CN111373486B - 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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- CN111373486B CN111373486B CN201880074644.1A CN201880074644A CN111373486B CN 111373486 B CN111373486 B CN 111373486B CN 201880074644 A CN201880074644 A CN 201880074644A CN 111373486 B CN111373486 B CN 111373486B
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- XLYOFNOQVPJJNP-ZSJDYOACSA-N Heavy water Chemical compound [2H]O[2H] XLYOFNOQVPJJNP-ZSJDYOACSA-N 0.000 title claims abstract description 74
- 239000003758 nuclear fuel Substances 0.000 title claims abstract description 44
- 238000000034 method Methods 0.000 title claims abstract description 18
- 230000009257 reactivity Effects 0.000 claims abstract description 48
- 230000001105 regulatory effect Effects 0.000 claims abstract description 37
- 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 19
- 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
- 230000002459 sustained effect Effects 0.000 claims description 3
- 230000002401 inhibitory effect Effects 0.000 claims description 2
- 230000000630 rising effect Effects 0.000 claims description 2
- GUTLYIVDDKVIGB-OUBTZVSYSA-N Cobalt-60 Chemical compound [60Co] GUTLYIVDDKVIGB-OUBTZVSYSA-N 0.000 abstract description 18
- 238000004519 manufacturing process Methods 0.000 abstract description 10
- 230000009467 reduction Effects 0.000 abstract description 3
- 230000005764 inhibitory process Effects 0.000 abstract description 2
- 238000010521 absorption reaction Methods 0.000 description 5
- 230000000694 effects Effects 0.000 description 4
- 238000000605 extraction Methods 0.000 description 4
- 239000000446 fuel Substances 0.000 description 4
- 230000006872 improvement Effects 0.000 description 4
- SAPGTCDSBGMXCD-UHFFFAOYSA-N (2-chlorophenyl)-(4-fluorophenyl)-pyrimidin-5-ylmethanol Chemical compound C=1N=CN=CC=1C(C=1C(=CC=CC=1)Cl)(O)C1=CC=C(F)C=C1 SAPGTCDSBGMXCD-UHFFFAOYSA-N 0.000 description 3
- 241000196324 Embryophyta Species 0.000 description 3
- 230000001965 increasing effect Effects 0.000 description 3
- 230000008569 process Effects 0.000 description 3
- 229910052770 Uranium Inorganic materials 0.000 description 2
- 230000002159 abnormal effect Effects 0.000 description 2
- 239000006096 absorbing agent Substances 0.000 description 2
- 238000009835 boiling Methods 0.000 description 2
- 238000013461 design Methods 0.000 description 2
- 238000005516 engineering process Methods 0.000 description 2
- 230000004048 modification Effects 0.000 description 2
- 238000012986 modification Methods 0.000 description 2
- 229910001220 stainless steel Inorganic materials 0.000 description 2
- 239000010935 stainless steel Substances 0.000 description 2
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 description 2
- YZCKVEUIGOORGS-OUBTZVSYSA-N Deuterium Chemical compound [2H] YZCKVEUIGOORGS-OUBTZVSYSA-N 0.000 description 1
- PEDCQBHIVMGVHV-UHFFFAOYSA-N Glycerine Chemical compound OCC(O)CO PEDCQBHIVMGVHV-UHFFFAOYSA-N 0.000 description 1
- 229910000831 Steel Inorganic materials 0.000 description 1
- 230000000712 assembly Effects 0.000 description 1
- 238000000429 assembly Methods 0.000 description 1
- 230000008901 benefit Effects 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
- 230000001276 controlling effect Effects 0.000 description 1
- 238000001816 cooling Methods 0.000 description 1
- 239000000498 cooling water Substances 0.000 description 1
- 229910052805 deuterium Inorganic materials 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 230000009977 dual effect Effects 0.000 description 1
- 230000002708 enhancing effect Effects 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
- 230000008676 import Effects 0.000 description 1
- 230000007246 mechanism Effects 0.000 description 1
- 230000035515 penetration Effects 0.000 description 1
- 238000010248 power generation Methods 0.000 description 1
- 230000005855 radiation 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
- 230000001629 suppression Effects 0.000 description 1
- 238000012360 testing method Methods 0.000 description 1
- 231100000167 toxic agent Toxicity 0.000 description 1
- 239000003440 toxic substance Substances 0.000 description 1
- 230000007704 transition Effects 0.000 description 1
- 239000002699 waste material Substances 0.000 description 1
Classifications
-
- 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
The present invention suppresses power reduction and enables cobalt-60 production by modifying the material of the tuning rod, provides a method for saving nuclear fuel of heavy water reactor, comprising the steps of: a first step of setting seven regulating rod groups consisting of the first to seventh regulating rod groups to be respectively led in or led out from different parts of the nuclear fuel assembly, and making the reactivity value of the regulating rods constituting the seventh regulating rod group smaller than that of the regulating rods constituting the rest regulating rod groups; and a second step of, when all of the first to seventh adjustment rod groups are drawn out from the nuclear fuel assembly, causing the seventh adjustment rod group to be finally drawn out, capable of preventing a phenomenon that the seventh adjustment rod group is automatically reintroduced due to an automatic rise of the water level of the liquid zone controller to a level higher than the adjustment rod introduction condition water level during the drawing out of the seventh adjustment rod group, eliminating an unnecessary combustion degree inhibition phenomenon caused by the automatic reintroduction of the seventh adjustment rod group, and thereby being capable of 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 changing the material of a tuning rod and producing cobalt-60.
Background
Nuclear power plants constructed and put into use in Korea are roughly classified into a light water reactor type (Light Water Reactor) and a heavy water reactor type (Heavy Water Reactor). This classification is based on whether light water or heavy water is used as a deceleration material for decelerating neutrons to stably perform nuclear power generation.
In addition, the light water reactor needs to increase the concentration of the nuclear fuel to achieve a critical state in which nuclear fission can stably occur, but the heavy water reactor can achieve a critical state even if unconcentrated natural uranium or nuclear fuel with low concentration is used, so that the amount of generated waste is small and the nuclear fuel can be replaced in an operating state. Although heavy water has an advantage in that the neutron travel distance is not required to be long because the neutron absorption is suppressed as compared with light water, and thus the reactor vessel can be miniaturized, heavy water has a disadvantage in that frequent fuel replacement is required in order to increase the operation rate as compared with light water.
A nuclear reactor developed to avoid such an increase in the size of a nuclear reactor vessel and an increase in the concentration of nuclear fuel is a pressure tube type heavy water reactor, and is typically a CANDU type (Canadian Deuterium Uranium) nuclear reactor developed in canada.
Like the light water reactor, the CANDU also includes a boiling heavy water reactor (boiling heavy water reactor, BHWR) that generates steam directly at the core, and a pressurized heavy water reactor (pressurized heavy water reactor, PHWR) that transfers heat from the core to the steam generator to generate steam. The heavy water reactor used in operation worldwide was a Pressurized Heavy Water Reactor (PHWR) except for the 250MWe capacity Gentilly-1, which was closed early.
In the heavy water reactor including machines 1, 2, 3, and 4 currently operated in the city of the month, the nuclear fuel assembly is disposed in a container called a gauntlet (calanderia), heavy water serving as a deceleration material is built in the gauntlet, and cooling water passes through a passage through which a fuel rod is inserted into the gauntlet, and thus 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, in the normal operation, the liquid zone controller (LZC, liquid Zone Controller) is used to automatically control the reactivity, and the reactivity exceeding the LZC control range is automatically controlled by the absorption rod. As shown in fig. 5, the Liquid Zone Controller (LZC) is divided into 14 zones inside the nuclear reactor, and controls the neutron absorption rate of each zone and the local output by appropriately controlling the internal water level in a cylindrical zone division space (zone division) in the vertical direction of each zone.
When the power plant is in a transition state, the power plant is safely controlled by executing a step-down power (Stepback) or a continuous power-down power (Setback) by the absorption rod according to the abnormal signal of the operation variable.
In the event of an abnormal situation (neutron high power, power up, etc.), a first shutdown system (inserted shutdown rod) and a second shutdown system (injected with a toxic substance) operating separately from a control computer (DCC) are started, thereby safely shutting down the power plant.
The adjusting rods are made of stainless steel and arranged in 21 areas of the calandria, and the 21 areas are divided into 7 groups by groups of several adjusting rods, so that the distribution of the reactor core power is flattened. In normal operation, the adjusting rod is fully inserted and kept in a locked state, and the adjusting rod is led out under the condition that positive reactivity is required. Here, the case where positive reactivity is required is a case where a nuclear reactor needs to be restarted within 30 minutes after a sudden stop, a case where a fuel switch fails, or a case where power needs to be reduced in stages or continuously. However, the korean nuclear power plant is not suitable for restarting the plant within 30 minutes after stopping the plant for the purpose of enhancing safety.
The same applies to 21 control rods of heavy water reactor (CANDU-600) in the city of moon, and the control rods are formed into 7 groups (banks), and as shown by red in fig. 1 and 2, are designed to be always inserted into the core during normal operation, thereby functioning as neutron absorbers. Here, the reactivity values of the 7 groups are different.
However, in the conventional 7-group adjusting rod group, as shown in the table of fig. 4, the reactivity value of the seventh group is large, and thus there is a problem that 100% introduction or extraction cannot be performed at one time. For example, when the seventh group is pulled out by 60% in the pulling-out process, the seventh group is pulled out (100% is indicated) in a state where the water level of the Liquid Zone Controller (LZC) is 20%, and the combustion degree increases, which is a reaction to the seventh group, and the water level of the liquid zone controller reaches 70% in order to suppress the combustion degree, but since the water level of the liquid zone controller reaches 70% which is a condition in which the pulled-out seventh group of the adjusting bars is re-pulled in, the seventh group is re-pulled in, and as a result, it is clear that the seventh group cannot be automatically pulled out when the seventh group needs to be pulled out. In this case, it is necessary to switch to manual operation to prevent the extraction and introduction of the seventh group from being automatically driven, and then to extract the adjustment bars 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 results in a problem of increased nuclear fuel consumption for increasing the degree of combustion.
In addition, cobalt-60% 60 Co) is one of the radioisotopes of cobalt. Cobalt-60 is used for photographing steel having a thickness of 5 to 15cm in a radiation penetration test, and cobalt-60 is industrially widely used in medical fields in addition to improvement of chemical fibers, films and the like, sterilization of foods, and improvement of plant species.
Since cobalt-60 does not exist in nature, it is necessary to artificially collide neutrons to cobalt-59 atoms to obtain cobalt-60. Currently, some countries are producing cobalt-60, and korea mainly relies on import from overseas.
Since cobalt-60 may be produced during operation of a nuclear reactor, techniques for producing cobalt-60 during operation of a nuclear reactor already exist. However, the conventional technology for producing cobalt-60 in a nuclear reactor focuses only on the production of cobalt-60, and there is a limitation in that it is impossible to develop a technology for organically coordinating the production process of cobalt-60 with the operation efficiency of the nuclear reactor.
Prior art literature
Korean patent application No. 10-1756952 (authorized date 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 caused by the inability to automatically draw out an adjusting rod in the conventional heavy water reactor, and can greatly reduce the nuclear fuel while maintaining the conventional degree of combustion, thereby not only improving the operating efficiency of the nuclear reactor, but also organically combining 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 configuring two or more regulating rods in such a manner that one regulating rod group is formed, arranging seven regulating rod groups formed by the first to seventh regulating rod groups so as to be respectively led in or led out of different parts of the nuclear fuel assembly, and manufacturing the regulating rod group in such a manner that the reactivity value of the regulating rods is smaller than that of the originally designed regulating rods, wherein the regulating rods are arranged in the nuclear fuel assembly for heavy water piles, and the combustion degree of the nuclear fuel is reduced or increased by leading in or leading out from the nuclear fuel assembly, so that the critical state in which the nuclear fission chain reaction can be sustained is maintained; and a second step of causing the seventh adjustment rod group to be finally drawn out when all of the first to seventh adjustment rod groups are drawn out from the nuclear fuel assembly.
Thus, the phenomenon that the seventh regulating rod group is automatically reintroduced due to the fact that the water level of the liquid zone controller (LZC, liquid Zone Control system) automatically rises above the regulating rod introducing condition water level during the drawing-out of the seventh regulating rod group can be prevented, excessive neutron absorption capacity can be reduced, unnecessary combustion degree inhibition phenomenon caused by the fact that the seventh regulating rod group is automatically reintroduced can be eliminated, and therefore required nuclear fuel can be greatly saved by improving the combustion degree.
In this case, preferably, in the first step, the material of the adjustment bars constituting the seventh adjustment bar group is cobalt-59 (Co-59).
And, it is preferable that the seventh adjustment bar group is made with a small reactivity value so that the sum of reactivity values of all adjustment bars constituting the first to seventh adjustment bar groups is reduced by 10% to 15%.
And, it is preferable that the reactivity value of the sixth regulating bar group of the first to seventh regulating bar groups is further made smaller than the reactivity value of the first to fifth regulating bar groups so that the decrease in reactivity value of all regulating bars constituting the first to seventh regulating bar groups caused by the decrease in reactivity value of the sixth regulating bar group and the seventh regulating bar group is 10% to 15%.
In addition, it is preferable that the adjustment bars constituting the seventh adjustment bar group are made into a bar shape.
Effects of the invention
According to the method for saving nuclear fuel in a heavy water reactor of the present invention, the problems that the conventional adjusting rod which has a problem in a heavy water reactor due to the reduction of the excessive reaction absorber component cannot be automatically led out and the problem of excessive nuclear fuel consumption can be solved, and thus the conventional degree of combustion can be improved, the nuclear fuel can be greatly saved, the operating efficiency of the nuclear reactor can be improved, and the improvement of the operating efficiency of the nuclear reactor and the production of cobalt-60 can be organically combined with each other.
Also, according to the present invention, as the reactivity value of the adjusting rod is reduced by about 2.4mk, as an effect of the rise of the combustibility, the combustion consumption is reduced by 15%, thus saving about 675 bundles of fuel rods per year, thereby having an effect of saving 131 billion Korean units per machine, and having an effect of producing cobalt-60 equivalent to about 9 billion Korean units per year per machine.
Drawings
FIG. 1 is a front sectional view of a heavy water reactor showing an adjustment rod introduced into the core during normal operation.
Fig. 2 is a plan view of a heavy water reactor showing the position of the tuning rods.
Fig. 3 is a side cross-sectional view of a conventional stainless steel tuning rod.
Fig. 4 is a table showing the variation of reactivity of seventh and sixth tuning rod assemblies when introduced into a nuclear reactor in stages.
Fig. 5 is a conceptual diagram showing the liquid zone controller (LZC, liquid Zone Controller).
FIG. 6 is a table comparing the reactivity values of all of the tuning rods to the reactivity values of other combustion control mechanisms than the tuning rods.
Detailed Description
The specific structural and functional descriptions disclosed herein are merely exemplary of embodiments based on the inventive concept, which can be embodied in various forms. And, it should not be construed as being limited to the embodiments described in the present specification, but should be construed to include all modifications, equivalents, and alternatives falling within the spirit and technical scope of the present invention.
The present invention will be described in detail below with reference to the drawings.
The method for saving nuclear fuel of the heavy water reactor comprises the following steps: a first step of arranging two or more adjustment bars so that one adjustment bar group is constituted, arranging seven adjustment bar groups constituted by first to seventh adjustment bar groups so as to be able to be introduced into or extracted from different portions of a nuclear fuel assembly, respectively, and making the seventh adjustment bar group so that the reactivity value of the adjustment bars constituting the seventh adjustment bar group is smaller than the reactivity value of the adjustment bars constituting the remaining adjustment bar groups, wherein the adjustment bars are arranged in the nuclear fuel assembly for a heavy water stack and reduce or increase the degree of combustion of nuclear fuel by being introduced into or extracted from the nuclear fuel assembly, thereby maintaining a critical state in which a nuclear fission chain reaction can be sustained, and a second step of causing the seventh adjustment bar group to be finally extracted when all of the first to seventh adjustment bar groups are extracted from the nuclear fuel assembly.
As described in the above background art section, among the seven groups of the adjustment bars of the heavy water pile currently used in korean operation, as shown in the table of fig. 4, the reactivity value of the seventh group is large, and thus there is a problem in that 100% introduction or extraction cannot be performed at one time.
In this case, the seventh group is pulled out (100% is indicated) in a state where the water level of the Liquid Zone Controller (LZC) is 20%, and in the pulling-out process, when 60% of the seventh group is pulled out of the adjustment rod group, the combustion degree increases, and the liquid zone controller water level reaches 70% in order to suppress the combustion degree, but since the liquid zone controller water level reaches 70% which is a condition where the pulled-out adjustment rod of the seventh group is pulled in again, and as a result, it is clear that the seventh group cannot be pulled out automatically when the seventh group needs to be pulled out. In this case, it is necessary to switch to manual operation to prevent the extraction and introduction of the seventh group from being automatically driven, and then to extract the adjustment bars one by one in the case where the water level is reduced again.
In order to solve the problems caused thereby, the invention proposes a solution in which the reactivity of the actuating rods forming the seventh actuating rod group is smaller than the reactivity values of the remaining actuating rod groups.
Thus, the phenomenon that the seventh regulating rod group is automatically reintroduced due to the automatic rising of the water level of the liquid zone controller (LZC, liquid Zone Control system) above the regulating rod introducing condition water level during the drawing of the seventh regulating rod group can be prevented, and the unnecessary combustion degree inhibiting phenomenon caused by the automatic reintroduction of the seventh regulating rod group can be eliminated, thereby greatly saving the required nuclear fuel by improving the combustion degree.
In particular, in order to prevent the condition that the reintroduction condition of the seventh regulating bar group, that is, the water level of the Liquid Zone Controller (LZC) reaches 70%, the seventh regulating bar group is manufactured with a small reactivity value, thereby reducing the sum of the reactivity values of all the regulating bars constituting the first to seventh regulating bar groups by 10% to 15%.
As shown in the table of FIG. 6, this means that the reactivity of the seventh conventional tuning bar set as shown in the table of FIG. 4 was reduced by 1.3 to 1.8mk at 16.4mk for all tuning bars, in which case the overall reactivity was 16.4mk, reduced by 10% to 15%.
In particular, such a design for reducing the reactivity value of the tuning rod can be achieved by manufacturing the tuning rod using cobalt-59, and in the case of reducing the reactivity value of the tuning rod by such a method for manufacturing the tuning rod using cobalt-59, not only the seventh tuning rod group can be automatically extracted, but also the neutron-absorbed cobalt-59 is automatically generated as cobalt-60, so that the production of cobalt-60, which has heretofore been impossible to be produced in korea, can be achieved in the process of improving the nuclear fuel efficiency of the heavy water reactor, because of the dual effect.
In addition, the following method can be adopted according to the need: in the first to seventh adjustment bar groups, the reactivity value of the sixth adjustment bar group is further made smaller than the reactivity value of the first to fifth adjustment bar groups so that the decrease in reactivity value of all adjustment bars constituting the first to seventh adjustment bar groups caused by the decrease in reactivity value of the sixth and seventh adjustment bar groups is 10% to 15%. In this case, the reactivity of the sixth and seventh adjustment bar 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 tuning rod can be achieved by reducing the cross-sectional diameter size of the tuning rod. When the tuning rod has a cross-sectional diameter at the time of initial design of the nuclear reactor, the tuning rod is tubular with a large cross-sectional diameter and has a large reactivity value, and when the tuning rod is manufactured in a rod shape with a reduced cross-sectional diameter size, the reactivity value can be reduced.
TABLE 1
The present invention described above is not limited to the above-described embodiments and drawings, and various substitutions, modifications and changes may be made without departing from the technical spirit of the present invention, as will be apparent to those skilled in the art to which the present invention pertains.
Claims (3)
1. A method of conserving nuclear fuel in a heavy water stack comprising the steps of:
a first step of arranging two or more adjustment bars in such a manner that one adjustment bar group is constituted, arranging seven adjustment bar groups constituted by a first to seventh adjustment bar groups so as to be able to be introduced into or extracted from different portions of a nuclear fuel assembly, respectively, and arranging the seventh adjustment bar group such that the reactivity value of the adjustment bars constituting the seventh adjustment bar group is smaller than the reactivity value of the adjustment bars constituting the remaining adjustment bar groups, wherein the adjustment bars are arranged in the nuclear fuel assembly for a heavy water stack and reduce or increase the degree of combustion of nuclear fuel by being introduced into or extracted from the nuclear fuel assembly, thereby maintaining a critical state in which a nuclear fission chain reaction can be sustained; and
a second step of, when all of the first to seventh adjustment rod groups are led out from the nuclear fuel assembly, leading out the seventh adjustment rod group finally,
thereby, the phenomenon that the seventh regulating rod group is automatically reintroduced due to the automatic rising of the water level of the liquid zone controller (LZC, liquid Zone Control system) above the regulating rod introducing condition water level during the drawing of the seventh regulating rod group can be prevented, and the unnecessary combustion degree inhibiting phenomenon caused by the automatic reintroduction of the seventh regulating rod group can be eliminated, thereby greatly saving the required nuclear fuel by improving the combustion degree,
in the first step, the material of the adjusting rods constituting the seventh adjusting rod group is cobalt-59 (Co-59),
the seventh tuning rod group is fabricated with a small reactivity so that the sum of reactivity values of all tuning rods constituting the first to seventh tuning rod groups is reduced by 10% to 15%.
2. The method for saving nuclear fuel in a heavy water reactor according to claim 1, 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 adjustment bars constituting the first to seventh adjustment bar groups caused by the decrease in the reactivity values of the sixth adjustment bar group and the seventh adjustment bar group is 10% to 15%.
3. The method for saving nuclear fuel in a heavy water pile according to claim 1, characterized in that the reactivity value of the tuning rods constituting the seventh tuning rod group is reduced by reducing the cross-sectional diameter of the tuning 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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| Publication Number | Publication Date |
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| CN111373486A CN111373486A (en) | 2020-07-03 |
| CN111373486B true CN111373486B (en) | 2023-11-03 |
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| Application Number | Title | Priority Date | Filing Date |
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| CN201880074644.1A Active CN111373486B (en) | 2017-11-28 | 2018-10-10 | Method for saving nuclear fuel of heavy water reactor |
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| KR (1) | KR102060778B1 (en) |
| CN (1) | CN111373486B (en) |
| WO (1) | WO2019107733A1 (en) |
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| JPH01172798A (en) * | 1987-12-26 | 1989-07-07 | Hitachi Ltd | Pressure tube type reactor |
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| CN101252025A (en) * | 2008-03-13 | 2008-08-27 | 上海核工程研究设计院 | Heavy water stack cobalt regulating rod component |
| CN101911211A (en) * | 2007-12-26 | 2010-12-08 | 钍能源股份有限公司 | Nuclear reactor (optionally), be used for nuclear reactor (optionally) seed region-renewing zone sub-component fuel assembly and be used for the fuel element of fuel assembly |
| CN102915774A (en) * | 2011-08-02 | 2013-02-06 | 李代甫 | Nuclear reactor and nuclear reactor shutdown method |
| CN103377736A (en) * | 2012-04-27 | 2013-10-30 | 上海核工程研究设计院 | Cobalt rod cluster part in cobalt regulating rod assembly |
| 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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| CN111373486A (en) | 2020-07-03 |
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