CN105021469A - In-situ mechanical property testing device of nuclear material in high temperature irradiation simulation environment - Google Patents
In-situ mechanical property testing device of nuclear material in high temperature irradiation simulation environment Download PDFInfo
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- CN105021469A CN105021469A CN201510403800.2A CN201510403800A CN105021469A CN 105021469 A CN105021469 A CN 105021469A CN 201510403800 A CN201510403800 A CN 201510403800A CN 105021469 A CN105021469 A CN 105021469A
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Abstract
The invention discloses an in-situ mechanical property testing device of a nuclear material in a high temperature irradiation simulation environment. The testing device comprises a high temperature irradiator, a heater used for heating samples, an irradiation collimator, a pressure head, a shaft sleeve, a controller and a driver. The high temperature irradiator is a water-cooling cavity structure and is provided with a first linear through-hole and a second linear through-hole. An opening of the first linear through-hole is positioned on one side surface of the high temperature irradiator and the first linear through-hole is communicated with the cavity. An opening of the second linear through-hole is positioned on the top surface of the high temperature irradiator and the second linear through-hole is communicated with the cavity. The heater is positioned inside the cavity of the high temperature irradiator. The irradiator collimator is communicated with the cavity through the first linear through-hole and is directed at the surface of a sample. The shaft sleeve passes through the second linear through-hole. The pressure head is installed at the bottom of the shaft sleeve. The driver is used for driving the shaft sleeve and the pressure head. The controller is connected to the heater and the driver. During the process of irradiation and heating, the pressure head can be pressed into a sample so as to carry out in-situ mechanical testing.
Description
Technical field
The present invention relates to nuclear engineering field, more specifically, relate to the in-situ testing device of nuclear material mechanical property under a kind of Elevated temperature irradiation simulated environment.
Background technology
Along with the fast development of Chinese national economy, energy supply is becoming the bottleneck of restriction China economy, society and environmental development, and people build consensus gradually for the critical role of nuclear energy in China's energy sustainable supply.As the basis that nuclear reactor is built, nuclear material is the key ensureing its security, reliability and economy.Each stepping exhibition of nuclear technology is all inseparable with the improvement of material irradiation performance, and therefore relevant research work is subject to attention especially always.
The most important means of current research pile materials irradiation behaviour are into piling irradiation, then utilize hot cell equipment to go out heap after sample test and test.But, be test after in-pile irradiation or irradiation to be all faced with the problems such as program is many, the cycle is long, expense is high.In order to make full use of valuable exposed material, reducing gamma-rays to the impact of sample temperature and the irradiation gradient reducing large scale sample interior simultaneously, having developed again the multiple method utilizing small sample to carry out irradiation behaviour research both at home and abroad.
Be applicable in the method for miniaturized test and micro-nano test many, instrumentation creasing method (instrumented indentation) method is due to spatial resolution high (being especially applicable to the heterogeneous material systems such as thin-walled material system and welding position such as fuel can), required sample size is little, in-situ test can be carried out, multiple mechanical quantity (elastic modulus can be carried out, hardness, yield strength, strain hardening, fracture toughness, activation energy of creep and stress exponent, viscoelastic parameters, welding residual stress etc.) measurement and the advantage such as integrated cost is low, in recent years at the irradiation hardening of nuclear material, irradiation damage, the study mechanism of the major issue such as temper embrittlement and fatigue deformation obtains important application, become the powerful of nuclear material Performance Evaluation and Study on Irradiation Effects.But, due to routine micro-receive indentation equipment and can only at room temperature work, above-mentioned research work is also all at room temperature detect the material after irradiation and characterize, and the data of acquisition still fully can not reflect the mechanical characteristic of material under the Elevated temperature irradiation environment of reality.Particularly consider that higher (such as the cold fast neutron reactor coolant outlet temperature of French phoenix sodium reaches 560 DEG C to the working temperature of new ideas heap-type, the coolant outlet temperature of the high temperature gas-cooled demonstration reactor in China Shidao Bay reaches more than 750 DEG C), the material behavior under the mechanical performance data utilizing room temperature indentation equipment to obtain and actual condition certainly will differ farther.Therefore development is applicable to the high temperature indentation equipment of research material Study on Irradiation Effects and corresponding method of testing just seems particularly necessary.
In the process of irradiation, material constantly produces all kinds of defects such as poor atomic region, interstitial atom, room, these defects constantly spread, develop, react to each other, also with the inherent shortcoming of material as interactions such as dislocation, precipitation particles, crystal boundaries, cause the heterogeneous microstructure of material and macro-mechanical property to change.This process is a heat activated dynamic process, and temperature directly affects defect evolution and interactional speed.After the irradiation generally adopted at present, (post-irradiation) is although inspection can the temperature of Quality control, but after the processes such as sample transports through transfer again, reheat, defect distribution, the heterogeneous microstructure of its inside change to some extent with comparing during irradiation, therefore original position (In situ) method of testing is developed, i.e. limit irradiation limit method of testing, research irradiation defect is developed and the dynamic process such as the fatigue of material and creep just valuable especially.
To sum up can find, micro-receive creasing method and become the powerful of research material irradiation effect, high temperature indentation equipment and method also obtain important progress under the driving of multiple domain requirement, but the work of application high temperature impression technique study material radiation effect is still far insufficient, needs badly and carry out deep research in testing apparatus and method of testing.
Summary of the invention
The present invention, for overcoming at least one defect (deficiency) described in above-mentioned prior art, provides the in-situ testing device of nuclear material mechanical property under a kind of Elevated temperature irradiation simulated environment.
For solving the problems of the technologies described above, technical scheme of the present invention is as follows:
An in-situ testing device for nuclear material mechanical property under Elevated temperature irradiation simulated environment, comprises Elevated temperature irradiation device, well heater, irradiation collimating apparatus, pressure head, axle sleeve, controller and driver for heated sample; Have cavity in described Elevated temperature irradiation device and offer the first straight line pylone and the second straight line pylone, a mouth of described first straight line pylone is positioned at a side of Elevated temperature irradiation device and this first straight line pylone communicates with cavity; A mouth of described second straight line pylone is positioned at the end face of Elevated temperature irradiation device and this second straight line pylone communicates with cavity; In addition, Elevated temperature irradiation device also offers the 3rd straight line pylone, and described 3rd straight line pylone is positioned at a side of Elevated temperature irradiation device and this first straight line pylone communicates with cavity.
Described well heater is positioned at the cavity of Elevated temperature irradiation device, and described irradiation collimating apparatus is by the first straight line pylone and cavity connects and just to sample, described axle sleeve is positioned at the second straight line pylone, and pressure head is arranged on bottom axle sleeve; Described driver is used for drive ram, and described controller is connected with well heater and driver.
Technique scheme, when needs carry out irradiation to sample, be placed on well heater by sample, and vent control control heater heats, irradiation ray or particle are irradiated sample by collimating apparatus.In irradiation and heating process, as carried out mechanical test, controller control and drive system band dynamic head is with the speed of specifying press-in sample, and controller records pressing-in force and compression distance continuously.
The in-situ testing device of the technical program a kind ofly can heat sample when sample stands irradiation and carry out the micro indentation device of in-situ mechanical test, for nucleus reliability of material under assessment Elevated temperature irradiation environment and carry out irradiation defect and damage research provides a kind of novel, high-precision characterization method on micro-meso-scale.
Further, in order to better heat sample, described well heater comprises primary heater and secondary heater, described primary heater is positioned at the center of the cavity bottom of Elevated temperature irradiation device, and sample is placed on described primary heater, described secondary heater is positioned at cavity top, just right with primary heater.
Further, in order to protect Elevated temperature irradiation device, between the inwall of described well heater and Elevated temperature irradiation device, thermofin is provided with.
Further, described well heater is ceramic electrical backing; Described thermofin is thermal insulation ceramics.
Further, in order to the temperature of Real-Time Monitoring well heater, to reach the object of sample heating being carried out to monitoring in real time, described well heater is provided with the temperature sensor be connected with controller.Said temperature sensor is connected with controller through the 3rd straight line pylone with the lead-in wire of well heater.
Further, in order to shield the gamma-rays of generation, described Elevated temperature irradiation device is positioned at radiation shield room (as vitriol chamber).
Above-mentioned Elevated temperature irradiation device, except heated sample, also need to ensure that sample is not oxidized, itself can not distribute heat on micro indentation instrument, therefore further, described in-situ testing device also comprises inert gas shielding module and water-cooled module; Described inert gas shielding module comprises the protection through hole with cavity connects, and described protection through hole carries out gas shield for the inert gas injected to the cavity of Elevated temperature irradiation device; Described water-cooled module is several water-cooling channels, and described water-cooling channel is distributed in the Elevated temperature irradiation device place with secondary heater both sides below primary heater.
Inert gas shielding module is introduced by the perforate on Elevated temperature irradiation device; its opening leads to the cavity of Elevated temperature irradiation device inside; because this Elevated temperature irradiation device inside is close to sealed environment; when carrying out high temperature experiment; by continuing to pass into inert gas; the inert gas environment of heating chamber can be achieved, and then prevent the oxidation of sample and pressure head.In addition, the electricity consumption end of above-mentioned in-situ testing device and with water (water-cooling channel in water-cooled module), with gas end (the protection through hole of inert gas shielding module) not on same vertical face, to ensure that this in-situ testing device is effectively avoided getting an electric shock and short circuit accident.
Further, be radiation-screening, in the cavity inner wall of described Elevated temperature irradiation device, the first straight line pylone and the 3rd straight line pylone, be coated with irradiation absorption layer (boron).
Said apparatus mainly adopts stainless steel and heat-barrier material, and main technical parameter and technical characteristic are:
(1) the highest experimental temperature: 1000 degrees Celsius;
(2) water speed passed in water-cooled module: ~ 0.2m/s(tap water);
(3) inert gas is suitable for: argon gas etc.
Compared with prior art, the beneficial effect of technical solution of the present invention is: the present invention is the in-situ testing device of nuclear material mechanical property under a kind of Elevated temperature irradiation simulated environment, is a kind of high temperature instrument press-in device that can carry out qualitative assessment and sign on micro-meter scale to the Elevated temperature irradiation effect of nuclear material.This device can measure the Elasto―Viscoplasticity parameter of sample while carrying out Elevated temperature irradiation, and this is by for nucleus reliability of material under assessment Elevated temperature irradiation environment and carry out irradiation defect and damage research provides a kind of pole to have the means of novelty.The present invention develops to the mechanical property of nuclear structural materials under Elevated temperature irradiation environment first and has carried out in-situ characterization, for the assessment of nuclear material, type selecting and Study on Irradiation Effects of carrying out provide a kind of novel, high-resolution means, the new unified viscoplastic constitutive model containing temperature effect, strain rate effect and irradiation effect for structure provides important foundation.
Accompanying drawing explanation
Fig. 1 is Elevated temperature irradiation chamber schematic diagram.
Embodiment
Below in conjunction with drawings and Examples, technical scheme of the present invention is described further.
In figure, 1-Elevated temperature irradiation device, 2-ceramic electrical backing, 3-irradiation collimating apparatus, 4-pressure head, 5-axle sleeve, 6-thermal insulation ceramics, 7-water-cooling channel, 8-protect through hole, 9-temperature sensor (containing power lead), 10-packing ring, 11-irradiation screened room, 12-irradiation absorption layer.
Embodiment
An in-situ testing device for nuclear material mechanical property under Elevated temperature irradiation simulated environment, comprises Elevated temperature irradiation device, well heater, collimating apparatus, pressure head, axle sleeve, controller and driver for heated sample; Have cavity in Elevated temperature irradiation device and offer the first straight line pylone and the second straight line pylone, a mouth of the first straight line pylone is positioned at a side of Elevated temperature irradiation device and this first straight line pylone communicates with cavity; A mouth of the second straight line pylone is positioned at the end face of Elevated temperature irradiation device and this second straight line pylone communicates with cavity;
Well heater is positioned at the cavity of Elevated temperature irradiation device, and collimating apparatus is by the first straight line pylone and cavity connects and just to sample, axle sleeve is positioned at the second straight line pylone, and pressure head is installed on axle sleeve; Driver is used for drive ram, and controller is connected with well heater and driver.
Technique scheme, when needs carry out irradiation to sample, be placed on well heater by sample, and vent control control heater heats, and simultaneously by irradiation collimator-alignment sample, adopts irradiation particle (as neutron) to irradiate sample.In irradiation and heating process, as carried out mechanical test, controller control and drive system band dynamic head is with the speed of specifying press-in sample, and controller records pressing-in force and compression distance continuously.
The in-situ testing device of the technical program a kind ofly can heat sample when sample stands neutron irradiation and carry out the micro indentation device of in-situ mechanical test, for nucleus reliability of material under assessment Elevated temperature irradiation environment and carry out irradiation defect and damage research provides a kind of novel, high-precision characterization method on micro-meso-scale.
In the present embodiment, in order to better heat sample, well heater comprises primary heater and secondary heater, primary heater is positioned at the center of the cavity bottom of Elevated temperature irradiation device, and sample is placed on primary heater, secondary heater is positioned at cavity top, just right with primary heater.
In order to protect Elevated temperature irradiation device, between the inwall of well heater and Elevated temperature irradiation device, be provided with thermofin.
Well heater is ceramic electrical backing; Thermofin is thermal insulation ceramics.
In order to the temperature of Real-Time Monitoring well heater, to reach the object of sample heating being carried out to monitoring in real time, well heater is provided with the temperature sensor be connected with controller.Said temperature sensor passes with the lead-in wire of well heater from the 3rd straight line pylone and is connected with controller.
In order to shield the gamma-rays of generation, Elevated temperature irradiation device is positioned at radiation shield room (as vitriol chamber).
In the present embodiment, above-mentioned Elevated temperature irradiation device, except heated sample, also need to ensure that sample is not oxidized, itself can not distribute heat on micro indentation instrument, therefore further, in-situ testing device also comprises inert gas shielding module and water-cooled module; Inert gas shielding module comprises the protection through hole with cavity connects, and protection through hole carries out gas shield for the inert gas injected to the cavity of Elevated temperature irradiation device; Water-cooled module is several water-cooling channels, and water-cooling channel is distributed in the Elevated temperature irradiation device place with secondary heater both sides below primary heater.
Inert gas shielding module is introduced by the perforate on Elevated temperature irradiation device; its opening leads to the cavity of Elevated temperature irradiation device inside; because this Elevated temperature irradiation device inside is close to sealed environment; when carrying out high temperature experiment; by continuing to pass into inert gas; the inert gas environment of heating chamber can be achieved, and then prevent the oxidation of sample and impression probe.In addition; the electricity consumption end of above-mentioned in-situ testing device and with water (water-cooling channel in water-cooled module), with gas end (the protection through hole of inert gas shielding module) all not on same vertical face, this can ensure that this in-situ testing device is effectively avoided getting an electric shock and short circuit accident.
In the present embodiment, be radiation-screening, in the cavity inner wall of Elevated temperature irradiation device, the first straight line pylone and the 3rd straight line pylone, be coated with irradiation absorption layer 12(boron).
Said apparatus mainly adopts stainless steel and heat-barrier material, and main technical parameter and technical characteristic are:
(1) the highest experimental temperature: 1000 degrees Celsius;
(2) water speed passed in water-cooled module: ~ 0.2m/s(tap water);
(3) inert gas is suitable for: argon gas etc.
The invention has the advantages that: (1) provides means for the mechanical property of in-situ characterization nuclear structural materials under Elevated temperature irradiation environment develops first; (2) equipment is by different stationary installations and pattern, can be installed on various normal temperature indentation equipment.Widely applicable; (3) device structure is simple, stability is high; (4) device security is reliable, effectively prevent scald, electric leakage and device damage unexpected.
Obviously, the above embodiment of the present invention is only for example of the present invention is clearly described, and is not the restriction to embodiments of the present invention.For those of ordinary skill in the field, can also make other changes in different forms on the basis of the above description.Here exhaustive without the need to also giving all embodiments.All any amendments done within the spirit and principles in the present invention, equivalent to replace and improvement etc., within the protection domain that all should be included in the claims in the present invention.
Claims (9)
1. the in-situ testing device of nuclear material mechanical property under Elevated temperature irradiation simulated environment, is characterized in that, comprises Elevated temperature irradiation device, well heater, irradiation collimating apparatus, pressure head, axle sleeve, controller and driver for heated sample; Described Elevated temperature irradiation device is cavity structure and offers the first straight line pylone and the second straight line pylone, and a mouth of described first straight line pylone is positioned at a side of Elevated temperature irradiation device and this first straight line pylone communicates with cavity; A mouth of described second straight line pylone is positioned at the end face of Elevated temperature irradiation device and this second straight line pylone communicates with cavity;
Described well heater is positioned at the cavity of Elevated temperature irradiation device, and described collimating apparatus is by the first straight line pylone and cavity connects and just to sample, described axle sleeve is positioned at the second straight line pylone, and pressure head is installed on bottom axle sleeve; Described driver is used for propeller shaft sleeve and pressure head, and described controller is connected with well heater and driver.
2. the in-situ testing device of nuclear material mechanical property under Elevated temperature irradiation simulated environment according to claim 1, it is characterized in that, described well heater comprises primary heater and secondary heater, described primary heater is positioned at the center of the cavity bottom of Elevated temperature irradiation device, and sample is placed on described primary heater, described secondary heater is positioned at cavity top, just right with primary heater.
3. the in-situ testing device of nuclear material mechanical property under Elevated temperature irradiation simulated environment according to claim 2, is characterized in that, be provided with thermofin between the inwall of described well heater and Elevated temperature irradiation device.
4. the in-situ testing device of nuclear material mechanical property under Elevated temperature irradiation simulated environment according to claim 3, it is characterized in that, described well heater is ceramic electrical backing; Described thermofin is thermal insulation ceramics.
5. the in-situ testing device of nuclear material mechanical property under Elevated temperature irradiation simulated environment according to claim 4, it is characterized in that, described well heater is provided with the temperature sensor be connected with controller.
6. under the Elevated temperature irradiation simulated environment according to any one of claim 1 to 5, the in-situ testing device of nuclear material mechanical property, is characterized in that, described Elevated temperature irradiation device is placed in radiation shielded container.
7. the in-situ testing device of nuclear material mechanical property under Elevated temperature irradiation simulated environment according to claim 1, it is characterized in that, described in-situ testing device also comprises inert gas shielding module and water-cooled module; Described inert gas shielding module comprises the protection through hole with the cavity connects of Elevated temperature irradiation device, and described protection through hole carries out gas shield for the inert gas that injects to the cavity of Elevated temperature irradiation device, sample and pressure head; Described water-cooled module is several water-cooling channels, and described water-cooling channel is distributed in the Elevated temperature irradiation device place with secondary heater both sides below primary heater.
8. the in-situ testing device of nuclear material mechanical property under Elevated temperature irradiation simulated environment according to claim 4, it is characterized in that, described Elevated temperature irradiation device also offers the 3rd straight line pylone, 3rd straight line pylone communicates with the cavity of Elevated temperature irradiation device, and the lead-in wire of temperature sensor, the lead-in wire of heating plate are through this through hole.
9. the in-situ testing device of nuclear material mechanical property under Elevated temperature irradiation simulated environment according to claim 8, is characterized in that, is coated with irradiation absorption layer in the cavity inner wall of described Elevated temperature irradiation device, the first straight line pylone and the 3rd straight line pylone.
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| CN106501109A (en) * | 2016-09-13 | 2017-03-15 | 北京理工大学 | The in-situ nano impression test platform of energy storage material under a kind of electrochemical hot atmosphere |
| CN106714341A (en) * | 2016-12-21 | 2017-05-24 | 浙江师范大学 | Open-type heater manufacturing method used for synchronous-radiation in-situ test |
| CN106908848A (en) * | 2017-03-14 | 2017-06-30 | 北京华力兴科技发展有限责任公司 | Cask flask and radiation scanning inspection system for accommodating betatron |
| CN107144475A (en) * | 2017-04-16 | 2017-09-08 | 中国科学院近代物理研究所 | Elevated temperature irradiation creep device |
| CN107885253A (en) * | 2017-11-21 | 2018-04-06 | 中国工程物理研究院电子工程研究所 | A kind of precise temperature control device for the experiment of semiconductor devices dose rate effect |
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| CN114814149A (en) * | 2022-04-12 | 2022-07-29 | 哈尔滨工业大学 | Method for evaluating performance of Alnico alloy under irradiation and temperature field conditions |
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Citations (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN201397691Y (en) * | 2009-02-27 | 2010-02-03 | 中国科学院上海应用物理研究所 | High temperature irradiation box for irradiation of electron accelerator |
| CN101788453A (en) * | 2010-01-06 | 2010-07-28 | 中国科学院近代物理研究所 | High-temperature and stress energetic ion irradiation device |
| CN102590253A (en) * | 2012-01-17 | 2012-07-18 | 中国科学院上海应用物理研究所 | High-temperature fused salt synchrotron radiation in-situ research device |
| JP2014163777A (en) * | 2013-02-25 | 2014-09-08 | Mitsubishi Rayon Co Ltd | Tension testing device with high temperature furnace |
| CN104502202A (en) * | 2014-12-15 | 2015-04-08 | 吉林大学 | Online material biaxial static-dynamic performance test platform under service temperature |
| CN104596873A (en) * | 2015-01-26 | 2015-05-06 | 吉林大学 | System and method for testing temperature-varying micro-nanometer indentations with vacuum protection characteristics |
| CN204374016U (en) * | 2015-01-12 | 2015-06-03 | 吉林大学 | The micro-nano impression test device of continuous regulating temp. type high vacuum low temperature |
| CN205789142U (en) * | 2016-03-18 | 2016-12-07 | 国核（北京）科学技术研究院有限公司 | The Elevated temperature irradiation target chamber of temperature-controllable |
-
2015
- 2015-07-10 CN CN201510403800.2A patent/CN105021469A/en active Pending
Patent Citations (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN201397691Y (en) * | 2009-02-27 | 2010-02-03 | 中国科学院上海应用物理研究所 | High temperature irradiation box for irradiation of electron accelerator |
| CN101788453A (en) * | 2010-01-06 | 2010-07-28 | 中国科学院近代物理研究所 | High-temperature and stress energetic ion irradiation device |
| CN102590253A (en) * | 2012-01-17 | 2012-07-18 | 中国科学院上海应用物理研究所 | High-temperature fused salt synchrotron radiation in-situ research device |
| JP2014163777A (en) * | 2013-02-25 | 2014-09-08 | Mitsubishi Rayon Co Ltd | Tension testing device with high temperature furnace |
| CN104502202A (en) * | 2014-12-15 | 2015-04-08 | 吉林大学 | Online material biaxial static-dynamic performance test platform under service temperature |
| CN204374016U (en) * | 2015-01-12 | 2015-06-03 | 吉林大学 | The micro-nano impression test device of continuous regulating temp. type high vacuum low temperature |
| CN104596873A (en) * | 2015-01-26 | 2015-05-06 | 吉林大学 | System and method for testing temperature-varying micro-nanometer indentations with vacuum protection characteristics |
| CN205789142U (en) * | 2016-03-18 | 2016-12-07 | 国核（北京）科学技术研究院有限公司 | The Elevated temperature irradiation target chamber of temperature-controllable |
Cited By (14)
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|---|---|---|---|---|
| CN106501109A (en) * | 2016-09-13 | 2017-03-15 | 北京理工大学 | The in-situ nano impression test platform of energy storage material under a kind of electrochemical hot atmosphere |
| CN106714341A (en) * | 2016-12-21 | 2017-05-24 | 浙江师范大学 | Open-type heater manufacturing method used for synchronous-radiation in-situ test |
| CN106908848A (en) * | 2017-03-14 | 2017-06-30 | 北京华力兴科技发展有限责任公司 | Cask flask and radiation scanning inspection system for accommodating betatron |
| CN107144475A (en) * | 2017-04-16 | 2017-09-08 | 中国科学院近代物理研究所 | Elevated temperature irradiation creep device |
| CN107144475B (en) * | 2017-04-16 | 2019-10-18 | 中国科学院近代物理研究所 | Elevated temperature irradiation creep device |
| CN107885253B (en) * | 2017-11-21 | 2024-05-03 | 中国工程物理研究院电子工程研究所 | Precise temperature control device for semiconductor device dose rate effect experiment |
| CN107885253A (en) * | 2017-11-21 | 2018-04-06 | 中国工程物理研究院电子工程研究所 | A kind of precise temperature control device for the experiment of semiconductor devices dose rate effect |
| CN109883868A (en) * | 2019-03-22 | 2019-06-14 | 吉林大学 | Impression test device is impacted under hot environment |
| CN110182755A (en) * | 2019-05-17 | 2019-08-30 | 东南大学 | A kind of nanometer of press fit instrument Cryo Equipment |
| CN110182755B (en) * | 2019-05-17 | 2021-10-29 | 东南大学 | Low temperature device for nanometer pressing-in instrument |
| CN111122344A (en) * | 2020-01-06 | 2020-05-08 | 大连理工大学 | Structure for realizing ultrahigh-temperature heating of in-situ stretching CT imaging experiment of synchrotron radiation light source |
| CN111257351A (en) * | 2020-02-11 | 2020-06-09 | 大连理工大学 | Irradiation water-cooling sample platform |
| CN111257351B (en) * | 2020-02-11 | 2021-12-03 | 大连理工大学 | Irradiation water-cooling sample platform |
| CN114814149A (en) * | 2022-04-12 | 2022-07-29 | 哈尔滨工业大学 | Method for evaluating performance of Alnico alloy under irradiation and temperature field conditions |
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