CN113871045B - Method for achieving critical loading of reactor core of high-temperature gas cooled reactor - Google Patents
Method for achieving critical loading of reactor core of high-temperature gas cooled reactor Download PDFInfo
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- CN113871045B CN113871045B CN202111112704.4A CN202111112704A CN113871045B CN 113871045 B CN113871045 B CN 113871045B CN 202111112704 A CN202111112704 A CN 202111112704A CN 113871045 B CN113871045 B CN 113871045B
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- 238000000034 method Methods 0.000 title claims abstract description 22
- 239000000446 fuel Substances 0.000 claims abstract description 55
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 claims description 7
- 229910002804 graphite Inorganic materials 0.000 claims description 7
- 239000010439 graphite Substances 0.000 claims description 7
- 238000010521 absorption reaction Methods 0.000 claims description 5
- 239000000203 mixture Substances 0.000 abstract 2
- 230000009257 reactivity Effects 0.000 description 4
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 3
- XLYOFNOQVPJJNP-ZSJDYOACSA-N Heavy water Chemical compound [2H]O[2H] XLYOFNOQVPJJNP-ZSJDYOACSA-N 0.000 description 2
- 238000013213 extrapolation Methods 0.000 description 2
- 230000009286 beneficial effect Effects 0.000 description 1
- 238000007664 blowing Methods 0.000 description 1
- 238000009835 boiling Methods 0.000 description 1
- 238000004364 calculation method Methods 0.000 description 1
- 230000007547 defect Effects 0.000 description 1
- 230000004992 fission Effects 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 238000012544 monitoring process Methods 0.000 description 1
- 239000002245 particle Substances 0.000 description 1
- 239000002574 poison Substances 0.000 description 1
- 231100000614 poison Toxicity 0.000 description 1
- 230000001105 regulatory effect Effects 0.000 description 1
Classifications
-
- 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
- G21C19/202—Arrangements for handling ball-form, i.e. pebble fuel
-
- 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
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- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention discloses a method for achieving critical loading of a high-temperature gas cooled reactor core, which comprises the following steps: 1) Preparing; 2) Loading a third theoretical critical loading of mixed fuel into the reactor core; 3) Loading the core with a blend of one third of the difference between the theoretical critical loading and the current loaded blend; 4) Determining the loading capacity of the next step, loading the reactor core, and then turning to the step 3) until the difference between the minimum extrapolated critical loading capacity and the current loading capacity is smaller than N mixed fuels, and then turning to the step 5); 5) Inserting a group of control rods to Mmm height, adding K mixed fuels on the basis of the last extrapolated critical loading capacity, and then feeding the mixed fuels into a reactor core; after all the mixed fuel is filled into the reactor core, a group of control rods which are inserted downwards are gradually lifted until the reactor is in a critical state by the out-of-core nuclear testing instrument.
Description
Technical Field
The invention belongs to the field of high-temperature gas cooled reactors, and particularly relates to a method for achieving critical loading of a reactor core of a high-temperature gas cooled reactor.
Background
At present, water-cooled reactors such as pressurized water reactors, boiling water reactors, heavy water reactors and the like rely on lifting of control rod groups to reach the critical reactor core. Because the structure of the reactor core of the pebble-bed high-temperature gas cooled reactor is completely different from that of a water cooled reactor, the fuel elements are graphite coated particle spherical fuel elements, and the critical operation of the reactor can be carried out after a certain number of reactor core fuel elements are required to be filled. If the pebble-bed high-temperature gas cooled reactor reaches the critical value by lifting the control rod at the initial stage of reactor core loading, a certain risk exists: firstly, no fission poison exists in the reactor core at the initial stage of reactor loading, the residual reactivity of the fuel is high, the introduced reactivity of the lifting control rod is faster, and the safety of the reactor is not facilitated; secondly, the reactor control rod is not calibrated in reactivity value, so that a clear gap exists between critical extrapolation calculation and actual critical rod positions, and uncertainty risks are brought to critical operation of the reactor.
Disclosure of Invention
The invention aims to overcome the defects of the prior art and provides a method for achieving critical loading of a high-temperature gas cooled reactor core, which can achieve critical loading of the high-temperature gas cooled reactor core and has higher safety.
In order to achieve the above purpose, the method for achieving critical loading of the high-temperature gas cooled reactor core comprises the following steps:
1) Preparing;
2) Filling mixed fuel with one third theoretical critical loading capacity into the reactor core, and recording the neutron count rate of an out-of-core nuclear measuring instrument;
3) Loading mixed fuel of one third of the difference between the theoretical critical loading capacity and the current loaded mixed fuel loading capacity into the reactor core, and recording the neutron count rate of an out-of-core nuclear measuring instrument;
4) Calculating an extrapolated critical load according to the neutron count rate of the out-of-core nuclear measuring instrument recorded in the step 3) and the neutron count rate of the out-of-core nuclear measuring instrument recorded in the step 2), taking the smaller value between the calculated extrapolated critical load and the theoretical critical load, making a difference with the current mixed fuel load, taking one third of the difference result as the load of the next step, loading the core, and then turning to the step 3) until the difference value between the minimum extrapolated critical load and the current load is smaller than N mixed fuels, and then turning to the step 5);
5) Inserting a group of control rods to Mmm height, adding K mixed fuels on the basis of the last extrapolated critical loading capacity, and then feeding the mixed fuels into a reactor core;
After all the mixed fuel is filled into the reactor core, gradually lifting a group of control rods which are inserted down until the reactor reaches a critical state by the out-of-core nuclear testing instrument.
N＝800。
M＝6000。
K＝450。
The specific operation process of the step 1) is as follows:
in the critical process of the reactor core of the pebble-bed high-temperature gas cooled reactor, all absorption balls are blown into a ball storage tank at the upper part of the reactor core, all control rods are lifted to the upper limit position at the top of the reactor core, the reactor core is at normal pressure, and a primary loop of the reactor core is in an air atmosphere.
All control rods comprise a shutdown rod, an adjusting rod and a compensating rod.
The mixed fuel comprises 4.2% enriched fuel elements and graphite nodules, wherein the part ratio of the 4.2% enriched fuel elements to the graphite nodules is 7:8.
The invention has the following beneficial effects:
When the method for achieving the critical loading of the high-temperature gas cooled reactor core is specifically operated, the mixed fuel is used for replacing the traditional fuel ball, the residual reactivity of the reactor core fuel is smaller and is easier to control, meanwhile, a gradual filling mode is adopted, when the difference between the minimum extrapolated critical loading capacity and the current loading capacity is smaller than N mixed fuels, a group of control rods are inserted, K mixed fuels are added on the basis of the last extrapolated critical loading capacity, and then the K mixed fuels are fed into the reactor core; after all the mixed fuel is filled into the reactor core, a group of control rods which are inserted downwards are gradually lifted until the reactor is in a critical state by the out-of-core nuclear testing instrument, so that the high-temperature gas cooled reactor core is in critical state, and the safety is higher.
Drawings
The accompanying drawings, which are included to provide a further understanding of the invention and are incorporated in and constitute a part of this specification, illustrate embodiments of the invention and together with the description serve to explain the invention. In the drawings:
FIG. 1 is a flow chart of the present invention.
Detailed Description
In order that those skilled in the art will better understand the present invention, a technical solution in the embodiments of the present invention will be clearly and completely described below with reference to the accompanying drawings in which it is apparent that the described embodiments are only some embodiments of the present invention, not all embodiments. All other embodiments, which can be made by those skilled in the art based on the embodiments of the present invention without making any inventive effort, shall fall within the scope of the present invention.
It should be noted that the terms "first," "second," and the like in the description and the claims of the present invention and the above figures are used for distinguishing between similar objects and not necessarily for describing a particular sequential or chronological order. It is to be understood that the data so used may be interchanged where appropriate such that the embodiments of the invention described herein may be implemented in sequences other than those illustrated or otherwise described herein. Furthermore, the terms "comprises," "comprising," and "having," and any variations thereof, are intended to cover a non-exclusive inclusion, such that a process, method, system, article, or apparatus that comprises a list of steps or elements is not necessarily limited to those steps or elements expressly listed but may include other steps or elements not expressly listed or inherent to such process, method, article, or apparatus.
The invention is described in further detail below with reference to the attached drawing figures:
referring to fig. 1, the method for achieving critical loading of the high-temperature gas cooled reactor core according to the invention comprises the following steps:
1) In the critical process of the reactor core of the pebble-bed high-temperature gas cooled reactor, all absorption balls are blown into a ball storage tank at the upper part of the reactor core, all control rods are lifted to the upper limit position at the top of the reactor core, the reactor core is at normal pressure, and a primary loop of the reactor core is in air atmosphere;
2) Filling mixed fuel with one third theoretical critical loading capacity into the reactor core, and recording the neutron count rate of an out-of-core nuclear measuring instrument;
3) Loading mixed fuel of one third of the difference between the theoretical critical loading capacity and the current loaded mixed fuel loading capacity into the reactor core, and recording the neutron count rate of an out-of-core nuclear measuring instrument;
4) Calculating an extrapolated critical load according to the neutron count rate of the out-of-core nuclear measuring instrument recorded in the step 3) and the neutron count rate of the out-of-core nuclear measuring instrument recorded in the step 2), taking the smaller value between the calculated extrapolated critical load and the theoretical critical load, making a difference with the current mixed fuel load, taking one third of the difference as the load of the next step, loading the core, and then turning to the step 3) until the difference between the minimum extrapolated critical load and the current load is smaller than 800 mixed fuels, and then turning to the step 5);
5) Inserting a group of control rods to a height of 6000mm, adding 450 mixed fuels on the basis of the critical loading capacity of the previous extrapolation, and then feeding the mixed fuels into a reactor core; after all the mixed fuel is filled into the reactor core, gradually lifting a group of control rods which are inserted down until the reactor reaches a critical state by the out-of-core nuclear testing instrument.
Example 1
The specific process of the embodiment is as follows:
1) Blowing all absorption balls in the absorption ball shutdown system into a ball storage tank at the upper part of the reactor core, lifting all control rods (shutdown rods, regulating rods and compensating rods) to an upper limit position at the top of the reactor core, wherein the reactor core is at normal pressure, and the primary loop is air atmosphere;
2) The reactor core is filled with mixed fuel with one third theoretical critical loading, the neutron count rate of an out-of-core nuclear measuring instrument is recorded, and the ratio of fuel elements to graphite nodules in the mixed fuel is 7:8, namely 7 parts of fuel elements with 4.2% enrichment: 8 parts of graphite spheres;
3) Loading mixed fuel of one third of the difference between the theoretical critical loading capacity and the current loaded mixed fuel loading capacity into the reactor core, and recording the neutron count rate of an out-of-core nuclear measuring instrument;
4) Calculating an extrapolated critical load according to the neutron count rate of the out-of-core nuclear measuring instrument recorded in the step 2) and the neutron count rate of the out-of-core nuclear measuring instrument recorded in the step 3);
5) Selecting the minimum value of the theoretical critical load and the extrapolated critical load, and taking one third of the difference result between the minimum value and the current mixed fuel load as the load of the next step;
6) Loading the reactor core according to the loading capacity determined in the step 5), and then turning to the step 5) until the difference between the minimum extrapolated critical loading capacity and the current loading capacity is less than 800 mixed fuels, and then turning to the step 7);
7) A group of control rods are inserted down to the 6000mm height of the reactor core;
8) Loading the last minimum extrapolated critical loading plus 450 numbers of mixed fuels into the core;
9) And gradually lifting the inserted group of control rods until the reactor reaches a critical state by monitoring and displaying by the out-core nuclear measuring instrument.
Finally, it should be noted that: the above embodiments are only for illustrating the technical aspects of the present invention and not for limiting the same, and although the present invention has been described in detail with reference to the above embodiments, it should be understood by those of ordinary skill in the art that: modifications and equivalents may be made to the specific embodiments of the invention without departing from the spirit and scope of the invention, which is intended to be covered by the claims.
Claims (4)
1. A method for critically loading a core of a high temperature gas cooled reactor, comprising the steps of:
1) Preparing;
2) Filling mixed fuel with one third theoretical critical loading capacity into the reactor core, and recording the neutron count rate of an out-of-core nuclear measuring instrument;
3) Loading mixed fuel of one third of the difference between the theoretical critical loading capacity and the current loaded mixed fuel loading capacity into the reactor core, and recording the neutron count rate of an out-of-core nuclear measuring instrument;
4) Calculating an extrapolated critical load according to the neutron count rate of the out-of-core nuclear measuring instrument recorded in the step 3) and the neutron count rate of the out-of-core nuclear measuring instrument recorded in the step 2), taking the smaller value between the calculated extrapolated critical load and the theoretical critical load, making a difference with the current mixed fuel load, taking one third of the difference result as the load of the next step, loading the core, and then turning to the step 3) until the difference value between the minimum extrapolated critical load and the current load is smaller than N mixed fuels, and then turning to the step 5);
5) Inserting a group of control rods to Mmm height, adding K mixed fuels on the basis of the last extrapolated critical loading capacity, and then feeding the mixed fuels into a reactor core;
after all the mixed fuel is filled into the reactor core, gradually lifting a group of control rods which are inserted downwards until the outside of the reactor core is displayed by a nuclear testing instrument to reach a critical state;
N＝800；
M＝6000；
K＝450。
2. the high temperature gas cooled reactor core charge criticality method of claim 1, wherein the specific process of step 1) is:
in the critical process of the reactor core of the pebble-bed high-temperature gas cooled reactor, all absorption balls are blown into a ball storage tank at the upper part of the reactor core, all control rods are lifted to the upper limit position at the top of the reactor core, the reactor core is at normal pressure, and a primary loop of the reactor core is in an air atmosphere.
3. The high temperature gas cooled reactor core charge criticality method of claim 1, wherein all control rods comprise shutdown rods, regulator rods and compensator rods.
4. The high temperature gas cooled reactor core charge criticality method of claim 1, wherein the mixed fuel comprises 4.2% enriched fuel elements and graphite nodules, wherein the fraction ratio of 4.2% enriched fuel elements to graphite nodules is 7:8.
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Citations (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| DE2735935A1 (en) * | 1977-08-10 | 1979-02-22 | Hochtemperatur Reaktorbau Gmbh | Initial charging of pebble bed reactor - with core rods fully inserted and side reflector rods fully withdrawn |
| CA1251872A (en) * | 1985-09-20 | 1989-03-28 | Eberhardt Teuchert | Method and apparatus for loading a ball-bed nuclear reactor |
| CN101083153A (en) * | 2007-06-25 | 2007-12-05 | 清华大学 | Ball bed high-temperature gascooled reactor online reloading system |
| CN109741838A (en) * | 2019-02-01 | 2019-05-10 | 中国原子能科学研究院 | Antineutron trap type research reactor initial criticality method |
| CN111799000A (en) * | 2020-06-02 | 2020-10-20 | 江苏核电有限公司 | Critical approaching method for pressurized water reactor primary reactor core without additional primary neutron source |
| CN113345605A (en) * | 2021-04-29 | 2021-09-03 | 广西防城港核电有限公司 | Fast critical control method for refueling and starting of nuclear reactor |
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- 2021-09-18 CN CN202111112704.4A patent/CN113871045B/en active Active
Patent Citations (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| DE2735935A1 (en) * | 1977-08-10 | 1979-02-22 | Hochtemperatur Reaktorbau Gmbh | Initial charging of pebble bed reactor - with core rods fully inserted and side reflector rods fully withdrawn |
| CA1251872A (en) * | 1985-09-20 | 1989-03-28 | Eberhardt Teuchert | Method and apparatus for loading a ball-bed nuclear reactor |
| CN101083153A (en) * | 2007-06-25 | 2007-12-05 | 清华大学 | Ball bed high-temperature gascooled reactor online reloading system |
| CN109741838A (en) * | 2019-02-01 | 2019-05-10 | 中国原子能科学研究院 | Antineutron trap type research reactor initial criticality method |
| CN111799000A (en) * | 2020-06-02 | 2020-10-20 | 江苏核电有限公司 | Critical approaching method for pressurized water reactor primary reactor core without additional primary neutron source |
| CN113345605A (en) * | 2021-04-29 | 2021-09-03 | 广西防城港核电有限公司 | Fast critical control method for refueling and starting of nuclear reactor |
Non-Patent Citations (1)
| Title |
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| 高温堆临界实验装置ASTRA的初始临界计算;常鸿;杨永伟;经荥清;;清华大学学报(自然科学版);20060625(06);第875-878页 * |
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