation at the BOC and the primary in the BOC necessary to realize a low temperature stop by chemical shim control.
- the processing capacity of the primary coolant containing boron necessary for the nuclear reactor can be used effectively.
- the boron concentration D1 in the primary coolant during the rated output operation at the BOC may be 0, but in this case, the amount of burnable poison added to the fuel is increased, and an appropriate output distribution is obtained.
- the core design may be difficult. For this reason, it is preferable that the boron concentration D1 in the primary coolant during the rated output operation at the BOC is a certain value.
- the boron concentration D1 in the primary coolant during the rated power operation at the BOC needs to have a certain margin. There is. For this reason, the boron concentration D1 in the primary coolant during the rated power operation at the BOC is set in consideration of a predetermined value for De ⁇ Db, that is, the design accuracy of the reactor and the specifications of the reactor core. It is preferable to add a predetermined margin Dm. As a result, the reactor can be operated more safely.
- the boron concentration margin based on the design accuracy of the reactor is 100 ppm
- the boron concentration margin based on the diversity of the reactor core specifications is 200 ppm
- De is 1000 ppm
- Db is 700 ppm
- D1 is 600 ppm.
- the boron concentration D1 contained in the primary coolant during the rated power operation of the nuclear reactor at the start of the nuclear reactor operation (BOC) is the value at the end of the nuclear reactor operation.
- a predetermined value (D1 De ⁇ Db + Dm) obtained by adding a predetermined margin Dm set in consideration of the design accuracy of the reactor and the specification of the reactor core to the value (De ⁇ Db) It will be.
- the burnable added to the fuel so that the boron concentration D1 contained in the primary coolant during the rated power operation of the reactor at the start of the reactor operation (BOC) can be realized.
- the amount of poison is determined.
- the specific amount of burnable poison to be loaded cannot be uniquely determined here because the operating conditions of the replacement core change variously. For this reason, it is determined that the concentration of boron is less than or equal to the required boron concentration in the replacement core design study that is performed at the time of fuel replacement.
- control rods are used to stop the reactor at a high temperature, and chemical shim control is used to stop the reactor at a low temperature. And when maintaining the shutdown state of the reactor, chemical shim control was used.
- the control rod is used for the high temperature shutdown and the low temperature shutdown of the nuclear reactor, and the chemical shim control is used only when the nuclear reactor is stopped. This eliminates the need for chemical shim control at the time of low-temperature shutdown, which has been conventionally used. Therefore, when controlling the reactivity of the reactor, as shown in F1 of FIG. Can be reduced.
- the safety system can be made autonomous (strengthening the response to the supercooling event).
- the high temperature shutdown refers to a shutdown state in which the reactor is kept subcritical and the primary coolant is at a temperature of about 100 ° C. or higher. It may also refer to a state where a no-load temperature of about 290 ° C. is maintained due to heat input of the primary coolant pump or the like.
- the low temperature shutdown means a state in which the nuclear fission reaction is stopped and the reactor is cooled and decompressed at a temperature of 95 ° C. or lower.
- the reactivity control ability of the control rod refers to the magnitude of the ability to adjust the reactivity of the reactor. If the amount of insertion or withdrawal is the same, the reactivity can be adjusted to a greater degree. The ability is great. Increasing the reactivity control ability can be realized by using a substance having a large neutron absorption ability for the control rod or increasing the number of control rods.
- 5 to 7 are diagrams showing an example of improving the reactivity control ability of the control rod.
- 5 to 7 show cross sections perpendicular to the longitudinal direction of the control rod.
- neutron absorber eg boron
- the control rod has the reactivity control capability that can shut down the reactor inside. In order to realize this, for example, the number of control rods used in the conventional PWR is increased, or the specification and shape of the control rods are devised.
- control rod specification and shape can be devised by adopting a full-length B 4 C control rod (a structure in which B 4 C is arranged as a neutron absorber over the entire region in the longitudinal direction of the fuel rod), Examples thereof include increasing the diameter, increasing the surface area of the control rod, or adding a neutron moderating substance to the control rod.
- a full-length B 4 C control rod a structure in which B 4 C is arranged as a neutron absorber over the entire region in the longitudinal direction of the fuel rod
- Examples thereof include increasing the diameter, increasing the surface area of the control rod, or adding a neutron moderating substance to the control rod.
- the diameter Df is made larger than the diameter Dn of the control rod 2LN used in the conventional PWR (Df> Dn).
- the diameter of the control rod 2LF is set to the maximum diameter in a range not interfering with the control rod 2LF in consideration of, for example, the interval at which the control rods 2LF are arranged.
- a control rod having a circular cross section so far such as the control rod 2LFa shown in FIG.
- the surface area of the control rod 2LFa can be increased as compared with the control rod having a circular cross section.
- a neutron moderating material ND for example, carbon or light water
- the neutron absorber NA for example, B 4 C
- the fast neutrons that have passed through the neutron absorber NA are decelerated by the neutron moderator ND to become thermal neutrons and absorbed by the neutron absorber NA. This improves the reactivity control capability of the control rod 2LFb.
- FIG. 8 is a diagram showing the relationship between the effective multiplication factor and the primary coolant density.
- the burden ratio of chemical shim control when the reactor is stopped is reduced.
- the hydrogen to heavy metal atom number ratio H / HM can be made larger than before.
- the temperature of the primary coolant decreases and the primary coolant density increases from ⁇ h (primary coolant density during rated operation) to ⁇ c (primary coolant density during low-temperature shutdown). .
- the effective multiplication factor also increases. Therefore, when the reactor is cooled, it is necessary to control the addition reactivity corresponding to the increased effective multiplication factor.
- FIG. 8 when the hydrogen-to-heavy metal atom ratio H / HM increases, the change in the effective multiplication factor during cooling is smaller than when the hydrogen-to-heavy metal atom ratio H / HM is small. Become. For example, as shown in FIG.
- the addition reactivity can be reduced by increasing the hydrogen to heavy metal atom ratio H / HM.
- H / HM hydrogen to heavy metal atom ratio
- FIG. 9 and 10 are diagrams showing the relationship between the effective multiplication factor and the hydrogen to heavy metal atom number ratio H / HM.
- FIG. 11 is a diagram showing the arrangement pitch of the fuel rods.
- a dotted line F in FIG. 9 shows a case where the amount of burnable poison added to the fuel is larger than the solid line N
- a dotted line F in FIG. 10 shows a case where the share of chemical shim control is reduced compared to the solid line N. Show.
- the maximum value of the hydrogen to heavy metal atomic ratio H / HM is a value when the effective multiplication factor becomes the maximum value (the portion where the effective multiplication factor is convex upward).
- the hydrogen to heavy metal atom ratio H / HM is a range from the curve showing the relationship between the effective multiplication factor when the BOC is stopped at a high temperature and the hydrogen to heavy metal atom ratio H / HM until the effective multiplication factor reaches the maximum value. Is set.
- the hydrogen to heavy metal atom ratio H / HM is preferably 4.5 or more, more preferably 5 or more, and further preferably 5.5 or more.
- the maximum value of the hydrogen to heavy metal atomic ratio H / HM is a value that maximizes the nuclear reactivity of the core in a state where the boron concentration in the primary coolant is 0 and all the control rods are pulled out, that is, the effective value. This is the value when the multiplication factor is maximized.
- the hydrogen to heavy metal atom ratio H / HM can be increased by reducing the diameter of the fuel rods or increasing the arrangement pitch of the fuel rods.
- the arrangement pitch of the fuel rods is a center-to-center distance P between adjacent fuel rods 2CL shown in FIG. 11, and in this embodiment, the arrangement pitch is 1.3 cm or more and 1.5 cm or less, more preferably 1.4 cm or more and 1 .5 cm or less.
- the hydrogen to heavy metal atom number ratio H / HM can be increased without being restricted by the production capacity of the fuel rods.
- the hydrogen to heavy metal atom ratio H / HM is increased, and the fuel assembly is designed in a range where the moderator density coefficient is not positive in BOC and HZP (Hot Zero Power).
- HZP Hot Zero Power
- the nuclear reactor according to the present invention is useful for reducing the environmental load, and is particularly suitable for PWR.
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Chemical & Material Sciences (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
Description
図2は、原子炉の反応度制御の内訳を示す図である。図3-1、図3-2は、燃料棒中のバーナブルポイズンの濃度を示す模式図である。図3-2中のLは、図3-2に示す燃料棒2CLb1の長手方向における寸法(長さ)であり、符号Cは、燃料棒2CLb1の中央を示す。本実施形態では、バーナブルポイズン(BP:Burnable Poison:可燃性毒物)を大量に用いる。例えば、バーナブルポイズンとしてガドリニウム(Gd)を用い、これを大量に燃料へ添加する(例えば、0質量%以上20質量%以下)。これによって、バーナブルポイズンの有する反応度分、一次冷却材中のホウ素濃度を低下させることができるので、図2に示すように、現状(N)と比較して、定格出力運転時に原子炉の反応度を制御する場合におけるケミカルシム制御の分担割合を低減できる(図2のF1)。その結果、原子炉の反応度を制御するにあたっては、ケミカルシム制御の分担割合を低減できる。
従来、原子炉を高温停止させる場合には制御棒を用い、低温停止させる場合にはケミカルシム制御を用いていた。そして、原子炉の停止状態を維持する場合にはケミカルシム制御を用いていた。本実施形態では、原子炉の高温停止及び低温停止に制御棒を用い、原子炉の停止状態を維持する場合のみにケミカルシム制御を用いる。これによって、従来用いられていた低温停止時におけるケミカルシム制御が不要になるので、原子炉の反応度を制御するにあたっては、図2のF1に示すように、ケミカルシム制御の分担割合を大幅に低減できる。また、制御棒のみによって瞬時に原子炉の低温停止が実現できる程度の反応度制御能力を制御棒に与えるので、原子炉の過冷却事象時における再臨界も回避できるという効果も得られる。さらに、低温停止を実現するために、ケミカルシム制御は用いないので、安全系の自律化(過冷却事象への対応強化)が可能となる。
1W 格納容器
2 原子炉
2A 制御棒駆動装置
2C 燃料部分
2CL、2CLa、2CLb1 燃料棒
2L、2LF、2LFa、2LFb、2LN 制御棒
2P 圧力容器
3 蒸気発生器
4 加圧器
5 一次冷却材ポンプ
8 タービン
9 復水器
10 発電機
14 体積制御タンク
15 充填ポンプ
16 脱塩塔
20 ホウ素注入装置
21 ホウ酸タンク
22 ホウ酸注入ポンプ
23 流量調整弁
24 ホウ酸供給通路
25 ホウ酸注入通路
26 開閉弁
28 流量計
Claims (11)
- 核燃料が封入された燃料棒と、前記核燃料の核反応を制御する制御棒とを有する原子炉において、
前記原子炉の運転開始時での前記原子炉の定格出力運転時における一次冷却材中に含まれる中性子吸収材の濃度を、前記原子炉の運転終了時に前記原子炉を低温停止させ、その状態を維持させるために必要な中性子吸収材の濃度から、前記原子炉の運転開始時に前記原子炉を低温停止させ、その状態を維持させるために必要な中性子吸収材の濃度を減算した値に、所定の値を加算した値以下とすることを特徴とする原子炉。 - 前記燃料棒を構成する燃料中にバーナブルポイズンを添加するとともに、前記燃料棒の少なくとも一方の端部側における前記バーナブルポイズンの濃度よりも、前記燃料棒の中央部分における前記バーナブルポイズンの濃度が高い請求項1に記載の原子炉。
- 前記制御棒は、前記一次冷却材へ中性子吸収材を投入することなしに運転中の前記原子炉を低温停止させることができる反応度制御能力を有する請求項1に記載の原子炉。
- 前記制御棒は、前記一次冷却材へ中性子吸収材を投入することなしに運転中の前記原子炉を低温停止させることができる反応度制御能力を有する請求項3に記載の原子炉。
- 前記一次冷却材は水であり、前記原子炉の水素対重金属原子数比は、4.5以上、かつ前記一次冷却材中にホウ素が添加されていない場合において炉心の核反応度を最大とさせる値以下である請求項1に記載の原子炉。
- 前記一次冷却材は水であり、前記原子炉の水素対重金属原子数比は、4.5以上、かつ前記一次冷却材中にホウ素が添加されていない場合において炉心の核反応度を最大とさせる値以下である請求項2に記載の原子炉。
- 前記一次冷却材は水であり、前記原子炉の水素対重金属原子数比は、4.5以上、かつ前記一次冷却材中にホウ素が添加されていない場合において炉心の核反応度を最大とさせる値以下である請求項3に記載の原子炉。
- 前記一次冷却材は水であり、前記原子炉の水素対重金属原子数比は、4.5以上、かつ前記一次冷却材中にホウ素が添加されていない場合において炉心の核反応度を最大とさせる値以下である請求項4に記載の原子炉。
- 核燃料が封入された燃料棒と、前記核燃料の核反応を制御する制御棒とを有する原子炉において、
前記核燃料中にバーナブルポイズンを添加するとともに、前記燃料棒の少なくとも一方の端部側における前記バーナブルポイズンの濃度よりも、前記燃料棒の中央部分における前記バーナブルポイズンの濃度が高いことを特徴とする原子炉。 - 核燃料が封入された燃料棒と、前記核燃料の核反応を制御する制御棒とを有する原子炉において、
前記制御棒は、前記一次冷却材へホウ素を投入することなしに運転中の前記原子炉を低温停止させることができる反応度制御能力を有することを特徴とする原子炉。 - 核燃料が封入された燃料棒と、前記核燃料の核反応を制御する制御棒とを有するとともに、一次冷却材は水を用いる原子炉において、
水素対重金属原子数比は、4.5以上、かつ前記一次冷却材中にホウ素が添加されていない場合において炉心の核反応度を最大とさせる値以下であることを特徴とする原子炉。
Priority Applications (4)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
US13/264,429 US20120033776A1 (en) | 2009-04-14 | 2010-04-12 | Nuclear reactor |
KR1020117024250A KR101317962B1 (ko) | 2009-04-14 | 2010-04-12 | 원자로 |
EP10764424.7A EP2421005B1 (en) | 2009-04-14 | 2010-04-12 | Nuclear reactor |
CN201080016598.3A CN102396033B (zh) | 2009-04-14 | 2010-04-12 | 核反应堆 |
Applications Claiming Priority (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP2009-098472 | 2009-04-14 | ||
JP2009098472A JP5364424B2 (ja) | 2009-04-14 | 2009-04-14 | 原子炉 |
Publications (1)
Publication Number | Publication Date |
---|---|
WO2010119840A1 true WO2010119840A1 (ja) | 2010-10-21 |
Family
ID=42982502
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
PCT/JP2010/056528 WO2010119840A1 (ja) | 2009-04-14 | 2010-04-12 | 原子炉 |
Country Status (6)
Country | Link |
---|---|
US (1) | US20120033776A1 (ja) |
EP (1) | EP2421005B1 (ja) |
JP (1) | JP5364424B2 (ja) |
KR (1) | KR101317962B1 (ja) |
CN (1) | CN102396033B (ja) |
WO (1) | WO2010119840A1 (ja) |
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
EP2461328B1 (en) * | 2010-12-06 | 2015-07-08 | Mitsubishi Heavy Industries, Ltd. | Nuclear fuel assembly |
CN109473185A (zh) * | 2018-11-13 | 2019-03-15 | 中国核动力研究设计院 | 一种自动化学停堆系统的测试装置及其测试方法 |
Families Citing this family (7)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN103236276B (zh) * | 2013-04-21 | 2016-12-28 | 中国科学院合肥物质科学研究院 | 一种用于液态重金属冷却反应堆的控制棒 |
US20170140842A1 (en) * | 2015-11-12 | 2017-05-18 | Westinghouse Electric Company Llc | Subcritical Reactivity Monitor Utilizing Prompt Self-Powered Incore Detectors |
CN106257596B (zh) * | 2016-09-06 | 2018-09-11 | 中国核动力研究设计院 | 一种小型反应堆异形控制棒 |
CN109147967B (zh) * | 2017-06-15 | 2022-08-16 | 广东核电合营有限公司 | 一种用于核电站的硼浓度控制装置和方法 |
WO2019164584A2 (en) | 2017-12-29 | 2019-08-29 | Nuscale Power, Llc | Controlling a nuclear reaction |
CN111508620B (zh) * | 2020-04-30 | 2023-03-24 | 中国核动力研究设计院 | 一种反应堆机动性自调节方法 |
WO2022126096A1 (en) * | 2020-12-07 | 2022-06-16 | Westinghouse Electric Company Llc | High energy nuclear fuel, fuel assembly, and refueling method |
Citations (7)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPS61129594A (ja) * | 1984-11-28 | 1986-06-17 | 株式会社日立製作所 | 軽水減速型原子炉 |
JPS63172990A (ja) * | 1987-01-12 | 1988-07-16 | 株式会社東芝 | 沸騰水型原子炉 |
JPH0194293A (ja) * | 1987-10-06 | 1989-04-12 | Mitsubishi Atom Power Ind Inc | 軽水冷却軽水減速型原子炉炉心の反応度制御方法 |
JPH02154195A (ja) * | 1988-12-07 | 1990-06-13 | Mitsubishi Atom Power Ind Inc | 炉心内挿物集合体 |
JPH04270991A (ja) * | 1991-02-27 | 1992-09-28 | Mitsubishi Atom Power Ind Inc | 原子炉制御棒駆動装置 |
JP2006113069A (ja) * | 2004-10-14 | 2006-04-27 | Westinghouse Electric Co Llc | 二酸化ウランにおけるホウ素または濃縮ホウ素同位体10bの使用 |
JP2007003371A (ja) * | 2005-06-24 | 2007-01-11 | Mitsubishi Heavy Ind Ltd | 原子炉用制御棒 |
Family Cites Families (10)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CA935571A (en) * | 1970-05-19 | 1973-10-16 | Westinghouse Electric Corporation | Boron control system for a nuclear power plant |
FR2520545A1 (fr) * | 1982-01-27 | 1983-07-29 | Framatome Sa | Procede et dispositif de modification de la concentration du poison soluble contenu dans le fluide refrigerant du circuit primaire d'un reacteur nuclaire |
JPH0640137B2 (ja) * | 1986-08-01 | 1994-05-25 | 株式会社日立製作所 | 燃料集合体および沸騰水型原子炉 |
FR2629623B1 (fr) * | 1988-04-05 | 1990-11-16 | Framatome Sa | Procede de determination et d'evaluation de la marge d'arret d'urgence d'un reacteur nucleaire a eau pressurisee |
JP3531011B2 (ja) * | 1993-10-12 | 2004-05-24 | 株式会社日立製作所 | 燃料集合体及び原子炉 |
DE4441751C1 (de) * | 1994-11-23 | 1996-04-25 | Siemens Ag | Schnellabschaltsystem und Verfahren zur Schnellabschaltung eines Kernreaktors |
SE513289C2 (sv) * | 1998-12-23 | 2000-08-21 | Asea Atom Ab | Korsformad styrstav där mängden absorbatormaterial är mindre i styrstavens övre del än i dess undre |
JP3779866B2 (ja) * | 2000-08-30 | 2006-05-31 | 株式会社日立製作所 | 沸騰水型原子炉の制御棒及び制御棒用ユニット並びに沸騰水型原子炉の制御棒の製造方法 |
EP2618333B1 (en) * | 2003-03-20 | 2015-05-13 | Hitachi, Ltd. | Boiling water reactor core |
CN100341075C (zh) * | 2004-12-03 | 2007-10-03 | 大亚湾核电运营管理有限责任公司 | 一种提高核电站安注系统整体可靠性的方法 |
-
2009
- 2009-04-14 JP JP2009098472A patent/JP5364424B2/ja active Active
-
2010
- 2010-04-12 KR KR1020117024250A patent/KR101317962B1/ko active IP Right Grant
- 2010-04-12 CN CN201080016598.3A patent/CN102396033B/zh not_active Expired - Fee Related
- 2010-04-12 US US13/264,429 patent/US20120033776A1/en not_active Abandoned
- 2010-04-12 WO PCT/JP2010/056528 patent/WO2010119840A1/ja active Application Filing
- 2010-04-12 EP EP10764424.7A patent/EP2421005B1/en not_active Not-in-force
Patent Citations (7)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPS61129594A (ja) * | 1984-11-28 | 1986-06-17 | 株式会社日立製作所 | 軽水減速型原子炉 |
JPS63172990A (ja) * | 1987-01-12 | 1988-07-16 | 株式会社東芝 | 沸騰水型原子炉 |
JPH0194293A (ja) * | 1987-10-06 | 1989-04-12 | Mitsubishi Atom Power Ind Inc | 軽水冷却軽水減速型原子炉炉心の反応度制御方法 |
JPH02154195A (ja) * | 1988-12-07 | 1990-06-13 | Mitsubishi Atom Power Ind Inc | 炉心内挿物集合体 |
JPH04270991A (ja) * | 1991-02-27 | 1992-09-28 | Mitsubishi Atom Power Ind Inc | 原子炉制御棒駆動装置 |
JP2006113069A (ja) * | 2004-10-14 | 2006-04-27 | Westinghouse Electric Co Llc | 二酸化ウランにおけるホウ素または濃縮ホウ素同位体10bの使用 |
JP2007003371A (ja) * | 2005-06-24 | 2007-01-11 | Mitsubishi Heavy Ind Ltd | 原子炉用制御棒 |
Non-Patent Citations (1)
Title |
---|
See also references of EP2421005A4 * |
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
EP2461328B1 (en) * | 2010-12-06 | 2015-07-08 | Mitsubishi Heavy Industries, Ltd. | Nuclear fuel assembly |
CN109473185A (zh) * | 2018-11-13 | 2019-03-15 | 中国核动力研究设计院 | 一种自动化学停堆系统的测试装置及其测试方法 |
Also Published As
Publication number | Publication date |
---|---|
JP2010249618A (ja) | 2010-11-04 |
KR20120011850A (ko) | 2012-02-08 |
EP2421005B1 (en) | 2014-08-13 |
CN102396033B (zh) | 2015-01-28 |
KR101317962B1 (ko) | 2013-10-14 |
JP5364424B2 (ja) | 2013-12-11 |
EP2421005A4 (en) | 2013-07-31 |
US20120033776A1 (en) | 2012-02-09 |
EP2421005A1 (en) | 2012-02-22 |
CN102396033A (zh) | 2012-03-28 |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
JP5364424B2 (ja) | 原子炉 | |
GB886874A (en) | Device and method for producing power | |
WO2010027656A2 (en) | Mixed oxide fuel assembly | |
WO2018074341A1 (ja) | 燃料集合体及びそれを装荷する沸騰水型原子炉の炉心 | |
KR100935560B1 (ko) | 가압수형 원자로의 연료 집합체 및 연료 집합체의 설계방법 | |
JP2018084558A (ja) | 制御棒ユニット、原子炉、燃料位置決定システム及び燃料位置決定方法 | |
JP2018071997A (ja) | 高速炉の炉心 | |
Baranaev et al. | Supercritical-pressure water nuclear reactors | |
US3247072A (en) | Nuclear reactor and method of operating to variably moderate and control same | |
Thomet | Feasibility studies of a soluble boron-free 900-MW (electric) PWR, core physics–I: Motivations, assembly design, and core control | |
JP2007256230A (ja) | 冷却材分離型溶融核燃料原子炉 | |
Li et al. | Conceptual core design of HAPPY200 reactor | |
Han et al. | An overview of heavy water reactors | |
Oka et al. | Light water reactor design | |
Yongchang et al. | Some features of the nuclear heating reactor (NHR) design in China | |
Melese-d'Hospital et al. | Status of gas-cooled fast breeder reactor programs | |
EP0170033B1 (en) | Fluid moderator control system -d2o/h2o | |
Nakamura et al. | High power transient characteristics and capability of NSRR | |
Oka et al. | Reactor design and safety | |
Bystrikov et al. | Experience in using uranium-erbium fuel in power-generating units with RBMK-1000 reactors | |
Renteria del Toro et al. | Loading pattern determination for 50% MOX and 50% UO 2 iPOWER reactor for initial cycle | |
Mehtap | BOILING WATER REACTORS | |
JP2024063575A (ja) | 炉心の制御方法 | |
JP2023535731A (ja) | 燃料補給および/または保管の中性子吸収棒 | |
Cameron et al. | The heavy-water-moderated reactor |
Legal Events
Date | Code | Title | Description |
---|---|---|---|
WWE | Wipo information: entry into national phase |
Ref document number: 201080016598.3 Country of ref document: CN |
|
121 | Ep: the epo has been informed by wipo that ep was designated in this application |
Ref document number: 10764424 Country of ref document: EP Kind code of ref document: A1 |
|
ENP | Entry into the national phase |
Ref document number: 20117024250 Country of ref document: KR Kind code of ref document: A |
|
NENP | Non-entry into the national phase |
Ref country code: DE |
|
WWE | Wipo information: entry into national phase |
Ref document number: 13264429 Country of ref document: US Ref document number: 2010764424 Country of ref document: EP |