CN1263978C - Method for reducing corrosion of connecting pipeline in primary return for CANDU nuclear power plant - Google Patents
Method for reducing corrosion of connecting pipeline in primary return for CANDU nuclear power plant Download PDFInfo
- Publication number
- CN1263978C CN1263978C CNB021305153A CN02130515A CN1263978C CN 1263978 C CN1263978 C CN 1263978C CN B021305153 A CNB021305153 A CN B021305153A CN 02130515 A CN02130515 A CN 02130515A CN 1263978 C CN1263978 C CN 1263978C
- Authority
- CN
- China
- Prior art keywords
- heat exchanger
- tube
- accordance
- solid material
- power plant
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Expired - Fee Related
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Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D1/00—Details of nuclear power plant
- G21D1/006—Details of nuclear power plant primary side of steam generators
-
- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F28—HEAT EXCHANGE IN GENERAL
- F28F—DETAILS OF HEAT-EXCHANGE AND HEAT-TRANSFER APPARATUS, OF GENERAL APPLICATION
- F28F19/00—Preventing the formation of deposits or corrosion, e.g. by using filters or scrapers
-
- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F28—HEAT EXCHANGE IN GENERAL
- F28G—CLEANING OF INTERNAL OR EXTERNAL SURFACES OF HEAT-EXCHANGE OR HEAT-TRANSFER CONDUITS, e.g. WATER TUBES OR BOILERS
- F28G1/00—Non-rotary, e.g. reciprocated, appliances
- F28G1/12—Fluid-propelled scrapers, bullets, or like solid bodies
-
- 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
- G21C19/28—Arrangements for introducing fluent material into the reactor core; Arrangements for removing fluent material from the reactor core
- G21C19/30—Arrangements for introducing fluent material into the reactor core; Arrangements for removing fluent material from the reactor core with continuous purification of circulating fluent material, e.g. by extraction of fission products deterioration or corrosion products, impurities, e.g. by cold traps
- G21C19/303—Arrangements for introducing fluent material into the reactor core; Arrangements for removing fluent material from the reactor core with continuous purification of circulating fluent material, e.g. by extraction of fission products deterioration or corrosion products, impurities, e.g. by cold traps specially adapted for gases
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/001—Decontamination of contaminated objects, apparatus, clothes, food; Preventing contamination thereof
-
- 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
-
- 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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- Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Mechanical Engineering (AREA)
- Plasma & Fusion (AREA)
- Life Sciences & Earth Sciences (AREA)
- Combustion & Propulsion (AREA)
- Chemical & Material Sciences (AREA)
- Food Science & Technology (AREA)
- Thermal Sciences (AREA)
- Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Preventing Corrosion Or Incrustation Of Metals (AREA)
- Jet Pumps And Other Pumps (AREA)
- Pressure Welding/Diffusion-Bonding (AREA)
Abstract
The present invention relates to a method for reducing corrosion erosion in the feeder pipes (12a, b) used in the primary loop of a CANDU type nuclear power plant. According to the present invention, to this end the surface roughness of the primary side inside walls of the heat exchanger tubes (22) of a steam generator (20) that is arranged in the primary loop, which is caused by operation of the nuclear power plant, is reduced by treatment with an abrasive.
Description
Technical field
The present invention relates to reduce the corroding method of the connecting tube in the primary circuit of CANDU (Canadian deuterium-uranium reactor) type nuclear power plant.
Background technique
The reactor vessel (calandria) of CANDU type nuclear power plant comprises many pressure tubes (pressure piping or calandria pipeline), wherein inserts some fuel elements and it flows through heating medium along this longitudinal direction along its longitudinal direction, i.e. heavy water.Each root pressure tube is connected on the connecting tube (conveyance conduit) at input end and output terminal, and the latter is from a common inlet dispenser (inlet header box) or lead to a common outlet collector (outlet header box).These connecting tubes have less internal diameter (about 2.5cm) and owing to the restriction that is subjected to condition has a plurality of curved parts than small radii of curvature.
Particularly observed the material corrosion on its internal surface in the output terminal of connecting tube now, this is owing to corrosion causes.In addition, the biphasic mixture that is made of steam bubble and heavy water that still occurs owing to the outlet port at pressure tube causes.This material corrosion reaches so high value along with pursuing of operating time increases in this case, for example observe promptly that its erosion ratio is the order of magnitude of annual 150 μ m, thus since therefore the wall thickness attenuation that brings also reach design of plant just may this connecting tube of replacing the life-span before.Yet, because the quantity of such connecting tube is very big and be subjected to the restriction of condition, once such replacing to relate to considerable technical fee and quite long dead time and so improved cost.
Summary of the invention
The objective of the invention is to, the corroding method of the connecting tube in the primary circuit of a kind of CANDU of minimizing type nuclear power plant is provided, this method can be implemented and make connecting tube reach obviously higher durability with low expense.
According to the present invention, the corroding method of the connecting tube in a kind of primary circuit that reduces CANDU type nuclear power plant is proposed.In the method, corrosion for the connecting tube in the primary circuit that reduces CANDU type nuclear power plant, according to the present invention, reduce on the inwall of the primary side of tube for heat exchanger because the surface roughness that the deposition of corrosion products causes by the processing of carrying out with a kind of shot-peening, this shot-peening is preferably by gas and the multiphase mixture formed with the solid material that particulate form exists.
Though by a kind of shot blast tube for heat exchanger of US patent specification 5,883,512 known basically usefulness.But this processing only is used as the provision of implementing an eddy current test, so that improve the EARLY RECOGNITION of material damage greatly by the reduction of noise level.
The present invention relates to such opinion, the reduction that is the heat transfer power of the surface roughness of tube for heat exchanger and the steam generator that brings thus causes: along with the operating time by increasing, quicken to come across corrosion and therefore lip-deep material corrosion in the connecting tube within it.
The increase of the surface roughness of the internal surface of the tube for heat exchanger that is found in the operating time itself mainly is owing to the corrosion in the connecting tube that appears at exhaust end in primary circuit causes.Therefore under the situation of corrosion, in primary circuit, particularly low carbon steel that adopts in the connecting tube of exhaust end or non-alloy carbon steel are corroded and have formed the compound of the iron that exists as ion and be discharged in the heating medium (heavy water).The compound of the iron of these ions is transfused in the steam generator and is deposited on as oxide on the internal surface of tube for heat exchanger.
These depositions cause tube for heat exchanger inwall higher surface roughness and on little degree, also cause by the reducing of the cross section of this deposition decision, thereby reduced the flow of heating medium relatively.Thereby this reduced again steam generator heat transfer power and along with the operating time by increase in primary circuit circuit heating medium (heavy water) the output terminal of steam generator and in the temperature of the input end of this reactor also by increasing.
The present invention relates to such consideration, is that 2 to 3 ℃ this less temperature rise just is enough to and will brings up to the degree of the corrosion in the connecting tube of appreciable impact exhaust end at the steam bubble composition in the outlet port of the pressure tube of nuclear reactor at the order of magnitude promptly.
Thereby utilize method of the present invention can get rid of effectively now forming the influential oxide deposition of surface roughness with the geometry of heating pipe irrelevant and significantly reduce tube for heat exchanger internal surface surface roughness and significantly improve the heat transfer power of steam generator.Reduced temperature thus at the reactor input end.By measure of the present invention, the temperature value in the time of the temperature value of input end being reached be about as much as the power station starting in the mode of sand blast.
Thereby the raising of the ratio of the heat transfer of steam generator has caused the pressure in the secondary vapour system to raise in addition and has improved the efficient in turbine zone.
The smooth convincingness of also having improved the result who in eddy current test or ultrasonic testing, obtains on the sediments removal relevant and the surface of tube for heat exchanger with shot blast, and reach less wearing and tearing owing to reduced friction, that is reached higher durability by the test control head of tube for heat exchanger.
Utilization according to method of the present invention reach can be comparable with the steam generator of brand-new state heat transfer capacity (heat transfer capacity of design), thereby at least generally return to the original design power of nuclear power plant.
Another advantage of the present invention is, compares with the soak cleaning or the chemical cleaning method of tube for heat exchanger, and the volume of its secondary slugs is very little.Chemical method produces many times the waste material volume according to the inventive method.Therefore be reduced in the abatement of pollution expense of the subsidiary a large amount of secondary slugs that produce in this case significantly.
Advantageously, adopt a kind of gas/solid material blends as shot-peening.Improve the speed of removing whereby and be easy to carry out shot blast.
In particularly advantageous form of implementation of the present invention, tube for heat exchanger before shot blast through being evacuated and/or the surrounding atmosphere of cyclic drying and being dried.This Dry run causes the coming off fully and help the effectiveness of heterogeneous processing of part of the oxide skin(coating) that deposits.
Utilize the gas/solid material blends especially can 5 seconds with time of 10 minutes within handle tube for heat exchanger.
In another favourable form of implementation of the present invention, the pressure of the preferred gas phase for nitrogen or air in the gas/solid material blends in entering tube for heat exchanger is for for example between 0.1MPa (1 crust) and 1MPa (10 cling to).
Solid material is particularly including the particulate of granular, spherical and/or the band angle/band corner angle.The solid material composition also can be a kind of granulate fraction.Solid material is particularly including glass, emery, metal, metallic oxide, pottery and/or comprise the raw material of tube for heat exchanger.
Also may use a kind of solid material mixture that comprises different materials.
The mean particle dia of solid material is preferably between 100 and 1000 μ m, particularly between 150 and 400 μ m.
Utilization except that the advantage that reduces corroding is, still keeps the heat transfer capacity of heat exchanger and its another advantage to be according to method of the present invention, reaches the EARLY RECOGNITION of damaging about the heat exchanger pipe-in-pipe.
Description of drawings
The present invention is described in more detail by means of accompanying drawing, wherein,
Fig. 1 is the signal structure with the CANDU type nuclear power plant shown in the schematic diagram.
Embodiment
According to this figure, the reactor 2 of a CANDU type nuclear power plant (so-called calandria) comprises many pressure tubes 4, generally is about 400, in order at the schematic diagram of this signal wherein two only to be shown for the purpose of obviously.Pressure tube 4 comprises fuel element 6 and by a kind of heating medium, i.e. heavy water D
2O flows through.All pressure tubes 4 are parallel to that its longitudinal axis is installed in the columniform container 10 and are outstanding from each end face of container 10 with its connecting end 4a, 4b.There they be connected to respective number input end or output terminal connecting tube 12a, 12b on.Each input end connecting tube 12a is from an inlet dispenser 14a.Each output terminal connecting tube leads to an outlet collector 14b.Between inlet dispenser 14a and outlet collector 14b, a steam generator 20 is set respectively.Steam generator 20 comprises many crooked tube for heat exchangers 22 that take the shape of the letter U, and its heat that will produce in reactor 2 is passed to the freezing mixture 24 of secondary end, i.e. light-water H
2O and make its vaporization so that drive turbine engine.
In addition by among the figure as can be known, container 10 is also by a moderator 30, i.e. heavy water D
2O passes through.
For can refuelling element 6, in fact connecting tube 12a, 12b be different from schematic diagram, are not at end face but are connected on the pressure tube 4 in the side.Therefore these connecting tubes have less internal diameter (specific power that depends on pressure tube is between 1.5 and 3.5 inches) and since be subjected to the restriction of installation conditions must be transverse to the longitudinal axis of pressure tube 4 around the pressure tube 4 of each adjacency also thereby by with less radius bend.
Connecting tube 12a, 12b are made of carbon steel and demonstrate obvious corrosion.Corrosion occurs among the connecting tube 12b that is connected to the outlet separately on the pressure tube 4, because cause the steam bubble composition of corrosion high especially at this end especially.Fu Shi degree is so high like this, so that the wall thickness attenuation that brings thus may cause the shortening in life-span.
The material that peels off on the internal surface by connecting tube 12b is deposited on all the other places of primary circuit pipe-line system, particularly is deposited in the tube for heat exchanger 22 and causes the reduction gradually of heating medium flow.Along with the reduction of heating medium flow brings the temperature rise of heating medium 8 at the inlet 4a place of pressure tube 4, this temperature rise reaches one very little degree centigrade the order of magnitude (2 to 5 ℃) in the operating time for many years.This less temperature rise just be enough to in pressure tube 4 and the steam bubble composition at outlet 4b place bring up to such degree, the negative effect to the reactor operation (pressure falls, and slows down) of promptly removing other is outer particularly to the generation of the corrosion among the connecting tube 12b of exhaust end adverse influence.
According to the present invention, by with a kind of shot-peening the processing of tube for heat exchanger 22 being caused the improvement of the heat transfer flow in the steam generator 20, it is reduced in the temperature and because the reduction that reduces to have caused particularly corroding in the connecting tube internal cause of exhaust end the erosion ratio that causes of steam power component at the 4a place that respectively enters the mouth of pressure tube 4.
Claims (11)
1. connecting tube (the 12a in the primary circuit that reduces CANDU type nuclear power plant, corroding method 12b), it is characterized in that, on the inwall of the primary side of the tube for heat exchanger (22) of the steam generator (20) that reduces in primary circuit, to be provided with by the processing of carrying out with a kind of shot-peening because the surface roughness that the operation of nuclear power plant causes.
2. in accordance with the method for claim 1, it is characterized in that, adopt a kind of gas/solid material blends as shot-peening.
3. in accordance with the method for claim 2, it is characterized in that at first and then dry heat exchanger pipe (22) is also handled it with described gas/solid material blends.
4. in accordance with the method for claim 3, it is characterized in that, by the dry heat exchanger pipe (22) that is evacuated.
5. according to claim 3 or 4 described methods, it is characterized in that,, adopt dry air for the drying of tube for heat exchanger (22).
6. in accordance with the method for claim 2, it is characterized in that the processing time of handling with described gas/solid material blends is between 5 seconds and 10 minutes.
7. in accordance with the method for claim 2, it is characterized in that the air pressure of described gas/solid material blends in entering tube for heat exchanger (22) time is between 0.1MPa and 1MPa.
8. in accordance with the method for claim 2, it is characterized in that, adopt particulate granular, spherical and/or the band angle as solid material.
9. in accordance with the method for claim 2, it is characterized in that described solid material comprises the raw material of glass, emery, metal, high-quality steel, pottery and/or tube for heat exchanger (22).
10. according to claim 8 or 9 described methods, it is characterized in that described solid material is made of particulate, mean particle dia is between 100 and 1000 μ m.
11. in accordance with the method for claim 10, it is characterized in that mean particle dia is between 150 and 400 μ m.
Applications Claiming Priority (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| DE10141304A DE10141304A1 (en) | 2001-08-28 | 2001-08-28 | Reduction of corrosion erosion, in feeder pipes within primary loop of nuclear power plant, involves reducing surface roughness of primary side inner walls of heat exchanger tubes of steam generator using adhesive |
| DE10141304.1 | 2001-08-28 |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN1401932A CN1401932A (en) | 2003-03-12 |
| CN1263978C true CN1263978C (en) | 2006-07-12 |
Family
ID=7696337
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CNB021305153A Expired - Fee Related CN1263978C (en) | 2001-08-28 | 2002-08-15 | Method for reducing corrosion of connecting pipeline in primary return for CANDU nuclear power plant |
Country Status (6)
| Country | Link |
|---|---|
| KR (1) | KR100589829B1 (en) |
| CN (1) | CN1263978C (en) |
| AR (1) | AR036372A1 (en) |
| CA (1) | CA2393461C (en) |
| DE (1) | DE10141304A1 (en) |
| RO (1) | RO121098B1 (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN108511091A (en) * | 2018-05-10 | 2018-09-07 | 中国核动力研究设计院 | A kind of pipe tube type pressurized water reactor system |
Families Citing this family (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| KR101406609B1 (en) * | 2012-12-03 | 2014-06-11 | 한국수력원자력 주식회사 | Pressurized heavy water reactor |
| CN106683720B (en) * | 2017-01-13 | 2018-01-30 | 中国核动力研究设计院 | A kind of shell-and-tube lead-containing alloy cooled reactor |
| CN108231220A (en) * | 2018-01-12 | 2018-06-29 | 中国核动力研究设计院 | A kind of pipe tube type pressurized water reactor system |
| CN110095011A (en) * | 2019-05-10 | 2019-08-06 | 大唐鲁北发电有限责任公司 | A kind of condenser cleaning internally-inlaid diamond dust spherical structure |
| CN115274150B (en) * | 2022-08-05 | 2024-05-07 | 中国核动力研究设计院 | Two-loop waste heat discharging system and method based on concentrated seawater cooling |
Family Cites Families (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| ES495960A0 (en) * | 1979-10-16 | 1985-09-01 | Westinghouse Electric Corp | METHOD AND ITS CORRESPONDING APPARATUS FOR DECONTAMINATING TUBES IN A NUCLEAR STEAM GENERATOR |
| US4645542A (en) * | 1984-04-26 | 1987-02-24 | Anco Engineers, Inc. | Method of pressure pulse cleaning the interior of heat exchanger tubes located within a pressure vessel such as a tube bundle heat exchanger, boiler, condenser or the like |
| DE3624119A1 (en) * | 1986-07-17 | 1988-01-21 | Rhein Westfael Elect Werk Ag | DEVICE FOR SIMULATING THE OPERATION OF A PRESSURE WATER REACTOR SYSTEM |
| JPH04227487A (en) * | 1990-05-18 | 1992-08-17 | Westinghouse Electric Corp <We> | Method of removing sludge and corrosion product |
| FR2694654B1 (en) * | 1992-08-06 | 1994-11-04 | Framatome Sa | Method and device for machining the internal surface of a tubular part and in particular an adapter fixed to the cover of the vessel of a pressurized water nuclear reactor. |
| DE69718729D1 (en) * | 1996-09-10 | 2003-03-06 | Kyokuto Rubber Co | Cleaning system for heat exchangers and method for cleaning a heat exchanger |
-
2001
- 2001-08-28 DE DE10141304A patent/DE10141304A1/en not_active Withdrawn
-
2002
- 2002-07-15 CA CA002393461A patent/CA2393461C/en not_active Expired - Fee Related
- 2002-08-12 RO ROA200201112A patent/RO121098B1/en unknown
- 2002-08-15 CN CNB021305153A patent/CN1263978C/en not_active Expired - Fee Related
- 2002-08-27 KR KR1020020050735A patent/KR100589829B1/en active IP Right Grant
- 2002-08-28 AR ARP020103227A patent/AR036372A1/en not_active Application Discontinuation
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN108511091A (en) * | 2018-05-10 | 2018-09-07 | 中国核动力研究设计院 | A kind of pipe tube type pressurized water reactor system |
Also Published As
| Publication number | Publication date |
|---|---|
| CN1401932A (en) | 2003-03-12 |
| AR036372A1 (en) | 2004-09-01 |
| KR100589829B1 (en) | 2006-06-14 |
| DE10141304A1 (en) | 2003-03-20 |
| CA2393461C (en) | 2003-12-23 |
| CA2393461A1 (en) | 2002-10-27 |
| RO121098B1 (en) | 2006-12-29 |
| KR20030019126A (en) | 2003-03-06 |
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| C06 | Publication | ||
| PB01 | Publication | ||
| C14 | Grant of patent or utility model | ||
| GR01 | Patent grant | ||
| C56 | Change in the name or address of the patentee |
Owner name: AALEYFART NP CO., LTD. Free format text: FORMER NAME OR ADDRESS: FRAMATOME ANP GMBH |
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| CP01 | Change in the name or title of a patent holder | ||
| CP01 | Change in the name or title of a patent holder |
Address after: Erlangen Patentee after: AREVA GmbH Address before: Erlangen Patentee before: Areva NP GmbH |
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| TR01 | Transfer of patent right | ||
| TR01 | Transfer of patent right |
Effective date of registration: 20190521 Address after: Germany Erlangen Patentee after: Farmaton Co.,Ltd. Address before: Erlangen Patentee before: AREVA GmbH |
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| CF01 | Termination of patent right due to non-payment of annual fee | ||
| CF01 | Termination of patent right due to non-payment of annual fee |
Granted publication date: 20060712 Termination date: 20190815 |