CN110580957B - Reactor charging starting method without external neutron source - Google Patents

Reactor charging starting method without external neutron source Download PDF

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CN110580957B
CN110580957B CN201910886447.6A CN201910886447A CN110580957B CN 110580957 B CN110580957 B CN 110580957B CN 201910886447 A CN201910886447 A CN 201910886447A CN 110580957 B CN110580957 B CN 110580957B
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reactor core
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fuel assemblies
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于颖锐
崔怀明
李海颖
周金满
肖锋
蒋朱敏
王帅
刘同先
秦冬
彭星杰
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Nuclear Power Institute of China
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    • 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
    • G21C19/20—Arrangements for introducing objects into the pressure vessel; Arrangements for handling objects within the pressure vessel; Arrangements for removing objects from the pressure vessel
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C7/00—Control of nuclear reaction
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C7/00—Control of nuclear reaction
    • G21C7/34—Control of nuclear reaction by utilisation of a primary neutron source
    • 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
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    • Y02E30/30—Nuclear fission reactors

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Abstract

The invention discloses a reactor charging starting method without an external neutron source, which comprises the following steps: injecting a proper amount of boric acid solution into the reactor core, so that the liquid level of the boric acid solution is not higher than the lower limit of the active section of the reactor core; a circle of fuel assemblies are evenly arranged on the outermost layer of the reactor core, and a plurality of out-of-reactor source range detectors are evenly distributed outside the reactor core; further injecting boric acid solution into the reactor core to submerge the reactor core and enable the out-of-core source range detector to enter a blind area; loading the residual fuel assemblies into the reactor core to finish loading; the effective value-added factor of the reactor is improved, and the subcritical degree is reduced until the reactor external source range detector can obtain effective counting, so that a dead zone is eliminated; the state of the reactor core is determined by the counting of the out-of-reactor source range detector, so that the reactor core reaches the critical state of the reactor. The invention is used for solving the problems of high price and strong source attenuation of the reactor starting relying on the primary neutron source in the prior art and achieving the purpose of charging and starting the reactor without using the primary neutron source and the secondary neutron source.

Description

Reactor charging starting method without external neutron source
Technical Field
The invention relates to the field of nuclear reactor cores, in particular to a reactor charge starting method without an external neutron source.
Background
The nuclear reactor is a device for releasing nuclear energy by utilizing the chain fission reaction of nuclear fuel, the nuclear fuel generally participates in the fuel management of a nuclear power plant in the form of fuel assemblies, and the general fuel management requires that the first circulation after the reactor is built is completely filled with new fuel assemblies in the reactor core, and new fuel assemblies are continuously filled in the subsequent circulation to replace part of the fuel assemblies which are burnt up to a certain extent. After a reactor is operated through one cycle, all fuel assemblies are discharged from the core, and at the beginning or first cycle, the fuel assemblies required for fuel management are required to be loaded into the core, and then the reactor is started to reach the critical state, which is called a reactor loading and starting process. The process of loading and starting the reactor is an important work of a nuclear power plant and is a foundation for ensuring the safe and stable operation of the reactor. Most of domestic existing reactors place additional starting neutron sources in the reactor core of the first cycle and the subsequent cycle in the charging and starting processes, and the neutron sources are used for raising the neutron fluence rate level in the reactor, so that the nuclear measurement system can effectively monitor the neutron fluence rate change in the reactor, thereby ensuring the critical safety and avoiding the occurrence of instantaneous criticality.
Commonly used starting neutron sources are classified into primary neutron sources and secondary neutron sources. The primary neutron source is capable of spontaneously generating neutrons, typically using a californium (elemental symbol: Cf) source, the source neutrons originating from
Figure BDA0002207428590000011
Spontaneous fission of (2). The secondary neutron source, which is usually an antimony (symbol of element: Sb) -beryllium (symbol of element: Be) source, generates neutrons after being activated by irradiation in the reactor, and the neutrons are derived from photon fission of beryllium. The primary neutron source material and the secondary neutron source material are manufactured into neutron source rods and put into a nuclear fuel assembly to manufacture a primary neutron source assembly and a secondary neutron source assembly. Existing nuclear reactors are typically built to rely on a primary neutron source assembly for charging and startup in a first cycle; the secondary neutron source is placed into the reactor for irradiation activation in the first cycle, and is used for the charging and starting processes of the reactor from the second cycle. The service life of the secondary neutron source rod is limited (usually 15 years), and after the service life is reached, a new secondary neutron source needs to be replaced and released in advanceAnd (5) putting the mixture into a reactor for irradiation activation. This way of starting has the following drawbacks:
(1) one set of primary neutron source assembly and a plurality of sets of secondary neutron source assemblies are required to be designed and manufactured for each nuclear reactor, and the design cost is increased. In particular, the primary neutron source component is very expensive, and tens of millions of RMB are required for the price of a single primary neutron source component.
(2) The primary neutron source assembly needs to be manufactured in a period of time before the reactor is charged, the source intensity of the primary neutron source assembly can be attenuated continuously, the time of the actual charging and starting process of the nuclear reactor is often difficult to control accurately, and the risk that the first cycle charging and starting requirements cannot be met due to excessive source intensity attenuation exists.
(3) The primary neutron source assembly can spontaneously fission and decay, and therefore, strict approval procedures are required in the manufacturing, transporting, installing and storing processes, so that the cost and the working procedure are greatly increased, and meanwhile, the risks of accidental criticality and personnel dosage overrun also exist.
(4) The neutron source component becomes radioactive waste after being discharged out of the reactor, and the cost of waste storage and post-treatment is increased.
In addition to specially made primary and secondary neutron sources, irradiated fuel assemblies in nuclear power plants can also provide neutrons for reactors, act as neutron sources, mainly derived from the self-fission reaction of actinides and the (alpha, n) reaction of alpha particles released by decay with actinides, with higher assembly burnup and higher source strength. In order to meet the counting requirement of the out-of-reactor detector required by critical supervision in the charging and starting processes, a plurality of irradiated fuel assemblies with high initial enrichment and burn-up depth are generally required to be arranged outside the reactor and close to the detector. It is generally not possible to have a sufficient number of irradiated fuel assemblies as described above until after a certain condition of the reactor has been reached (e.g., after a transition to an equilibrium cycle of 18 months refueling).
It should be noted that the current implementation of this technique is within a single reactor, i.e. irradiated fuel assemblies produced by a certain reactor will only be used for its own charging and start-up process, replacing its own secondary neutron source, and will not be used for charging and start-up processes of other reactors, acting as a start-up neutron source for other reactors. However, because the implementation range is within a single reactor, fuel assemblies are not irradiated in the first cycle, the charging and starting processes of the first cycle still need to depend on a neutron source, and the defects caused by the use of a neutron source for starting can be still faced.
Disclosure of Invention
The invention aims to provide a reactor charging starting method without an external neutron source, which aims to solve the problems that the reactor is started by a primary neutron source, the price is high and the phenomenon of strong source attenuation exists in the prior art and realize the purpose of charging and starting the reactor without using the primary neutron source and a secondary neutron source.
The invention is realized by the following technical scheme:
a reactor charge starting method without an external neutron source comprises the following steps:
(a) injecting a proper amount of boric acid solution into the reactor core, so that the liquid level of the boric acid solution is not higher than the lower limit of the active section of the reactor core;
(b) a circle of fuel assemblies are evenly arranged on the outermost layer of the reactor core, and a plurality of out-of-reactor source range detectors are evenly distributed outside the reactor core;
(c) further injecting boric acid solution into the reactor core to submerge the reactor core and enable the out-of-core source range detector to enter a blind area;
(d) loading the residual fuel assemblies into the reactor core to finish loading;
(e) the effective value-added factor of the reactor is improved, and the subcritical degree is reduced until the reactor external source range detector can obtain effective counting, so that a dead zone is eliminated;
(f) the state of the reactor core is determined by the counting of the out-of-reactor source range detector, so that the reactor core reaches the critical state of the reactor.
In the prior art, a set of primary neutron source assembly and a plurality of sets of secondary neutron source assemblies need to be designed and manufactured for each nuclear reactor, so that the design cost is increased. Particularly, the primary neutron source component is very expensive, and the price of a single primary neutron source component is tens of millions of RMB; the primary neutron source assembly needs to be manufactured in a period of time before the reactor is charged, the source strength of the primary neutron source assembly is continuously attenuated, the time of the actual charging and starting process of the nuclear reactor is often difficult to accurately control, and the risk that the first cycle charging and starting requirements cannot be met due to excessive attenuation of the source strength exists; the primary neutron source component can spontaneously fission and decay, so that strict approval processes are required in the manufacturing, transporting, installing and storing processes, the cost and the working procedures are greatly increased, and the risks of accidental criticality and personnel dosage overrun also exist; the neutron source component becomes radioactive waste after being discharged out of the reactor, and the cost of waste storage and post-treatment is increased. Therefore, the invention provides a reactor charging starting method without an external neutron source, which firstly recycles the neutron source generated by the fuel assembly to carry out the charging and starting processes of the reactor. In the second and subsequent cycles, the reactor is charged and started by the fuel assemblies and the neutron source provided by the irradiated fuel assemblies during operation of the reactor. Firstly, injecting a proper amount of boric acid solution into a reactor core to ensure that the liquid level of the boric acid solution is not higher than the lower limit of an active section of the reactor core; and then, a circle of fuel assemblies are evenly loaded in the outermost layer of the reactor core, a plurality of out-of-stack source range detectors are evenly distributed outside the reactor core, and the fuel assemblies loaded in the outermost layer of the reactor core are preferably close to each out-of-stack source range detector, so that the out-of-stack source range detectors can obtain effective counting, and the effectiveness of the out-of-stack source range detectors can be verified. Then further inject boric acid solution into the reactor core, submerge the reactor core, this will guarantee the critical safety of reactor during the material loading, simultaneously, boric acid solution will make the neutron fluence rate greatly reduced of the external source range detector department of reactor to the massive absorption of neutron, can not obtain effective count, gets into the blind area. And then charging the residual fuel assemblies into the core to complete charging. Then, the effective value-added factor of the reactor is improved, and the subcritical degree is reduced until an external reactor range detector can obtain effective counting, so that a dead zone is eliminated; and finally, determining the state of the reactor core by the counting of the out-of-reactor source range detector, so that the reactor core reaches the critical state of the reactor, and the reactor core can be started. The method is not only suitable for the first charging and starting of the reactor, but also suitable for the second and subsequent circulating charging and starting processes.
And (c) after the fuel assembly is loaded in the step (b), ensuring that each external source range detector obtains effective counting.
When the method is used in the first reactor cycle, all the fuel assemblies are new fuel assemblies;
when the method is used in the second and subsequent cycles of the reactor, the fuel assemblies consist of fresh fuel assemblies and fuel assemblies irradiated by the reactor operation.
Compared with the prior art, the method provided by the invention has the advantages that the neutron source generated by the new fuel assembly is recycled firstly, so that the primary neutron source is not needed to be used in the reactor, and the secondary neutron source is not needed to be used in the reactor by recycling the neutron source generated by the new fuel assembly and the irradiated fuel assembly subsequently. Therefore, the series problems caused by the dependence on an external starting neutron source in the process of loading and starting the reactor in the prior art are solved, and the operation cost of the nuclear power plant is greatly reduced; meanwhile, the risk that the first cycle loading and starting requirements cannot be met due to the fact that the source is strongly and continuously attenuated in the waiting period from the completion of the manufacturing of the primary neutron source to the charging is perfectly avoided, and the approval process of the primary neutron source in the manufacturing, transporting, installing and storing processes is also avoided; and completely overcomes the risks of accidental criticality and personnel dose overruns.
Preferably, the new fuel assembly is square.
Preferably, the method for increasing the effective value-added factor of the reactor and reducing the subcritical degree in the step (e) comprises the following steps: lifting the control rod and/or diluting the boric acid solution.
Preferably, the method for making the reactor core reach the reactor critical in the step (f) is as follows: lifting the control rod and/or diluting the boric acid solution.
Preferably, the reactor core includes 177 groups of fuel assemblies, wherein step (b) is charged with the outermost group 36 and step (d) is charged with the remaining group 141.
Preferably, the number of the out-of-stack source range detectors is four. The reactor core is taken as the circle center, and the corresponding circle center angle between two adjacent out-of-pile source range detectors is 90 degrees.
Compared with the prior art, the invention has the following advantages and beneficial effects:
compared with the prior art, the reactor charging starting method without an additional neutron source firstly recycles the neutron source generated by the new fuel assembly, so that the reactor does not need to use a primary neutron source, and then recycles the neutron source generated by the new fuel assembly and the irradiated fuel assembly, so that the reactor does not need to use a secondary neutron source. Therefore, the series problems caused by the dependence on an external starting neutron source in the process of loading and starting the reactor in the prior art are solved, and the operation cost of the nuclear power plant is greatly reduced; meanwhile, the risk that the first cycle loading and starting requirements cannot be met due to the fact that the source is strongly and continuously attenuated in the waiting period from the completion of the manufacturing of the primary neutron source to the charging is perfectly avoided, and the approval process of the primary neutron source in the manufacturing, transporting, installing and storing processes is also avoided; and completely overcomes the risks of accidental criticality and personnel dose overruns.
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The accompanying drawings, which are included to provide a further understanding of the embodiments of the invention and are incorporated in and constitute a part of this application, illustrate embodiment(s) of the invention and together with the description serve to explain the principles of the invention. In the drawings:
FIG. 1 is a schematic view of a charge of an embodiment of the present invention.
Detailed Description
In order to make the objects, technical solutions and advantages of the present invention more apparent, the present invention is further described in detail below with reference to examples and accompanying drawings, and the exemplary embodiments and descriptions thereof are only used for explaining the present invention and are not meant to limit the present invention.
Example 1:
a reactor charge starting method without an external neutron source comprises the following steps:
(a) injecting a proper amount of boric acid solution into the reactor core, so that the liquid level of the boric acid solution is not higher than the lower limit of the active section of the reactor core;
(b) a circle of fuel assemblies are evenly arranged on the outermost layer of the reactor core, and a plurality of out-of-reactor source range detectors are evenly distributed outside the reactor core;
(c) further injecting boric acid solution into the reactor core to submerge the reactor core and enable the out-of-core source range detector to enter a blind area;
(d) loading the residual fuel assemblies into the reactor core to finish loading;
(e) the effective value-added factor of the reactor is improved, and the subcritical degree is reduced until the reactor external source range detector can obtain effective counting, so that a dead zone is eliminated;
(f) the state of the reactor core is determined by the counting of the out-of-reactor source range detector, so that the reactor core reaches the critical state of the reactor.
Preferably, after the fuel assembly is loaded in the step (b), each of the off-stack source range detectors is guaranteed to obtain a valid count.
Preferably, when the method is used in the reactor lead cycle, all of the fuel assemblies are new fuel assemblies;
when the method is used in the second and subsequent cycles of the reactor, the fuel assemblies consist of fresh fuel assemblies and fuel assemblies irradiated by the reactor operation.
Preferably, the new fuel assembly is square. The method for improving the effective value-added factor of the reactor and reducing the subcritical degree in the step (e) comprises the following steps: lifting the control rod and/or diluting the boric acid solution. The method for making the reactor core reach the critical value of the reactor in the step (f) comprises the following steps: lifting the control rod and/or diluting the boric acid solution.
Compared with the prior art, the method firstly recycles the neutron source generated by the new fuel assembly, so that the reactor does not need to reuse the primary neutron source, and then recycles the neutron source generated by the new fuel assembly and the irradiated fuel assembly, so that the reactor does not need to reuse the secondary neutron source. Therefore, the series problems caused by the dependence on an external starting neutron source in the process of loading and starting the reactor in the prior art are solved, and the operation cost of the nuclear power plant is greatly reduced; meanwhile, the risk that the first cycle loading and starting requirements cannot be met due to the fact that the source is strongly and continuously attenuated in the waiting period from the completion of the manufacturing of the primary neutron source to the charging is perfectly avoided, and the approval process of the primary neutron source in the manufacturing, transporting, installing and storing processes is also avoided; and completely overcomes the risks of accidental criticality and personnel dose overruns.
Example 2:
a reactor charging starting method without an external neutron source is suitable for a reactor adopting a Hualong I reactor technology or an M310 reactor technology. In this embodiment, a hualong first reactor is taken as an example:
when a newly built Hualong I (ACP1000) reactor is firstly circularly charged and started, the method is divided into the following stages:
1. the reactor core is injected with a certain amount of boric acid solution, but the water level is not higher than the lower limit of the active section of the reactor core.
2. The core is loaded with 36 groups of new fuel assemblies which are evenly distributed on the outermost layer of the core and are close to 4 out-of-core source range detectors on the periphery. This will ensure that the off-stack source range detector will obtain a valid count, as shown in figure 1, verifying its validity.
3. Further injection of boric acid solution into the reactor core floods the reactor core which will ensure critical safety of the reactor during charging. However, the neutron fluence rate at the position of the out-of-pile source range detector is greatly reduced due to the large absorption of the boric acid solution to neutrons, so that effective counting cannot be obtained, and the neutrons enter a blind area.
4. The core was charged with the remaining 141 groups of fresh fuel assemblies, completing the charge.
5. Improving the effective value-added factor K of the reactor by lifting the control rod and diluting the boric acid solutioneffThe subcritical degree is reduced, secondary fission neutrons caused by neutrons generated by the new fuel assemblies are increased in the process, and the out-of-pile source range detector can obtain effective counting and get rid of dead zones after the certain subcritical degree is reached.
6. The reactor core state is determined by the counting of the out-of-reactor source range detector, and the reactor criticality is reached by further lifting a control rod or diluting a boric acid solution.
During the second and subsequent cyclic loading and starting processes of the reactor, the processes are still carried out according to the stages 1 to 6, and the main difference is that fuel assemblies loaded in the stages 2 and 4 contain a large number of fuel assemblies irradiated by the operation of the reactor besides part of new fuel assemblies, and the irradiated fuel assemblies provide larger neutron source intensity than the new fuel assemblies and are beneficial to being separated from the dead zone of the out-of-reactor source range detector as soon as possible.
The embodiment firstly recycles the neutron source generated by the new fuel assembly to carry out the charging and starting processes of the reactor. In the second and subsequent cycles, the reactor is charged and started with new fuel assemblies and neutron sources provided by irradiated fuel assemblies during reactor operation.
The above-mentioned embodiments are intended to illustrate the objects, technical solutions and advantages of the present invention in further detail, and it should be understood that the above-mentioned embodiments are merely exemplary embodiments of the present invention, and are not intended to limit the scope of the present invention, and any modifications, equivalent substitutions, improvements and the like made within the spirit and principle of the present invention should be included in the scope of the present invention.

Claims (7)

1. A reactor charge starting method without an external neutron source is characterized by comprising the following steps:
(a) injecting a proper amount of boric acid solution into the reactor core, so that the liquid level of the boric acid solution is not higher than the lower limit of the active section of the reactor core;
(b) a circle of fuel assemblies are evenly arranged on the outermost layer of the reactor core, and a plurality of out-of-reactor source range detectors are evenly distributed outside the reactor core;
(c) further injecting boric acid solution into the reactor core to submerge the reactor core and enable the out-of-core source range detector to enter a blind area;
(d) loading the residual fuel assemblies into the reactor core to finish loading;
(e) the effective value-added factor of the reactor is improved, and the subcritical degree is reduced until the reactor external source range detector can obtain effective counting, so that a dead zone is eliminated;
(f) determining the state of the reactor core by the counting of the out-of-reactor source range detector, so that the reactor core reaches the critical state of the reactor;
and (c) after the fuel assembly is loaded in the step (b), ensuring that each external source range detector obtains effective counting.
2. A method of starting a reactor charge without an external neutron source as defined in claim 1, wherein:
when the method is used in the first reactor cycle, all the fuel assemblies are new fuel assemblies;
when the method is used in the second and subsequent cycles of the reactor, the fuel assemblies consist of fresh fuel assemblies and fuel assemblies irradiated by the reactor operation.
3. A method of starting a reactor charge without an external neutron source as in claim 2 wherein the new fuel assemblies are square.
4. The method for starting a reactor charge without an external neutron source as claimed in claim 1, wherein the method for increasing the effective multiplication factor of the reactor and reducing the subcritical degree in the step (e) comprises the following steps: lifting the control rod and/or diluting the boric acid solution.
5. The method of claim 1, wherein the step (f) of achieving reactor criticality comprises: lifting the control rod and/or diluting the boric acid solution.
6. The method of claim 1, wherein the reactor core includes 177 groups of fuel assemblies, wherein the outermost group 36 is provided in step (b) and the remaining group 141 is provided in step (d).
7. The method of claim 6, wherein there are four off-stack source range detectors.
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