CN111373486A - Method for saving nuclear fuel of heavy water reactor - Google Patents
Method for saving nuclear fuel of heavy water reactor Download PDFInfo
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- CN111373486A CN111373486A CN201880074644.1A CN201880074644A CN111373486A CN 111373486 A CN111373486 A CN 111373486A CN 201880074644 A CN201880074644 A CN 201880074644A CN 111373486 A CN111373486 A CN 111373486A
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- XLYOFNOQVPJJNP-ZSJDYOACSA-N Heavy water Chemical compound [2H]O[2H] XLYOFNOQVPJJNP-ZSJDYOACSA-N 0.000 title claims abstract description 76
- 239000003758 nuclear fuel Substances 0.000 title claims abstract description 48
- 238000000034 method Methods 0.000 title claims abstract description 21
- 230000009257 reactivity Effects 0.000 claims abstract description 51
- 230000001105 regulatory effect Effects 0.000 claims abstract description 27
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 25
- 238000002485 combustion reaction Methods 0.000 claims abstract description 21
- 239000007788 liquid Substances 0.000 claims abstract description 14
- 239000000463 material Substances 0.000 claims abstract description 7
- GUTLYIVDDKVIGB-IGMARMGPSA-N cobalt-59 atom Chemical compound [59Co] GUTLYIVDDKVIGB-IGMARMGPSA-N 0.000 claims description 8
- 238000006243 chemical reaction Methods 0.000 claims description 5
- 230000004992 fission Effects 0.000 claims description 4
- 230000000630 rising effect Effects 0.000 claims description 3
- 238000000605 extraction Methods 0.000 claims 1
- GUTLYIVDDKVIGB-OUBTZVSYSA-N Cobalt-60 Chemical compound [60Co] GUTLYIVDDKVIGB-OUBTZVSYSA-N 0.000 abstract description 19
- 238000004519 manufacturing process Methods 0.000 abstract description 9
- 230000008569 process Effects 0.000 abstract description 5
- 230000009467 reduction Effects 0.000 abstract description 3
- 230000001629 suppression Effects 0.000 abstract description 3
- 230000008859 change Effects 0.000 abstract description 2
- 230000003750 conditioning effect Effects 0.000 description 10
- 230000000694 effects Effects 0.000 description 6
- 239000000446 fuel Substances 0.000 description 4
- 230000006872 improvement Effects 0.000 description 4
- 239000006096 absorbing agent Substances 0.000 description 3
- PEDCQBHIVMGVHV-UHFFFAOYSA-N Glycerine Chemical compound OCC(O)CO PEDCQBHIVMGVHV-UHFFFAOYSA-N 0.000 description 2
- 238000010521 absorption reaction Methods 0.000 description 2
- 230000001276 controlling effect Effects 0.000 description 2
- 238000013461 design Methods 0.000 description 2
- 238000005516 engineering process Methods 0.000 description 2
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- 238000012986 modification Methods 0.000 description 2
- 230000004044 response Effects 0.000 description 2
- 229910001220 stainless steel Inorganic materials 0.000 description 2
- 239000010935 stainless steel Substances 0.000 description 2
- 241000196324 Embryophyta Species 0.000 description 1
- 229910000831 Steel Inorganic materials 0.000 description 1
- 229910052770 Uranium Inorganic materials 0.000 description 1
- 230000002159 abnormal effect Effects 0.000 description 1
- 230000005856 abnormality Effects 0.000 description 1
- 230000008901 benefit Effects 0.000 description 1
- 238000009835 boiling Methods 0.000 description 1
- 229910017052 cobalt Inorganic materials 0.000 description 1
- 239000010941 cobalt Substances 0.000 description 1
- GUTLYIVDDKVIGB-UHFFFAOYSA-N cobalt atom Chemical compound [Co] GUTLYIVDDKVIGB-UHFFFAOYSA-N 0.000 description 1
- 238000001816 cooling Methods 0.000 description 1
- 239000000498 cooling water Substances 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 239000000835 fiber Substances 0.000 description 1
- 235000013305 food Nutrition 0.000 description 1
- JEGUKCSWCFPDGT-UHFFFAOYSA-N h2o hydrate Chemical compound O.O JEGUKCSWCFPDGT-UHFFFAOYSA-N 0.000 description 1
- 238000003384 imaging method Methods 0.000 description 1
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- 230000035515 penetration Effects 0.000 description 1
- 231100000614 poison Toxicity 0.000 description 1
- 238000010248 power generation Methods 0.000 description 1
- 230000005855 radiation Effects 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
- 239000010959 steel Substances 0.000 description 1
- 230000001954 sterilising effect Effects 0.000 description 1
- 238000004659 sterilization and disinfection Methods 0.000 description 1
- 239000000126 substance Substances 0.000 description 1
- 238000006467 substitution reaction Methods 0.000 description 1
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- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 description 1
- 239000002699 waste material Substances 0.000 description 1
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
- G21C7/26—Control of nuclear reaction by displacement of the moderator or parts thereof by changing the moderator concentration
-
- C—CHEMISTRY; METALLURGY
- C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
- C22C—ALLOYS
- C22C19/00—Alloys based on nickel or cobalt
- C22C19/07—Alloys based on nickel or cobalt based on cobalt
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C5/00—Moderator or core structure; Selection of materials for use as moderator
- G21C5/12—Moderator or core structure; Selection of materials for use as moderator characterised by composition, e.g. the moderator containing additional substances which ensure improved heat resistance of the moderator
-
- 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
-
- 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
- Y10—TECHNICAL SUBJECTS COVERED BY FORMER USPC
- Y10S—TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y10S376/00—Induced nuclear reactions: processes, systems, and elements
- Y10S376/90—Particular material or material shapes for fission reactors
- Y10S376/904—Moderator, reflector, or coolant materials
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- Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- Chemical & Material Sciences (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Materials Engineering (AREA)
- Mechanical Engineering (AREA)
- Metallurgy (AREA)
- Organic Chemistry (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
More particularly, the present invention relates to a method for saving nuclear fuel, which suppresses unnecessary power reduction by adjusting a change in material of a rod and enables production of cobalt-60, and provides a method for saving nuclear fuel for a heavy water reactor, comprising the steps of: a first step of arranging seven regulating rod groups, which are composed of first to seventh regulating rod groups, so as to be introduced or withdrawn to or from different portions of the nuclear fuel assembly, respectively, and making the reactivity value of the regulating rods constituting the seventh regulating rod group smaller than the reactivity values of the regulating rods constituting the remaining regulating rod groups; and a second step of drawing out the seventh adjusting rod group last when all of the first to seventh adjusting rod groups are drawn out from the nuclear fuel assembly, thereby preventing an automatic reintroduction phenomenon of the seventh adjusting rod group caused by the automatic rise of the water level of the liquid zone controller above the adjusting rod introduction condition water level during the drawing-out process of the seventh adjusting rod group, eliminating an unnecessary combustion degree suppression phenomenon caused by the automatic reintroduction of the seventh adjusting rod group, and greatly saving the required nuclear fuel by improving the combustion degree.
Description
Technical Field
The present invention relates to a method for saving nuclear fuel, and more particularly, to a method for saving nuclear fuel capable of suppressing unnecessary power reduction by modifying the material of a tuning bar and producing cobalt-60.
Background
Nuclear power plants built and put into use in korea are roughly classified into a Light Water Reactor (Light Water Reactor) and a Heavy Water Reactor (Heavy Water Reactor). This classification is based on whether light water or heavy water is used as a decelerating material that can stably perform nuclear power generation by decelerating neutrons.
In addition, the light water reactor needs to increase the enrichment degree of nuclear fuel to reach a critical state in which nuclear fission can be stably generated, but the heavy water reactor can reach a critical state even if non-enriched natural uranium or nuclear fuel with low enrichment degree is used, so that the amount of waste generated is small and the nuclear fuel can be replaced in an operating state. Although heavy water has an advantage that the reactor vessel can be downsized because absorption of neutrons is suppressed and the travel distance of neutrons does not need to be long as compared with light water, the heavy water reactor has a drawback that fuel replacement is required frequently to improve the operating rate as compared with the light water reactor.
A nuclear reactor developed to avoid such an increase in the size of a nuclear reactor vessel and an increase in the nuclear fuel enrichment is a pressure tube type heavy water reactor, and typically a CANDU (Canadian nuclear reactor) type nuclear reactor developed in canada.
Like the light water reactor, the CANDU also includes a Boiling Heavy Water Reactor (BHWR) that directly generates steam in the core, and a Pressurized Heavy Water Reactor (PHWR) that transfers heat of the core to a steam generator to generate steam. The heavy water heap used for worldwide operations is a pressurized heavy water heap (PHWR) with the exception of the 250MWe capacity gentily-1 which was shut down early.
The heavy water reactor used in domestic operation in korea includes machines No. 1, 2, 3, and 4 currently operated in the moon city, in which a nuclear fuel assembly is provided in a container called a Calandria (calandra), heavy water used as a deceleration material is built in the Calandria, and cooling water passes through a channel for inserting a fuel rod into the Calandria, so that the heavy water and the cooling material are spatially separated from each other.
When the heavy water reactor nuclear power station is in output operation, the reactivity of the whole reactor core and each region is automatically adjusted by the reactivity control device. That is, during normal operation, the reactivity is automatically controlled by a Liquid Zone Controller (LZC), and the reactivity outside the LZC control range is automatically controlled by the absorber. As shown in fig. 5, the Liquid Zone Controller (LZC) is divided into 14 zones in the reactor, and the neutron absorptance of each zone is adjusted and the local output is controlled by appropriately controlling the internal water level in a cylindrical zone partition space (zone component) in the vertical direction of each zone.
When the power station is in a transient state, the power is reduced in stages (Stepback) or continuously (Setback) by the absorption rods according to the operation variable abnormality signal, thereby safely controlling the power station.
When abnormal conditions (high neutron power, power increase and the like) occur, a first shutdown system (inserting shutdown rods) and a second shutdown system (injecting toxic substances) which are operated separately from a control computer (DCC) are started, so that the power station is safely shut down.
The adjusting rods are made of stainless steel and are arranged in 21 regions of the rack pipe, and the 21 regions are divided into 7 groups by using several adjusting rods as a group, so that the distribution of the core power is flattened. In normal operation, the control rod is fully inserted and held in a locked state, and the control rod is pulled out when a positive reactivity is required. Here, the case where a positive reactivity is required is a case where a reactor needs to be restarted within 30 minutes after a sudden shutdown, a case where a fuel exchanger fails, or a case where power needs to be reduced in stages and power needs to be reduced continuously. However, the korean nuclear power plant is not suitable for restarting the power plant within 30 minutes after the power plant is stopped in order to enhance safety.
The same total of 21 control rods for the heavy water reactor (CANDU-600) in the moon city are also configured into 7 groups (banks), and are designed to be inserted into the core at all times during normal operation as shown by red in fig. 1 and 2, thereby functioning as neutron absorbers. Here, the reactivity values of the 7 groups were different from each other.
However, in the conventional 7-group set of control rods, as shown in the table of fig. 4, the reactivity value of the seventh group was large, and there was a problem that the reaction was not 100% introduced or withdrawn at a time. For example, when the drawing of the seventh group is started (instruction 100%) in a state where the water level of the Liquid Zone Controller (LZC) is 20%, in the drawing process, when the drawing of the seventh group of the adjustment rod group is 60%, the water level of the liquid zone controller is 70% for suppressing the combustion degree in response to the drawing of the seventh group, but the water level of the liquid zone controller is 70% under the condition that the drawn adjustment rod of the seventh group is drawn again, and therefore the seventh group is drawn again, and as a result, it is clear that the drawing of the seventh group is necessary but the seventh group cannot be automatically drawn. In this case, it is necessary to switch to manual to prevent the drawing-out and drawing-in of the seventh group from being automatically driven, and then to draw out the regulating rods one by one in the case where the water level is reduced again.
Therefore, the seventh group cannot be drawn out when necessary, and as a result, unnecessary suppression of the degree of combustion occurs, which leads to a problem that the consumption of nuclear fuel increases in order to increase the degree of combustion.
In addition, cobalt-60 (60Co) is one of the radioactive isotopes of cobalt. Cobalt-60 is used for imaging steel having a thickness of 5 to 15cm in a radiation penetration test, and in industry, cobalt-60 is widely used in medical applications in addition to improvement of chemical fibers, films and the like, sterilization of foods, and improvement of plant varieties.
Since cobalt-60 does not exist in nature, it is necessary to artificially collide neutrons against cobalt-59 atoms to obtain cobalt-60. Currently, some countries are producing cobalt-60, and korea relies mainly on import from overseas.
The art of generating cobalt-60 during operation of nuclear reactors has long existed, since cobalt-60 can be generated during operation of nuclear reactors. However, the existing technology for generating cobalt-60 in a nuclear reactor focuses only on the production of cobalt-60, and there is a limitation that the technology for organically coordinating the cobalt-60 production process with the operation efficiency of the nuclear reactor cannot be developed.
Documents of the prior art
Korean patent laid-open publication No. 10-1756952 (grant day 2017.07.05)
Disclosure of Invention
Problems to be solved by the invention
In view of the above, an object of the present invention is to provide a method for saving nuclear fuel in a heavy water reactor, which can solve the problem of excessive consumption of nuclear fuel due to the inability to automatically draw out a control rod in a conventional heavy water reactor, and can improve the operating efficiency of the nuclear reactor by significantly reducing the nuclear fuel while maintaining the conventional combustion degree, and can organically combine the improvement of the operating efficiency of the nuclear reactor with the production of cobalt-60.
Means for solving the problems
The method for saving heavy water nuclear fuel according to the present invention for achieving the above object comprises the steps of: a first step of arranging the control rods such that two or more control rods constitute a control rod group, setting seven control rod groups, each of which is composed of first to seventh control rod groups, to be capable of being introduced into or withdrawn from different parts of the nuclear fuel assembly, respectively, and manufacturing the control rod groups in such a manner that the reactivity of the control rods is smaller than a reactivity value of an originally designed control rod, wherein the control rods are provided in the nuclear fuel assembly for the heavy water reactor, and reduce or increase a degree of combustion of the nuclear fuel by introducing or withdrawing the nuclear fuel assembly into or from the nuclear fuel assembly, thereby maintaining a critical state in which the nuclear fission chain reaction can be sustained; and a second step of, when all of the first to seventh adjusting rod groups are drawn out from the nuclear fuel assembly, causing the seventh adjusting rod group to be drawn out last.
Accordingly, it is possible to prevent the seventh adjusting rod group from being automatically reintroduced due to the water level of the Liquid Zone Controller (LZC) automatically rising to the adjusting rod introduction condition water level or more in the process of withdrawing the seventh adjusting rod group, and it is possible to reduce the excessive neutron absorbing capacity, eliminate the unnecessary combustion degree suppressing phenomenon due to the automatic reintroduction of the seventh adjusting rod group, and greatly save the required nuclear fuel by improving the combustion degree.
In this case, it is preferable that, in the first step, the material of the adjustment rods constituting the seventh adjustment rod group is cobalt-59 (Co-59).
And, preferably, the seventh adjusting rod group is made with a small reactivity value so that the sum of the reactivity values of all the adjusting rods constituting the first to seventh adjusting rod groups is reduced by 10 to 15%.
And, preferably, the reactivity value of the sixth adjusting rod group of the first to seventh adjusting rod groups is further made smaller than the reactivity values of the first to fifth adjusting rod groups so that the decrease in the reactivity values of all the adjusting rods constituting the first to seventh adjusting rod groups, which is caused by the decrease in the reactivity values of the sixth adjusting rod group and the seventh adjusting rod group, is 10 to 15%.
In addition, it is preferable that the adjusting rods constituting the seventh adjusting rod group are made rod-shaped.
Effects of the invention
According to the method for saving nuclear fuel in a heavy water reactor of the present invention, it is possible to solve the problems that the conventional control rod, which has a problem in the heavy water reactor due to the reduction of the excessive reaction absorber component, cannot be automatically drawn out and the nuclear fuel is excessively consumed, thereby achieving the effects of improving the conventional combustion degree and greatly saving the nuclear fuel, improving the operating efficiency of the nuclear reactor, and organically combining the improvement of the operating efficiency of the nuclear reactor and the production of cobalt-60.
Also, according to the present invention, as the reactivity value of the conditioning rod is reduced by about 2.4mk, combustion consumption is reduced by 15% as an effect of the increase of the combustion degree, and thus fuel rods are saved by about 675 bundles every year, thereby having an effect of saving 131 billion won per machine, and having an effect of producing cobalt-60 equivalent to about 9 billion won per machine per year.
Drawings
Fig. 1 is an elevational cross-section of a heavy water reactor showing a conditioning rod being introduced into the core during normal operation.
Fig. 2 is a plan view of a heavy water reactor showing the position of the adjustment rods.
Fig. 3 is a side sectional view of a conventional stainless steel conditioning bar.
Fig. 4 is a table showing the change in reactivity when the seventh and sixth groups of regulating rods are introduced into the nuclear reactor in stages.
Fig. 5 is a conceptual diagram showing a Liquid Zone Controller (LZC).
Fig. 6 is a table comparing the reactivity values of all the pilot rods with the reactivity values of the other combustion control mechanisms than the pilot rods.
Detailed Description
The specific structures and functional explanations disclosed in the embodiments of the present invention are merely examples for explaining the embodiments based on the concept of the present invention, and the embodiments based on the concept of the present invention can be implemented in various forms. The present invention is not to be construed as being limited to the embodiments described herein, and all modifications, equivalents, and alternatives falling within the spirit and technical scope of the present invention are intended to be included therein.
The present invention will be described in detail below with reference to the accompanying drawings.
The method for saving the nuclear fuel of the heavy water reactor comprises the following steps: a first step of arranging the regulating rods such that two or more regulating rods constitute one regulating rod group, and arranging seven regulating rod groups, each of which is composed of first to seventh regulating rod groups, so as to be capable of being introduced or withdrawn to different locations of the nuclear fuel assembly, and the seventh regulating rod group is made such that the reactivity value of the regulating rods constituting the seventh regulating rod group is smaller than the reactivity values of the regulating rods constituting the remaining regulating rod groups, wherein the adjusting rod is provided to the nuclear fuel assembly for heavy water reactor and reduces or increases a degree of combustion of nuclear fuel by being introduced into or withdrawn from the nuclear fuel assembly, thereby maintaining a critical state in which a nuclear fission chain reaction can be continued, and a second step, when all of the first to seventh adjusting rod groups are led out of the nuclear fuel assembly, the seventh adjusting rod group is finally led out.
As described in the background art section above, among the seven groups of the heavy water stacks currently used in korean operation, the seventh group has a large reactivity value as shown in the table of fig. 4, and thus has a problem in that 100% of the heavy water stacks cannot be introduced or withdrawn at a time.
In this case, the drawing of the seventh group is started (indicated 100%) in a state where the water level of the Liquid Zone Controller (LZC) is 20%, and in the course of drawing, when the seventh group of the adjustment rod groups is drawn by 60%, the combustion degree rises in response to the drawing of the seventh group, and the water level of the liquid zone controller reaches 70% to suppress the combustion degree, but the liquid zone controller water level reaches 70% under the condition that the drawn adjustment rod of the seventh group is drawn again, and therefore the seventh group is drawn again, and as a result, it is clear that the seventh group cannot be automatically drawn in a case where the drawing of the seventh group is necessary. In this case, it is necessary to switch to manual to prevent the drawing-out and drawing-in of the seventh group from being automatically driven, and then to draw out the regulating rods one by one in the case where the water level is reduced again.
In order to solve the problems caused by this, the invention proposes a solution in which the reactivity of the control rods forming the seventh control rod group is lower than the reactivity values of the remaining control rod groups.
Accordingly, it is possible to prevent the seventh adjusting rod group from being automatically reintroduced due to the water level of the Liquid Zone Controller (LZC) automatically rising to the adjusting rod introduction condition water level or more in the drawing process of the seventh adjusting rod group, and to eliminate the unnecessary combustion degree suppression phenomenon due to the automatic reintroduction of the seventh adjusting rod group, thereby greatly saving the required nuclear fuel by increasing the combustion degree.
In particular, in order to prevent the condition of re-introduction of the seventh adjustment rod set, that is, the condition that the water level of the Liquid Zone Controller (LZC) reaches 70%, the seventh adjustment rod set is manufactured with a small reactivity value, so that the sum of the reactivity values of all the adjustment rods constituting the first to seventh adjustment rod sets is reduced by 10% to 15%.
As shown in the table of FIG. 6, this means that when the reactivity of all the control rods is 16.4mk, the reactivity of the seventh conventional control rod group, 3.46mk, as shown in the table of FIG. 4, is reduced by 1.3 to 1.8mk, in which case the overall reactivity is 16.4mk, which is reduced by 10 to 15%.
In particular, such a design of reducing the reactivity value of the conditioning rods can be achieved by fabricating the conditioning rods using cobalt-59, and in the case of reducing the reactivity value of the conditioning rods by such a method of fabricating the conditioning rods using cobalt-59, not only the seventh conditioning rod group can be automatically drawn out, but also cobalt-59 having absorbed neutrons is automatically generated into cobalt-60, and thus it is possible to achieve the production of cobalt-60, which has not been produced so far in korea, in the process of improving the nuclear fuel efficiency of the heavy water stack, because of a double effect.
In addition, the method can be made as follows according to the requirement: in the first to seventh adjusting rod groups, the reactivity value of the sixth adjusting rod group is further made smaller than the reactivity values of the first to fifth adjusting rod groups so that the decrease in the reactivity values of all the adjusting rods constituting the first to seventh adjusting rod groups, which is caused by the decrease in the reactivity values of the sixth and seventh adjusting rod groups, is 10 to 15%. In this case, the reactivity of the sixth and seventh control rod groups is reduced by 1.3 to 1.8mk in total.
In this case, the adjustment of the reactivity value at the time of manufacturing the conditioning rod can be achieved by reducing the sectional diameter size of the conditioning rod. When the adjusting rod has a cross-sectional diameter at the time of initial design of the nuclear reactor, the adjusting rod has a tubular shape with a large cross-sectional diameter and a large reactivity value, and when the adjusting rod is made into a rod shape with a reduced cross-sectional diameter, the reactivity value can be reduced.
[ Table 1]
It will be apparent to those skilled in the art that the present invention described above is not limited to the above embodiments and the accompanying drawings, and that various substitutions, modifications and changes can be made without departing from the technical spirit of the present invention.
Claims (5)
1. A method of conserving nuclear fuel in a heavy water reactor, comprising the steps of:
a first step of arranging the control rods such that two or more control rods constitute one control rod group, arranging seven control rod groups, each of which is composed of first to seventh control rod groups, so as to be capable of being introduced into or withdrawn from different portions of a nuclear fuel assembly, and making the seventh control rod group such that a reactivity value of the control rods constituting the seventh control rod group is smaller than reactivity values of the control rods constituting the remaining control rod groups, wherein the control rods are provided in the nuclear fuel assembly for a heavy water reactor and reduce or increase a degree of combustion of nuclear fuel by introducing or withdrawing the nuclear fuel assembly, thereby maintaining a critical state in which a nuclear fission chain reaction can continue; and
a second step of, when all of the first to seventh adjusting rod groups are introduced from the nuclear fuel assembly, causing the seventh adjusting rod group to be introduced last,
accordingly, it is possible to prevent the seventh adjusting rod group from being automatically reintroduced due to the water level of the Liquid Zone Controller (LZC) automatically rising to the adjusting rod introduction condition water level or more in the course of the extraction of the seventh adjusting rod group, and to eliminate the unnecessary combustion degree suppressing phenomenon due to the automatic reintroduction of the seventh adjusting rod group, thereby greatly saving the required nuclear fuel by increasing the combustion degree.
2. The method for saving nuclear fuel of a heavy water reactor according to claim 1, wherein, in the first step, the material of the regulating rods constituting the seventh regulating rod group is cobalt-59 (Co-59).
3. The method for saving nuclear fuel of a heavy water reactor according to claim 2, wherein the seventh adjusting rod group is fabricated with a small reactivity so that the sum of reactivity values of all the adjusting rods constituting the first to seventh adjusting rod groups is reduced by 10 to 15%.
4. The method for saving nuclear fuel of a heavy water reactor according to claim 2, wherein the reactivity value of the sixth adjusting rod group of the first to seventh adjusting rod groups is made smaller than the reactivity value of the first to fifth adjusting rod groups,
so that the decrease in the reactivity values of all the regulating rods constituting the first to seventh regulating rod groups, which is caused by the decrease in the reactivity values of the sixth and seventh regulating rod groups, is 10 to 15%.
5. The method for saving nuclear fuel of a heavy water reactor according to claim 2, wherein the reactivity value of the regulating rods constituting the seventh regulating rod group is reduced by reducing the sectional diameter of the regulating rods.
Applications Claiming Priority (3)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| KR1020170160484A KR102060778B1 (en) | 2017-11-28 | 2017-11-28 | Method of reducing nuclear fuel for heavy-water reactor |
| KR10-2017-0160484 | 2017-11-28 | ||
| PCT/KR2018/011878 WO2019107733A1 (en) | 2017-11-28 | 2018-10-10 | Method for saving fuel in heavy water reactor |
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| CN111373486A true CN111373486A (en) | 2020-07-03 |
| CN111373486B CN111373486B (en) | 2023-11-03 |
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| KR (1) | KR102060778B1 (en) |
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| WO2015199372A1 (en) * | 2014-06-24 | 2015-12-30 | 박윤원 | Method for preparing isotopes using heavy water nuclear reactor |
| KR101756952B1 (en) * | 2016-01-07 | 2017-07-12 | 한국원자력연구원 | Isotropes of cobalt production method in heavy water reactor |
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| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
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| KR20190061773A (en) | 2019-06-05 |
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