CN112309595A - Device and method for high-temperature gas cooled reactor core subregion loading - Google Patents
Device and method for high-temperature gas cooled reactor core subregion loading Download PDFInfo
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- CN112309595A CN112309595A CN202011232254.8A CN202011232254A CN112309595A CN 112309595 A CN112309595 A CN 112309595A CN 202011232254 A CN202011232254 A CN 202011232254A CN 112309595 A CN112309595 A CN 112309595A
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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
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
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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
- G21C19/18—Apparatus for bringing fuel elements to the reactor charge area, e.g. from a storage place
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- 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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- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention discloses a device and a method for sectionally charging a reactor core of a high-temperature gas cooled reactor, which comprises a reactor pressure vessel, a burnup measuring system, a spent fuel system, a fuel loading and unloading system, a new fuel system and a three-way valve group, wherein the reactor pressure vessel is connected with the reactor core through a pipeline; the reactor pressure vessel is internally loaded with high-temperature gas cooled reactor fuel balls, an outlet at the bottom of the reactor pressure vessel is communicated with an inlet of a burnup measuring system, an outlet of the burnup measuring system is communicated with an inlet of a spent fuel system and an inlet of a fuel loading and unloading system, an outlet of a new fuel system is communicated with an inlet of the fuel loading and unloading system, an outlet of the fuel loading and unloading system is communicated with N feeding ports at the top of the reactor pressure vessel through a three-way valve group, a reactor core loading partition in the reactor pressure vessel is divided into N loading partitions, one loading partition corresponds to one feeding port, and each feeding port is communicated with the corresponding loading partition.
Description
Technical Field
The invention belongs to the field of nuclear reactor core loading, and relates to a device and a method for partitioned loading of a high-temperature gas cooled reactor core.
Background
The core of the pressurized water reactor nuclear power unit generally uses a whole group of fuel assemblies to carry out an optimized partitioned charging strategy, namely, new fuel assemblies and fuel assemblies which pass through one fuel cycle period and two fuel cycle periods are rearranged in the core, on the basis of fully improving the fuel consumption level of nuclear fuel of a reactor, the power distribution in the core of the reactor is flattened as much as possible, and the power peak factor is reduced; meanwhile, the neutron leakage rate is reduced, and the neutron injection quantity of the reactor pressure vessel is reduced.
The high-temperature gas cooled reactor is a spherical fuel element, is transported to the center of the top of the reactor pressure vessel one by a fuel loading and unloading system through a pipeline, and freely falls and is filled to form a reactor core fuel area. Therefore, a higher bulge is formed in the middle of the reactor core, so that the central power peak factor of the reactor is larger, and the temperature of the reactor core is higher. Meanwhile, new fuel falls into the central area of the reactor core after being charged, so that the central power peak value and the fuel temperature of the reactor are further increased; due to the uniform arrangement of the fuel in the reactor core, the fuel ball burnup in the middle of the reactor core is higher, the fuel ball burnup depth outside the reactor core is lower, the unloading burnup depth is 68000-.
Disclosure of Invention
The invention aims to overcome the defects of the prior art and provides a device and a method for loading a reactor core of a high-temperature gas cooled reactor in a partitioned mode, wherein the device and the method can effectively solve the problems of nonuniform reactor core fuel consumption and high power crest factor.
In order to achieve the purpose, the device for loading the reactor core of the high-temperature gas cooled reactor in a partitioned mode comprises a reactor pressure vessel, a burnup measuring system, a spent fuel system, a fuel loading and unloading system, a new fuel system and a three-way valve group.
The reactor pressure vessel is internally provided with a high-temperature gas cooled reactor fuel ball, an outlet at the bottom of the reactor pressure vessel is communicated with an inlet of a burnup measuring system, an outlet of the burnup measuring system is communicated with an inlet of a spent fuel system and an inlet of a fuel loading and unloading system, an outlet of a new fuel system is communicated with an inlet of the fuel loading and unloading system, an outlet of the fuel loading and unloading system is communicated with N feeding ports at the top of the reactor pressure vessel through a three-way valve group, a reactor core loading partition in the reactor pressure vessel is divided into N loading partitions, one loading partition corresponds to one feeding port, and each feeding port is communicated with the corresponding loading partition.
The fuel consumption measuring system comprises a fuel consumption measuring system, a fuel consumption measuring system and a three-way valve group control system, wherein the fuel consumption measuring system comprises a fuel consumption measuring system, a fuel consumption measuring system and a fuel consumption measuring system.
N equals 16.
The reactor core loading partition is divided into a central circular area, a first annular area, a second annular area and a third annular area from inside to outside, wherein the central circular area, the first annular area, the second annular area and the third annular area are equally divided into five loading areas.
When the high-temperature gas cooled reactor is charged for the first time, the ratio of fuel spheres and graphite spheres charged into each charging subarea in the third annular area is 20: 80; the ratio of fuel spheres to graphite spheres loaded in each loading subarea in the second annular area is 60: 40; the ratio of fuel spheres to graphite spheres loaded in each loading partition in the first annular region is 40: 60; the fuel spheres and graphite spheres were loaded in each loading zone in a ratio of 30:70 in the central circular region.
A method for loading high-temperature gas cooled reactor core in different regions comprises the following steps that when the high-temperature gas cooled reactor is loaded for the first time, the ratio of fuel spheres loaded into each loading region in a third annular region to graphite spheres is 20: 80; the ratio of fuel spheres to graphite spheres loaded in each loading subarea in the second annular area is 60: 40; the ratio of fuel spheres to graphite spheres loaded in each loading partition in the first annular region is 40: 60; the fuel spheres and graphite spheres were loaded in each loading zone in a ratio of 30:70 in the central circular region.
A method for loading high-temperature gas-cooled reactor core in different zones comprises discharging fuel balls through a connecting pipe at the bottom of a reactor pressure vessel when the high-temperature gas-cooled reactor is balanced for refueling, sending the fuel balls into a burnup measuring system for burnup measurement, discharging the fuel balls with the burnup depth reaching the requirement into a spent fuel system, sending the fuel balls with the burnup depth not reaching the requirement into a fuel loading and unloading system, then entering different loading zones of a reactor core loading zone through a three-way valve group 4, controlling the online state of the three-way valve group by a three-way valve group control system to realize that the fuel balls enter the corresponding loading zone, sending a signal of the three-way valve group control system from the burnup measuring system, discharging the fuel balls with the burnup depth exceeding 80000MWD/tU into the spent fuel system, sequentially sending high-burnup fuel balls with the burnup depth of 60000MWD/tU into a third annular zone of the fuel loading zone by the three-way, the high-fuel-consumption fuel balls with the fuel consumption depth of 30000-.
The bottom outlet of the reactor pressure vessel is communicated with the inlet of the burnup measuring system through a discharge pipeline.
The invention has the following beneficial effects:
the reactor core partitioned charging device and the method of the high temperature gas cooled reactor adopt a partitioned charging mode during specific operation to solve the problem that a higher bulge is formed in the middle of the reactor core, specifically, the reactor core loading partition in the reactor pressure vessel is divided into N charging partitions, one charging partition corresponds to one feeding port, each feeding port is communicated with the corresponding charging partition, and the charging is respectively carried out on each charging partition through each feeding port to avoid the problem that the higher bulge is formed in the middle of the reactor core, so that the power distribution of the reactor core is flattened, and the power peak value and the central temperature of the reactor core are reduced. In addition, the invention carries out the burnup measurement through the burnup measurement system, arranges the fuel balls with the fuel ball burnup depth reaching the requirement into the spent fuel system, sends the fuel balls with the burnup depth not reaching the requirement into the fuel handling system, and is arranged in the reactor core by the three-way valve group in a partitioned way, thereby being beneficial to improving the burnup depth of the fuel, improving the utilization rate of the fuel and improving the economy of the fuel.
Drawings
FIG. 1 is a schematic structural view of the present invention;
FIG. 2 is a graph showing the division results of the core load division 8 according to the present invention.
Wherein, 1 is a fuel loading and unloading system, 2 is a three-way valve group control system, 3 is a fuel consumption measuring system, 4 is a three-way valve group, 5 is a spent fuel system, 6 is a new fuel system, 7 is a reactor pressure vessel, and 8 is a reactor core loading partition.
Detailed Description
The invention is described in further detail below with reference to the accompanying drawings:
referring to fig. 1 and 2, the apparatus for loading a reactor core of a high temperature gas cooled reactor in a partitioned manner includes a reactor pressure vessel 7, a burnup measuring system 3, a spent fuel system 5, a fuel handling system 1, a new fuel system 6 and a three-way valve group 4; the reactor pressure vessel 7 is internally provided with a high-temperature gas cooled reactor fuel ball, an outlet at the bottom of the reactor pressure vessel 7 is communicated with an inlet of a burnup measuring system 3, an outlet of the burnup measuring system 3 is communicated with an inlet of a spent fuel system 5 and an inlet of a fuel loading and unloading system 1, an outlet of a new fuel system 6 is communicated with an inlet of the fuel loading and unloading system 1, an outlet of the fuel loading and unloading system 1 is communicated with N material inlet openings at the top of the reactor pressure vessel 7 through a three-way valve group 4, a reactor core loading partition 8 in the reactor pressure vessel 7 is divided into N material loading partitions, one material loading partition corresponds to one material inlet opening, and each material inlet opening is communicated with the corresponding material loading partition.
The invention also comprises a three-way valve group control system 2, wherein the output end of the fuel consumption measuring system 3 is connected with the input end of the three-way valve group control system 2, the output end of the three-way valve group control system 2 is connected with the control end of the three-way valve group 4, and the bottom outlet of the reactor pressure vessel 7 is communicated with the inlet of the fuel consumption measuring system 3 through a discharge pipeline.
N is equal to 16, the reactor core loading partition 8 is divided into a central circular area, a first annular area, a second annular area and a third annular area from inside to outside, wherein the central circular area, the first annular area, the second annular area and the third annular area are equally divided into five loading partitions.
The method for the first charging is as follows: the ratio of fuel spheres to graphite spheres loaded in each loading subarea in the third annular area is 20: 80; the ratio of fuel spheres to graphite spheres loaded in each loading subarea in the second annular area is 60: 40; the ratio of fuel spheres to graphite spheres loaded in each loading partition in the first annular region is 40: 60; the fuel spheres and graphite spheres were loaded in each loading zone in a ratio of 30:70 in the central circular region.
The method for balanced charging comprises the following steps: in the balance refueling stage of the high-temperature gas cooled reactor, fuel spheres are discharged through a connecting pipe at the bottom of a reactor pressure vessel 7 and are sent into a burnup measuring system 3 for burnup measurement, the fuel spheres with the burnup depth reaching the requirement are discharged into a spent fuel system 5, the fuel spheres with the burnup depth not reaching the requirement are sent into a fuel handling system 1 and then enter different loading subareas of a reactor core loading subarea 8 through a three-way valve group 4, the three-way valve group control system 2 controls the on-line state of the three-way valve group 4 to realize that the fuel spheres enter a certain loading subarea, and signals of the three-way valve group control system 2 come from the burnup measuring system 3. Fuel balls with the burning depth exceeding 80000MWD/tU are discharged to a spent fuel system 5, high-burning-rate fuel balls with the burning depth of 60000-. New fuel spheres from the new fuel system 6 are delivered in turn by the three-way valve set 4 into the second annular region.
When the scheme is used for system design or transformation, fuel spheres with different burnups can be simplified and partitioned or refined and partitioned according to actual operating conditions, and the burnup conditions referred by the partitions can be set through the three-way valve group control system 2, so that the uneven burnup of the reactor core and the reduction of the power peak effect caused by the reactor core bulge formed by the fuel spheres in the reactor core are ensured.
Claims (7)
1. The reactor core zoning charging device of the high temperature gas cooled reactor is characterized by comprising a reactor pressure vessel (7), a burnup measuring system (3), a spent fuel system (5), a fuel loading and unloading system (1), a new fuel system (6) and a three-way valve group (4);
the reactor pressure vessel (7) is internally loaded with high-temperature gas-cooled reactor fuel balls, an outlet at the bottom of the reactor pressure vessel (7) is communicated with an inlet of a burnup measuring system (3), an outlet of the burnup measuring system (3) is communicated with an inlet of a spent fuel system (5) and an inlet of a fuel loading and unloading system (1), an outlet of a new fuel system (6) is communicated with an inlet of the fuel loading and unloading system (1), an outlet of the fuel loading and unloading system (1) is communicated with N material inlet openings at the top of the reactor pressure vessel (7) through a three-way valve group (4), a reactor core loading subarea (8) in the reactor pressure vessel (7) is divided into N material loading subareas, one material loading subarea corresponds to one material inlet opening, and each material inlet opening is communicated with the corresponding material loading subarea.
2. The device for the core partition charging of the high temperature gas cooled reactor according to claim 1, further comprising a three-way valve group control system (2), wherein an output end of the burnup measurement system (3) is connected with an input end of the three-way valve group control system (2), and an output end of the three-way valve group control system (2) is connected with a control end of the three-way valve group (4).
3. The apparatus for zonal loading of a high temperature gas cooled reactor core as recited in claim 1, wherein N is equal to 16.
4. The device for the core-partitioned charging of the high-temperature gas-cooled reactor according to claim 3, wherein the core-loading partition (8) is divided into a central circular area, a first annular area, a second annular area and a third annular area from inside to outside, wherein the central circular area, the first annular area, the second annular area and the third annular area are equally divided into five charging partitions.
5. The device for the core-partitioned charging of the high-temperature gas-cooled reactor according to claim 1, wherein a bottom outlet of the reactor pressure vessel (7) is communicated with an inlet of the burnup measurement system (3) through a discharge pipeline.
6. The method for loading the core of the high temperature gas cooled reactor in a partitioned mode is characterized in that the device for loading the core of the high temperature gas cooled reactor in the partitioned mode based on claim 3 comprises the following steps: when the high-temperature gas cooled reactor is charged for the first time, the ratio of fuel spheres and graphite spheres charged into each charging subarea in the third annular area is 20: 80; the ratio of fuel spheres to graphite spheres loaded in each loading subarea in the second annular area is 60: 40; the ratio of fuel spheres to graphite spheres loaded in each loading partition in the first annular region is 40: 60; the fuel spheres and graphite spheres were loaded in each loading zone in a ratio of 30:70 in the central circular region.
7. The method for loading the core of the high temperature gas cooled reactor in a partitioned mode is characterized in that the device for loading the core of the high temperature gas cooled reactor in the partitioned mode based on claim 3 comprises the following steps: when the high-temperature gas cooled reactor is balanced and reloaded, fuel balls are discharged through a connecting pipe at the bottom of a reactor pressure vessel (7) and are sent into a fuel consumption measuring system (3) for fuel consumption measurement, the fuel balls with the fuel consumption depth reaching the requirement are discharged into a spent fuel system (5), the fuel balls with the fuel consumption depth not reaching the requirement are sent into a fuel loading and unloading system (1), then the fuel balls enter different loading subareas of a reactor core loading subarea (8) through a three-way valve group (4), the three-way valve group control system (2) controls the online state of the three-way valve group (4) to realize that the fuel balls enter corresponding loading subareas, signals of the three-way valve group control system (2) come from the fuel consumption measuring system (3), the fuel balls with the fuel consumption depth exceeding 80000MWD/tU are discharged into the spent fuel system (5), and the high-fuel balls with the fuel consumption depth of 60000 and 80000MWD/tU are sequentially sent to a third annular area of the fuel loading subarea (8) through the three-way, high-fuel-consumption fuel balls with the fuel consumption depth of 30000-.
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| CN202011232254.8A CN112309595B (en) | 2020-11-06 | 2020-11-06 | Device and method for high-temperature gas cooled reactor core subregion loading |
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Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN115527696A (en) * | 2022-10-11 | 2022-12-27 | 华能核能技术研究院有限公司 | Nuclear energy system of tandem high-temperature gas cooled reactor and operation method thereof |
Citations (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US3034689A (en) * | 1958-10-14 | 1962-05-15 | Lincoln D Stoughton | Discharge valve for granular material |
| GB961084A (en) * | 1962-06-01 | 1964-06-17 | Atomic Energy Authority Uk | Nuclear reactor |
| GB1269804A (en) * | 1968-05-08 | 1972-04-06 | Brown Boveri Krupp Reaktor | A method of charging a gas-cooled high temperature nuclear reactor |
| CN1731533A (en) * | 2005-08-26 | 2006-02-08 | 田嘉夫 | Regular bed modular high temperature gas cooled reactor and its fuel sphere disposal method |
| CN101083153A (en) * | 2007-06-25 | 2007-12-05 | 清华大学 | Ball bed high-temperature gascooled reactor online reloading system |
| CN103065695A (en) * | 2012-12-20 | 2013-04-24 | 清华大学 | Control system of peddle bed type high temperature gas cooled reactor spent fuel charging and retake device |
| CN103137226A (en) * | 2011-11-28 | 2013-06-05 | 清华大学 | Reactor core fuel sphere position measurement device of pebble-bed-type high-temperature gas cooled reactor |
| CN103474113A (en) * | 2013-09-30 | 2013-12-25 | 清华大学 | Pebble-bed module type high-temperature gas cooled reactor fuel loading and unloading system |
| CN111695246A (en) * | 2020-05-26 | 2020-09-22 | 国家核安保技术中心 | Nuclear material balance method, device and equipment and computer storage medium |
-
2020
- 2020-11-06 CN CN202011232254.8A patent/CN112309595B/en active Active
Patent Citations (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US3034689A (en) * | 1958-10-14 | 1962-05-15 | Lincoln D Stoughton | Discharge valve for granular material |
| GB961084A (en) * | 1962-06-01 | 1964-06-17 | Atomic Energy Authority Uk | Nuclear reactor |
| GB1269804A (en) * | 1968-05-08 | 1972-04-06 | Brown Boveri Krupp Reaktor | A method of charging a gas-cooled high temperature nuclear reactor |
| CN1731533A (en) * | 2005-08-26 | 2006-02-08 | 田嘉夫 | Regular bed modular high temperature gas cooled reactor and its fuel sphere disposal method |
| CN101083153A (en) * | 2007-06-25 | 2007-12-05 | 清华大学 | Ball bed high-temperature gascooled reactor online reloading system |
| CN103137226A (en) * | 2011-11-28 | 2013-06-05 | 清华大学 | Reactor core fuel sphere position measurement device of pebble-bed-type high-temperature gas cooled reactor |
| CN103065695A (en) * | 2012-12-20 | 2013-04-24 | 清华大学 | Control system of peddle bed type high temperature gas cooled reactor spent fuel charging and retake device |
| CN103474113A (en) * | 2013-09-30 | 2013-12-25 | 清华大学 | Pebble-bed module type high-temperature gas cooled reactor fuel loading and unloading system |
| CN111695246A (en) * | 2020-05-26 | 2020-09-22 | 国家核安保技术中心 | Nuclear material balance method, device and equipment and computer storage medium |
Non-Patent Citations (1)
| Title |
|---|
| 杨永伟，等: "HTR_10石墨球与燃料球均匀混合装料初装堆方案研究", 《核动力工程》 * |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN115527696A (en) * | 2022-10-11 | 2022-12-27 | 华能核能技术研究院有限公司 | Nuclear energy system of tandem high-temperature gas cooled reactor and operation method thereof |
| CN115527696B (en) * | 2022-10-11 | 2023-08-22 | 华能核能技术研究院有限公司 | Tandem high-temperature gas cooled reactor nuclear energy system and operation method thereof |
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