CN203908882U - Special measurement device for creep property of nuclear zirconium alloy tubing - Google Patents
Special measurement device for creep property of nuclear zirconium alloy tubing Download PDFInfo
- Publication number
- CN203908882U CN203908882U CN201420346047.9U CN201420346047U CN203908882U CN 203908882 U CN203908882 U CN 203908882U CN 201420346047 U CN201420346047 U CN 201420346047U CN 203908882 U CN203908882 U CN 203908882U
- Authority
- CN
- China
- Prior art keywords
- pressure
- zirconium alloy
- pipe
- coupon
- measurement device
- 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 - Lifetime
Links
- 229910001093 Zr alloy Inorganic materials 0.000 title claims abstract description 34
- 238000005259 measurement Methods 0.000 title claims abstract description 23
- 238000012360 testing method Methods 0.000 claims abstract description 37
- 238000010438 heat treatment Methods 0.000 claims abstract description 21
- 238000006073 displacement reaction Methods 0.000 claims abstract description 7
- 239000007789 gas Substances 0.000 claims description 53
- 230000001174 ascending effect Effects 0.000 claims description 11
- 230000008878 coupling Effects 0.000 claims description 4
- 238000010168 coupling process Methods 0.000 claims description 4
- 238000005859 coupling reaction Methods 0.000 claims description 4
- 238000009434 installation Methods 0.000 claims description 3
- 230000007246 mechanism Effects 0.000 claims description 3
- 229910001220 stainless steel Inorganic materials 0.000 claims description 3
- 230000004323 axial length Effects 0.000 claims description 2
- 238000002347 injection Methods 0.000 abstract 2
- 239000007924 injection Substances 0.000 abstract 2
- 238000000034 method Methods 0.000 description 4
- 239000003758 nuclear fuel Substances 0.000 description 4
- 238000005253 cladding Methods 0.000 description 3
- 239000000446 fuel Substances 0.000 description 3
- 230000008859 change Effects 0.000 description 2
- 238000005516 engineering process Methods 0.000 description 2
- 239000008188 pellet Substances 0.000 description 2
- 230000006399 behavior Effects 0.000 description 1
- 239000002826 coolant Substances 0.000 description 1
- 239000008358 core component Substances 0.000 description 1
- 230000007797 corrosion Effects 0.000 description 1
- 238000005260 corrosion Methods 0.000 description 1
- 230000007547 defect Effects 0.000 description 1
- 230000007812 deficiency Effects 0.000 description 1
- 238000013461 design Methods 0.000 description 1
- 238000011161 development Methods 0.000 description 1
- 230000018109 developmental process Effects 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 230000004992 fission Effects 0.000 description 1
- 230000003993 interaction Effects 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 229910052751 metal Inorganic materials 0.000 description 1
- 239000002184 metal Substances 0.000 description 1
- 239000007769 metal material Substances 0.000 description 1
- 238000012544 monitoring process Methods 0.000 description 1
- 238000010248 power generation Methods 0.000 description 1
- 230000001105 regulatory effect Effects 0.000 description 1
- 230000004044 response Effects 0.000 description 1
- 238000007789 sealing Methods 0.000 description 1
- 238000010998 test method Methods 0.000 description 1
Landscapes
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Investigating Strength Of Materials By Application Of Mechanical Stress (AREA)
Abstract
The utility model relates to a special measurement device for creep property of nuclear zirconium alloy tubing. The device comprises a sample unit, a heating unit, a test unit, a pressurizing unit and a control unit, wherein the heating unit comprises a drum-type resistance furnace, the sample unit comprises a zirconium alloy sample tube, a pressure injection tube and a pressure outlet tube respectively connected with two ends of the sample tube, an axial creep clamp and a chuck arranged at the end part of the sample tube; the zirconium alloy tube is arranged in the drum-type resistance furnace, the pressure injection tube is communicated with a high pressure gas outlet of the pressurizing unit; the test unit comprises a laser diameter measuring instrument, a temperature control thermocouple installed outside the sample tube, as well as a displacement sensor and a pressure sensor; the control unit comprises a main control cabinet respectively connected with the test device, the pressurizing unit and the heating unit of the test unit to realize the closed-loop control of temperature and pressure. The axial creep and the radial creep can be simultaneously measured online, the temperature and pressure can be controlled in a closed loop, the axial loading is realized, the cost is low and the test success rate is high.
Description
Technical field
The utility model relates to a kind of nuclear zirconium alloy pipe croop property measurement mechanism.
Background technology
Nuclear fuel element is the core component of reactor, is made up of fuel pellet, involucrum and member thereof.Because the running environment of nuclear fuel element is more severe, the corrosion of neutron irradiation, cooling medium and in reactor startup, shutdown and operation later stage fuel pellet and the mechanical interaction of zirconium alloy cladding pipe and the release of fission gas, make cladding tubes bear biaxial stress, all can cause the mechanical properties decrease of fuel element, form potential safety hazard.The security performance of nuclear fuel element directly affects the safe reliability of reactor.The key property that need to understand zirconium alloy cladding pipe in the time that the design of nuclear fuel element and simulated condition are evaluated, comprises internal pressure creep and enduring quality.
Conventionally the high-temerature creep of metal material and the mensuration of enduring quality are that the circular cross section sample of selection standard carries out high temperature unilateral stretching creep or duration running, the croop property under cannot response sample circumference stress state.The single circumference stress state that hoop stretches and hoop creep test can analog zirconium alloy pipe, and under actual service conditions, when zirconium alloy tube at high temperature bears interior pressure, be in fact subject to hoop and axial two-dimensional stress, result and the actual condition of traditional tensile creep and duration running method have a certain distance.Therefore, compress into the test of row internal pressure creep and can better simulate its actual stress state in application in employing zirconium alloy tube at high temperature directly bears, test findings has stronger directive significance.
In the world for the main boiler tube internal pressure creep test method that adopts of metal pipe material internal pressure creep test.From the seventies in last century, domestic Thermal Power Generation Industry has been set up a collection of boiler tube internal pressure creep testing machine, boiler tube has been carried out to a large amount of internal pressure creep experimental studies, but there is the defects such as slip is high, test pressure is unstable, and temperature control precision is poor in these testing machines.Newly the Inner Pressure Creep Behaviors of Advanced Zirconium Alloys test unit of development mainly adopts the method to being welded after sample pressurising to ensure sealing.Coolingly be incubated some hours under test condition after again external diameter is measured, thereby determined the deflection of tubing hoop creep.The shortcoming that the method mainly exists is 1, tests tubing as there is pressure leakage, cannot further test; 2, along with the increase of deflection, the pressure in test tubing will reduce, and test condition will change; The circumferential deformation of the tubing under 3, cannot on-line monitoring test condition.
Summary of the invention
Technical problem to be solved in the utility model is to overcome the existing deficiency of prior art, a kind of nuclear zirconium alloy pipe croop property special measurement device is provided, this device is simple to operate, work efficiency is high, easy to use, can simulate better the complex stress condition of involucrum in heap, improve success of the test rate, closed-loop control test temperature and pressure, realize the real-time online record of data.
For solving the problems of the technologies described above, the utility model is taked following technical scheme:
A kind of nuclear zirconium alloy pipe croop property special measurement device, it comprises sample cell, heating unit, test cell, for presser unit and the control module of gases at high pressure are provided, heating unit comprises cartridge type resistance furnace, sample cell comprises zircaloy coupon to be tested, the pressure ascending pipe and the pressure that are connected with the two ends of coupon respectively spread out of pipe, be arranged on the Axial creep fixture of coupon one end and be arranged on the chuck of coupon end, zircaloy coupon is arranged in cartridge type resistance furnace, pressure ascending pipe is communicated with the gases at high pressure outlet of presser unit, test cell comprises laser diameter measuring instrument for measuring coupon external diameter, be arranged on temperature-control heat couple outside coupon, for measuring displacement transducer that coupon axial length changes and for measuring the pressure transducer of coupon pressure, control module comprises overhead control cabinet, and it is connected with each proving installation, presser unit, the heating unit of test cell respectively, realizes the closed-loop control of temperature and pressure.
According to a concrete aspect, described cartridge type resistance furnace and coupon uprightly arrange, and displacement transducer is positioned at sample cell below.
Preferably, described presser unit comprises power air pipe, work air pipe, gas booster and the multiple gases at high pressure export pipelines that are connected in parallel with gas booster, and the end of described gases at high pressure export pipeline is gases at high pressure outlets.
Preferably, on described power air pipe, be connected with compressed air interface, filtrator, pressure regulator valve, tensimeter, safety valve and stop valve in turn.
Preferably, described air pipe comprises work gas cylinder and the filtrator, tensimeter and the stop valve that connect successively; Work gas gas is gases at high pressure by gas booster supercharging.
Preferably, described gases at high pressure export pipeline exports and is provided with successively safety valve, high-pressure stop valve, tensimeter and high-pressure unloading valve to gases at high pressure from the end being connected with gas booster.
Preferably, said pressure ascending pipe, pressure spread out of pipe and all adopt 316 stainless steels to make, allowable stress 60000psi under room temperature.
Preferably, said pressure ascending pipe spreads out of pipe with pressure and is connected with described coupon by Swagelok rapid-acting coupling respectively.
Preferably, described measurement mechanism also comprises the pressure apparatus that applies axial load by chuck to coupon.By pressure apparatus and the adjustable coupon hoop of chuck axial stress ratio.
Preferably, described cartridge type resistance furnace adopts multistage heating temperature control, and uniform temperature zone is more than or equal to 300mm, ensures enough uniform temperature zone length.
Preferably, heating unit has multiple, and multiple heating units are separate, do not interfere with each other.
Using method of the present utility model is: the specimen surface temperature of whole test heating unit reaches after test temperature, be connected with sample and sample be forced into the test pressure of requirement and keep pressure and temperature stable by the outlet of presser unit gases at high pressure, the axial and Radial creep result of on-line measurement zirconium alloy tube.
Due to the enforcement of above technical scheme, the utility model compared with prior art tool has the following advantages:
Nuclear zirconium alloy pipe internal pressure creep device for measuring properties of the present utility model is a kind of on-line measurement device, can measure online Axial creep and Radial creep simultaneously, can closed loop temperature-control pressure-control, can axially load, cost is low, success of the test rate is high, is specially adapted to simulate internal pressure creep performance online under the complicated applied force state of nuclear zirconium alloy pipe in reactor and measures.
Brief description of the drawings
Below in conjunction with accompanying drawing and specific embodiment, the utility model is described in more detail.
Fig. 1 is according to the structural representation of nuclear zirconium alloy pipe croop property special measurement device of the present utility model;
Fig. 2 is the local enlarged diagram of Fig. 1;
Wherein: A, presser unit; B, heating unit; 1, compressed air interface; 2, filtrator; 3, pressure regulator valve; 4, tensimeter; 5, safety valve; 6, stop valve; 7, work gas cylinder; 8, gas booster; 9, high-pressure stop valve; 10, high-pressure unloading valve; 11, gases at high pressure outlet; 12, cartridge type resistance furnace; 13, laser diameter measuring instrument; 15, temperature-control heat couple; 17, displacement transducer; 18, pressure transducer; 19, overhead control cabinet; 20, chuck; 21, pressure ascending pipe; 22, Swagelok rapid-acting coupling; 23, coupon; 24, pressure spreads out of pipe; 25, Axial creep fixture.
Embodiment
As shown in Figure 1, the nuclear zirconium alloy pipe croop property special measurement device that this example provides comprises presser unit A, control module, multiple heating unit B, test cell.In heating unit B, be provided with sample cell D.Control module comprises overhead control cabinet 19, and it is connected with each proving installation, presser unit A, the heating unit B of test cell respectively, realizes the closed-loop control of temperature and pressure.
Presser unit A comprises power air pipe, work air pipe, gas booster and the multiple gases at high pressure export pipelines that are connected in parallel with gas booster, and the end of described gases at high pressure export pipeline is gases at high pressure outlets.On power air pipe, be connected with compressed air interface 1, filtrator 2, pressure regulator valve 3, tensimeter 4, safety valve 5 and stop valve 6 in turn.Work air pipe comprises work gas cylinder 7 and the filtrator 2, tensimeter 4 and the stop valve 6 that connect successively; Work gas gas is gases at high pressure by gas booster 8 superchargings.Gases at high pressure export pipeline is connected with safety valve 5 in turn, and high-pressure stop valve 9, tensimeter 4 and high-pressure unloading valve 10 are to gases at high pressure outlet 11.The embodiment of presser unit A is: pressurized air is entered by compressed air interface 1, provide power by filtrator 2, pressure regulator valve 3, tensimeter 4 and stop valve 6 for gas booster 8 successively, the working gas of work in gas cylinder 7 and successively by filtrator 2, tensimeter 4 and stop valve 6, by gas booster 8 superchargings be gases at high pressure via high-pressure stop valve 9 to the each coupon of gases at high pressure outlet 11 input.Tensimeter 4 is measured each staged pressure.Tensimeter 4, stop valve 6 is connected with the overhead control cabinet 19 of control module with high-pressure stop valve 9, auto stop when sample reaches set pressure, automatic compensation while reaching a certain degree lower than set pressure.
Cartridge type resistance furnace 12 adopts multistage heating temperature control, and uniform temperature zone is greater than 300mm, ensures enough uniform temperature zone length.
Referring to Fig. 2, sample cell of the present utility model comprises coupon 23 and is arranged on the pressure ascending pipe 21 at coupon 23 two ends and pressure spreads out of pipe 24, Axial creep fixture 25 and chuck 20.Pressure ascending pipe 21, pressure spread out of pipe 24 and adopt 316 stainless steels to make, and allowable stress 60000psi under room temperature adopts Swagelok rapid-acting coupling 22 to be connected with coupon 23; Chuck 20 can apply axial load, and regulating ring is to axial stress ratio.
Test cell comprise be arranged on cartridge type resistance furnace 12 outer for measure described coupon external diameter laser diameter measuring instrument 13, be arranged on temperature-control heat couple 15 outside coupon 23, be arranged on displacement transducer 17 and the pressure transducer 18 of sample cell below.
Each heating unit of the present utility model is separate, do not interfere with each other, the specimen surface temperature of whole test heating unit reaches after test temperature, be connected with sample by presser unit high-pressure outlet and sample be forced into the test pressure of requirement and keep pressure and temperature stable, the axial and Radial creep result of on-line measurement zirconium alloy tube.
Above the utility model is described in detail; its object is to allow the personage who is familiar with this art can understand content of the present utility model and be implemented; can not limit protection domain of the present utility model with this; all equivalences of doing according to Spirit Essence of the present utility model change or modify, and all should be encompassed in protection domain of the present utility model.
Claims (10)
1. a nuclear zirconium alloy pipe croop property special measurement device, it is characterized in that: comprise sample cell, heating unit, test cell, for presser unit and the control module of gases at high pressure are provided, described heating unit comprises cartridge type resistance furnace, described sample cell comprises zircaloy coupon to be tested, the pressure ascending pipe and the pressure that are connected with the two ends of described coupon respectively spread out of pipe, be arranged on the Axial creep fixture of described coupon one end and be arranged on the chuck of described coupon end, described zircaloy coupon is arranged in described cartridge type resistance furnace, described pressure ascending pipe is communicated with the gases at high pressure outlet of described presser unit, described test cell comprises laser diameter measuring instrument for measuring described coupon external diameter, be arranged on temperature-control heat couple outside described coupon, for measuring displacement transducer that coupon axial length changes and for measuring the pressure transducer of described coupon pressure, described control module comprises overhead control cabinet, and it is connected with the each described proving installation of described test cell, described presser unit, described heating unit respectively, realizes the closed-loop control of temperature and pressure.
2. nuclear zirconium alloy pipe croop property special measurement device according to claim 1, is characterized in that: described cartridge type resistance furnace and coupon uprightly arrange, and described displacement transducer is positioned at described sample cell below.
3. nuclear zirconium alloy pipe croop property special measurement device according to claim 1, it is characterized in that: described presser unit comprises power air pipe, work air pipe, gas booster and the multiple gases at high pressure export pipelines that are connected in parallel with gas booster, and the end of described gases at high pressure export pipeline is gases at high pressure outlets.
4. nuclear zirconium alloy pipe croop property special measurement device according to claim 3, is characterized in that: on described power air pipe, be connected with compressed air interface, filtrator, pressure regulator valve, tensimeter, safety valve and stop valve in turn.
5. nuclear zirconium alloy pipe croop property special measurement device according to claim 3, is characterized in that: described air pipe comprises work gas cylinder and the filtrator, tensimeter and the stop valve that connect successively; Work gas gas is gases at high pressure by described gas booster supercharging.
6. nuclear zirconium alloy pipe croop property special measurement device according to claim 3, is characterized in that: described gases at high pressure export pipeline exports and is provided with successively safety valve, high-pressure stop valve, tensimeter and high-pressure unloading valve to gases at high pressure from the end being connected with gas booster.
7. nuclear zirconium alloy pipe croop property special measurement device according to claim 1, is characterized in that: said pressure ascending pipe, pressure spread out of pipe and all adopts 316 stainless steels to make, allowable stress 60000psi under room temperature.
8. nuclear zirconium alloy pipe croop property special measurement device according to claim 1, is characterized in that: said pressure ascending pipe spreads out of pipe with pressure and is connected with described coupon by Swagelok rapid-acting coupling respectively.
9. nuclear zirconium alloy pipe croop property special measurement device according to claim 1, is characterized in that: described measurement mechanism also comprises the pressure apparatus that applies axial load by described chuck to described coupon.
10. nuclear zirconium alloy pipe croop property special measurement device according to claim 1, is characterized in that: described cartridge type resistance furnace adopts multistage heating temperature control, and uniform temperature zone is more than or equal to 300mm.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201420346047.9U CN203908882U (en) | 2014-06-25 | 2014-06-25 | Special measurement device for creep property of nuclear zirconium alloy tubing |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201420346047.9U CN203908882U (en) | 2014-06-25 | 2014-06-25 | Special measurement device for creep property of nuclear zirconium alloy tubing |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN203908882U true CN203908882U (en) | 2014-10-29 |
Family
ID=51783145
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201420346047.9U Expired - Lifetime CN203908882U (en) | 2014-06-25 | 2014-06-25 | Special measurement device for creep property of nuclear zirconium alloy tubing |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN203908882U (en) |
Cited By (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104390867A (en) * | 2014-12-12 | 2015-03-04 | 中国石油天然气集团公司 | Testing device and method for predicting thermal creep performance of metal material for thick oil thermal recovery sleeve |
| CN106153472A (en) * | 2016-06-17 | 2016-11-23 | 华北电力大学 | A kind of realize multi-axial creep pilot system and the method that intrinsic pressure and stretching combinations loads |
| CN106248499A (en) * | 2016-08-25 | 2016-12-21 | 宝鸡石油钢管有限责任公司 | A kind of tubing External Pressure at High Temperature bend test device |
| CN107389467A (en) * | 2017-06-23 | 2017-11-24 | 中国核电工程有限公司 | A kind of device for simulating the experiment of spentnuclear fuel involucrum high-temperature mechanical property |
| CN107560946A (en) * | 2017-09-25 | 2018-01-09 | 苏州热工研究院有限公司 | It is a kind of to be used to detect pilot system and detection method that tubing creep collapses performance |
| CN108051321A (en) * | 2017-12-20 | 2018-05-18 | 广东核电合营有限公司 | A kind of cladding tubes internal pressure explosion bulge test device and its test method |
| CN113654912A (en) * | 2021-07-24 | 2021-11-16 | 安阳工学院 | High-temperature thin-wall pressure vessel double-shaft creep testing system and method |
| WO2021258550A1 (en) * | 2020-06-23 | 2021-12-30 | 西安热工研究院有限公司 | Automatic pressure control type internal pressure creep blasting test device and method |
| CN114279823A (en) * | 2021-12-13 | 2022-04-05 | 中机试验装备股份有限公司 | Creep test device and test fixture for in-band pressure pipe sample |
-
2014
- 2014-06-25 CN CN201420346047.9U patent/CN203908882U/en not_active Expired - Lifetime
Cited By (12)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104390867A (en) * | 2014-12-12 | 2015-03-04 | 中国石油天然气集团公司 | Testing device and method for predicting thermal creep performance of metal material for thick oil thermal recovery sleeve |
| CN106153472A (en) * | 2016-06-17 | 2016-11-23 | 华北电力大学 | A kind of realize multi-axial creep pilot system and the method that intrinsic pressure and stretching combinations loads |
| CN106248499A (en) * | 2016-08-25 | 2016-12-21 | 宝鸡石油钢管有限责任公司 | A kind of tubing External Pressure at High Temperature bend test device |
| CN107389467A (en) * | 2017-06-23 | 2017-11-24 | 中国核电工程有限公司 | A kind of device for simulating the experiment of spentnuclear fuel involucrum high-temperature mechanical property |
| CN107389467B (en) * | 2017-06-23 | 2022-09-27 | 中国核电工程有限公司 | Device for simulating spent fuel cladding high-temperature mechanical performance test |
| CN107560946A (en) * | 2017-09-25 | 2018-01-09 | 苏州热工研究院有限公司 | It is a kind of to be used to detect pilot system and detection method that tubing creep collapses performance |
| CN108051321A (en) * | 2017-12-20 | 2018-05-18 | 广东核电合营有限公司 | A kind of cladding tubes internal pressure explosion bulge test device and its test method |
| CN108051321B (en) * | 2017-12-20 | 2023-08-25 | 广东核电合营有限公司 | Internal pressure explosion test device and test method for cladding tube |
| WO2021258550A1 (en) * | 2020-06-23 | 2021-12-30 | 西安热工研究院有限公司 | Automatic pressure control type internal pressure creep blasting test device and method |
| CN113654912A (en) * | 2021-07-24 | 2021-11-16 | 安阳工学院 | High-temperature thin-wall pressure vessel double-shaft creep testing system and method |
| CN113654912B (en) * | 2021-07-24 | 2024-05-28 | 安阳工学院 | Double-shaft creep testing system and method for high-temperature thin-wall pressure vessel |
| CN114279823A (en) * | 2021-12-13 | 2022-04-05 | 中机试验装备股份有限公司 | Creep test device and test fixture for in-band pressure pipe sample |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN203908882U (en) | Special measurement device for creep property of nuclear zirconium alloy tubing | |
| CN103258577B (en) | Nuclear power station high energy line leakage test cut analogy method | |
| Cinbiz et al. | A pulse-controlled modified-burst test instrument for accident-tolerant fuel cladding | |
| CN103247358A (en) | High-energy pipeline local leakage monitoring test bed for nuclear power station | |
| CN203241303U (en) | Detecting device for detecting blasting performance of nuclear zirconium alloy pipe material | |
| CN205538507U (en) | Nuclear is with zircaloy tubular product rapid heating up bursting property measuring device | |
| CN106979895A (en) | A kind of method of thin metallic tubd transient prediction high temperature explosion bulge test | |
| CN109323662B (en) | Device for controlling temperature of inner surface and outer surface of annular cladding and measuring deformation of annular cladding in high-temperature environment | |
| Hui et al. | Plastic limit load analysis for steam generator tubes with local wall-thinning | |
| Perez-Feró et al. | Experimental database of E110 claddings exposed to accident conditions | |
| CN202126374U (en) | Comprehensive pressure test-bed | |
| Barua et al. | Methodology for stress-controlled fatigue test under in-air and pressurized water reactor coolant water condition and to evaluate the effect of pressurized water reactor water and loading rate on ratcheting | |
| CN204064839U (en) | The thermal fatigue test device that a kind of constant stress loads | |
| Linton et al. | Hot Cell Installation and Demonstration of the Severe Accident Test Station | |
| RU132603U1 (en) | DEVICE FOR MECHANICAL TESTS OF TUBULAR SHELLS | |
| Grigoriev et al. | Advanced techniques for mechanical testing of irradiated cladding materials | |
| Penttilä et al. | Miniature Autoclave and Double Bellows Loading Device for Material Testing in Future Reactor Concept Conditions—Case Supercritical Water | |
| CN110967259A (en) | High-flux external extrusion damage test device and method for metal pipe with defects | |
| Choo et al. | Technical Issues Occurred during an Out-Pile Testing of HANARO Long-Term Irradiation Capsule | |
| Shewfelt et al. | Guillotine failure of fixed-end pipes, pressurized with hot water | |
| Kim et al. | Experimental Facility Design for Assessment of SMART Passive Safety System Concept | |
| Chung et al. | Performance of the CANFLEX fuel bundle under mechanical flow testing | |
| Wiesenack et al. | Axial gas transport and loss of pressure after ballooning rupture of high burn-up fuel rods subjected to LOCA conditions | |
| tao; NING Guang-sheng; TONG Zhen-feng | Tensile Test and Creep Test of Zr Alloy Pipe | |
| Gourdin et al. | Environmental Effect on Fatigue Crack Initiation under Equi-Biaxial Loading of an Austenitic Stainless Steel. Metals 2021, 11, 203 |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C14 | Grant of patent or utility model | ||
| GR01 | Patent grant | ||
| C41 | Transfer of patent application or patent right or utility model | ||
| TR01 | Transfer of patent right |
Effective date of registration: 20151111 Address after: 518031 Guangdong province Futian District Shangbu Road West of the city of Shenzhen Shenzhen science and technology building, 15 Floor Patentee after: Lingao Nuclear Power Co., Ltd. Patentee after: Suzhou Nuclear Power Research Institute Co., Ltd. Patentee after: Zhongkehua Nuclear Power Technology Institute Co., Ltd. Patentee after: China General Nuclear Power Corporation Address before: 215004 West Ring Road, Jiangsu, Suzhou, No. 1788 Patentee before: Suzhou Nuclear Power Research Institute Co., Ltd. Patentee before: Zhongkehua Nuclear Power Technology Institute Co., Ltd. Patentee before: China General Nuclear Power Corporation |