CN111161897A - High-power thick rod fuel element simulation device - Google Patents

High-power thick rod fuel element simulation device Download PDF

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Publication number
CN111161897A
CN111161897A CN201911380800.XA CN201911380800A CN111161897A CN 111161897 A CN111161897 A CN 111161897A CN 201911380800 A CN201911380800 A CN 201911380800A CN 111161897 A CN111161897 A CN 111161897A
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section
tube
heating
heating section
cylinder body
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CN111161897B (en
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陈森
杨宁
李华琪
朱磊
康小亚
田晓艳
陈立新
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Northwest Institute of Nuclear Technology
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    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C17/00Monitoring; Testing ; Maintaining
    • G21C17/001Mechanical simulators
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

The invention relates to a high-power thick rod fuel element simulation device. Comprises a heating component and a cylinder body; the heating assembly is sleeved in the cylinder body, and a medium circulation channel is formed between the heating assembly and the cylinder body; the heating assembly comprises a heat-conducting core rod, a screw plug, an outer electric conduction tube, a ceramic inner tube, a ceramic outer tube, a connecting tube and a positioning head; according to the invention, by reasonably arranging the positions of the thermocouple, the pressure gauge and the interface of the pressure difference gauge and the arrangement of the heating section and the non-heating section in the heat-conducting core rod, the operation condition of the pool type research reactor is met, the high-power stable operation is realized, and the research on the critical heat flux density of the pool type research reactor is realized.

Description

High-power thick rod fuel element simulation device
Technical Field
The invention belongs to the field of thermal hydraulic experiment research, and particularly relates to a high-power thick rod fuel element simulation device.
Background
The critical heat flux density phenomenon of the surface of the cladding of the fuel element is not allowed in the thermal safety design rule of the reactor. Therefore, critical heat flux density experimental study needs to be carried out in reactor design to obtain the critical heat flux density under different operating conditions so as to ensure the thermal safety performance of the reactor.
The reactor core of the pool type fuel elements is arranged in an equilateral triangle, 9 circles of 211 hole sites are provided, wherein the standard fuel elements occupy 99 hole sites, the diameter of each fuel element is 37.2mm, the length of each fuel segment is 0.39mm, and the structural size of each fuel element is greatly different from that of a conventional pressurized water reactor fuel element.
Chinese patent, application number: 201711004546.4 discloses a pressurized water reactor fuel assembly simulation device with low voltage and high power, which provides a square flow passage assembly, can realize the simulation of the pressurized water reactor assembly with low voltage and high power, and is used for the experimental study of critical heat flux density and flow instability of the pressurized water reactor fuel assembly. However, the invention is not suitable for being used as a simulation device of the fuel element of the pool type stack, so that the experimental study of the critical heat flux density cannot be carried out.
Disclosure of Invention
In order to solve the problem that the existing simulation assembly is not suitable for being used as a simulation device of a pool type stack fuel element, the invention provides a high-power thick rod fuel element simulation device.
In order to achieve the purpose, the invention adopts the following technical scheme:
the invention provides a high-power thick rod fuel element simulation device, which comprises a heating assembly and a cylinder body;
the heating assembly is sleeved in the cylinder body, and a medium circulation channel is formed between the heating assembly and the cylinder body;
the heating assembly comprises a heat-conducting core rod, a screw plug, an outer electric conduction tube, a ceramic inner tube, a ceramic outer tube, a connecting tube and a positioning head;
the outer conductive tube is coaxially sleeved outside the heat-conducting core rod, a ceramic inner tube is arranged on the part of the outer wall of the heat-conducting core rod, which is positioned in the outer conductive tube, a ceramic outer tube is arranged on the inner wall of the corresponding outer conductive tube, and an annular cavity is formed between the ceramic inner tube and the ceramic outer tube;
the heat conducting core rod comprises an upper non-heating section, a middle heating section and a lower non-heating section;
a quick heat conducting cylinder is sleeved on the outer wall of the outer conducting tube at a position corresponding to the middle heating section;
a first thermocouple interface for installing the temperature of the measured medium is arranged on the middle heating section corresponding to the cylinder;
an external pressure gauge mounting interface is arranged at the heating starting point of the middle heating section and is used for measuring the pressure of the heating starting point;
an external differential pressure meter installation interface is arranged at the heating end point of the middle heating section and is used for measuring the differential pressure of the heating section;
the middle heating section corresponding to the cylinder body is provided with a second thermocouple interface for installing and measuring the temperature of the rapid heat conducting cylinder;
the upper end of the outer conductive tube is in threaded connection with the screw plug, the lower end of the outer conductive tube is connected with a positioning head through a connecting tube, and the positioning head is matched with the barrel body and used for fixing the whole heating assembly in the barrel body;
the heat conducting core rod and the outer electric conducting tube are respectively connected with the anode and the cathode of an external power supply.
Furthermore, the number of the first thermocouple ports is four, and the first thermocouple ports are arranged on the cylinder body corresponding to the middle heating section from bottom to top along the medium flow direction; nine second thermocouple interfaces are arranged on the middle heating section corresponding barrel from bottom to top in sequence along the medium flow direction, and the distance between every two adjacent second thermocouple interfaces is gradually reduced from bottom to top.
Further, the distance from the nine second thermocouple interfaces to the terminal point of the middle heating section along the axial direction is respectively 10mm, 30mm, 50mm, 70mm, 100mm, 150mm, 200mm, 300mm and 390 mm.
Further, the cylinder comprises an inlet pipe and an outlet pipe;
the inlet pipe is of a bent pipe structure with flanges at two ends;
the outlet pipe comprises a vertical section, an expansion section and a horizontal section; the vertical section and the expansion section are sequentially communicated, the horizontal section is communicated with the middle part of the expansion section, and flanges are arranged at the lower end of the vertical section, the upper end of the expansion section and the left end of the horizontal section; the lower end of the vertical section is communicated with the inlet pipe through a flange; the left end of the horizontal section is communicated with the external equipment through a flange;
the pipe diameter of the lower half part of the expansion section is gradually increased from bottom to top, and the pipe diameters of the upper half part of the expansion section are the same.
Furthermore, the material of the rapid heat conduction cylinder is Inconel 625, the thickness is 0.6mm, and the effective length is 390 mm.
Further, the length of the middle heating section is 390mm, the outer diameter is 37.2mm, the length of the upper non-heating section is 400mm, and the length of the lower non-heating section is 700 mm.
Further, the conductive core rod and the outer conductive tube are both made of copper materials, wherein the temperature resistance of the conductive core rod is 350 ℃.
Compared with the prior art, the invention has the following advantages:
1. the heating assembly and the cylinder are adopted to form the simulating device of the fuel element of the pool type reactor, the positions of the thermocouple, the pressure gauge and the differential pressure gauge are reasonably arranged, and the heating section and the non-heating section in the heat-conducting core rod are arranged, so that the operating condition of the pool type reactor can be met, the high-power stable operation can be realized, and the research on the critical heat flux density of the pool type reactor can be realized.
2. Nine second thermocouple interfaces are arranged (namely nine second thermocouples can be installed), and the thermocouples are arranged densely in the axial direction towards the tail end of the middle heating section.
3. The lower part and the upper part of the heating section in the heat-conducting core rod are respectively non-heating sections, so that the inlet and the outlet of the fluid can be fully developed.
4. The expansion section is arranged in the outlet pipe in the cylinder body, and the purpose of the expansion section is to fully consider the expansion and volume increase of fluid when the fluid is heated and relieve the problem of flow instability in practical experiments.
5. The dimensions and parameter design of the cylinder and the heating assembly can realize the simulation of short and thick fuel elements.
Drawings
Fig. 1 is a schematic structural view illustrating the installation of a first thermocouple, a load cell, and a differential pressure gauge in the present invention.
Fig. 2 is a schematic view of the structure of the inlet tube.
Figure 3 is a schematic view of the outlet tube.
Fig. 4 is a schematic structural view of the heating assembly.
Fig. 5 is a schematic view of the distribution of the mounting positions of the nine second thermocouples.
The reference numbers are as follows:
1-cylinder body, 11-inlet pipe, 111-inlet buffer flange, 112-horizontal buffer section, 113-bend section, 114-vertical buffer section, 115-inlet bottom flange, 12-outlet pipe, 121-vertical section, 122-expansion section, 123-horizontal section, 2-heating component, 21-heat conducting core rod, 211-upper non-heating section, 212-middle heating section, 213-lower non-heating section, 22-screw plug, 23-outer electric conduction pipe, 24-ceramic inner pipe, 25-ceramic outer pipe, 26-connecting pipe, 27-positioning head, 28-rapid heat conduction cylinder, 29-annular chamber, 3-first thermocouple, 4-second thermocouple, 5-pressure gauge and 6-differential pressure gauge.
Detailed Description
The invention is further described with reference to the following figures and specific embodiments.
The core heat source is the generation of energy by fission of nuclear fuel. In the critical heat flux density experiment, the heating of the fuel element is simulated by an electric heating mode, and the size of the heating part of the simulated element is consistent with that of the heating part of the fuel element of the pool type stack.
The experimental working condition is required to be consistent with the operation working condition of the pool type reactor, namely the natural circulation requirement is met, and the inlet pressure of the reactor core is 0.16 MPa. To meet the critical heat flow density experimental requirements, the analog device power must reach a predetermined value, and the dimensions and characteristics of the selected analog components are determined for the power requirements.
In the critical heat flow density experiment, the occurrence of the critical heat flow density phenomenon is generally determined by simulating the sharp rise of the temperature of the outer surface of the element. In practice, in order to obtain the outer surface temperature of the dummy member, the inner surface temperature of the dummy member is generally measured by a thermocouple, and the outer surface temperature is calculated. Thus, the thermocouple is arranged on the inner surface of the simulation element, and the interference of thermocouple leads to a flow field is reduced.
The embodiment provides a high-power thick rod fuel element simulation device, which has a structure shown in fig. 1 and comprises a cylinder 1 and a heating assembly 2;
the heating component 2 is sleeved in the cylinder body 1, and a medium circulation channel is formed between the heating component 2 and the cylinder body 1;
the barrel 1 comprises an inlet pipe 11 and an outlet pipe 12;
the inlet pipe 11 is a bent pipe structure with flanges at two ends, and the specific structure is shown in fig. 2, and includes an inlet buffer flange 111, a horizontal buffer section 112, a bent pipe section 113, a vertical buffer pipe section 114, and an inlet bottom flange 115. The diameter of the inlet pipe is 50mm, adopts stainless steel material preparation, and horizontal buffer section 112 and vertical buffer tube 114 length are 200mm and 150mm respectively, and vertical buffer tube 114 can guarantee that the fluid fully develops in the experimental section.
As shown in fig. 3, the outlet pipe 12 includes a vertical section 121, an expansion section 122, and a horizontal section 123; the vertical section 121 and the expansion section 122 are communicated in sequence, the horizontal section 123 is communicated with the middle of the expansion section 122, and flanges are arranged at the lower end of the vertical section 121, the upper end of the expansion section 122 and the left end of the horizontal section 123; the lower end of the vertical section 121 is communicated with an inlet bottom flange 115 of the inlet pipe through a flange; the left end of the horizontal section 123 is communicated with external equipment through a flange; the pipe diameter of the lower half part of the expansion section 122 is gradually increased from bottom to top, the pipe diameters of the upper half part of the expansion section 122 are the same, buffering with a certain length is guaranteed after fluid is heated and expanded in an experiment, and the stability of pressure in the experiment process is guaranteed; wherein, vertical section 121 passes through the proportion between the flow area of thick stick single channel and the heating girth, confirms that the pipe diameter is 45.3mm, and this design can guarantee that the thermal technology water conservancy that flows is similar. The 123 inner diameter of the horizontal section is 60mm, the length is 200mm, a stainless steel pipeline is adopted, the wall thickness of the stainless steel of the flow channel is 7mm, and the experiment pressure-bearing requirement can be met.
Many places of this barrel adopt flange joint, make things convenient for the quick installation of whole device to remove and trade.
As shown in fig. 4, the heating assembly 2 is sleeved in the cylinder 1, and a medium circulation channel is formed between the heating assembly 2 and the cylinder 1;
the heating assembly 2 comprises a heat conducting core rod 21, a screw plug 22, an outer electric conducting tube 23, a ceramic inner tube 24, a ceramic outer tube 25, a connecting tube 26 and a positioning head 27;
the outer conductive tube 23 is coaxially sleeved outside the heat conducting core rod 21, the ceramic inner tube 24 is arranged on the outer wall of the part, located in the outer conductive tube 23, of the heat conducting core rod 21, the ceramic outer tube 25 is arranged on the inner wall of the corresponding outer conductive tube 23, an annular cavity 29 is formed between the ceramic inner tube 24 and the ceramic outer tube 25, the ceramic inner tube 24 and the ceramic outer tube 25 play an insulating role, and meanwhile, due to the fact that the ceramic material is large in heat conductivity coefficient, efficient heat conduction can be achieved.
The heat-conducting core rod 21 comprises an upper non-heating section 211, a middle heating section 212 and a lower non-heating section 213; wherein, the length of the middle heating section 212 is 390mm, the outer diameter is 37.2mm, the length of the upper non-heating section 211 is 400mm, and the length of the lower non-heating section 213 is 700 mm.
A rapid heat conducting tube 28 is sleeved on the outer wall of the outer conductive tube 23 corresponding to the middle heating section 212; the quick heat conducting cylinder 28 is made of Inconel 625, the thickness is 0.6mm, the effective length is 390mm, the cross section area is small, the pipe wall is thin, the thermal resistance is large, and the structural design can ensure the maximum power output of 55kW on the heating pipe surface.
The middle heating section 212 is provided with four first thermocouple ports corresponding to the cylinder 1 for installing measured medium temperature (i.e. four first thermocouples 3 are also installed on the cylinder corresponding to the middle heating section from bottom to top along the medium flow direction).
An external pressure gauge 5 mounting interface is arranged at the heating starting point of the middle heating section 222 and is used for measuring the pressure of the heating starting point;
an external differential pressure gauge 6 mounting interface is arranged at the heating end point of the middle heating section 212 and is used for measuring the differential pressure of the heating section;
the middle heating section 212 is provided with a second thermocouple interface corresponding to the cylinder body 1 and used for installing and measuring the temperature of the rapid heat-conducting cylinder 28; in this embodiment, the number of the second thermocouple interfaces is nine, that is, the number of the second thermocouples 4 is also nine, and the second thermocouples are sequentially installed on the cylinder corresponding to the middle heating section from bottom to top along the medium flow direction, the distance between the adjacent second thermocouples 6 is gradually reduced from bottom to top, the specific arrangement mode is shown in fig. 5, and the distance between the nine second thermocouples and the terminal point of the middle heating section along the axial direction is respectively 10mm, 30mm, 50mm, 70mm, 100mm, 150mm, 200mm, 300mm, and 390 mm. The mode of nonuniform arrangement of the thermocouples can accurately judge the occurrence of critical heat flux density and prevent the heating rod from being burnt.
The upper end of the outer conductive tube 23 is in threaded connection with the screw plug 22, the lower end of the outer conductive tube 23 is connected with a positioning head 27 through a connecting tube 26, and the positioning head 27 is matched with the cylinder 1 to fix the whole heating assembly 2 in the cylinder 1;
the heat conducting core rod 21 and the outer electric conducting tube 23 are respectively connected with the positive electrode and the negative electrode of an external power supply. The conductive core rod 21 and the outer conductive tube 23 adopt cylindrical rods, and the conductive copper rod can resist the temperature of 350 ℃.
The foregoing is illustrative of the present invention only and is not to be construed as limiting thereof, and variations and modifications to the above-described embodiments, within the true spirit and scope of the invention, should be considered as within the scope of the claims of the present invention to those skilled in the art.

Claims (7)

1. A high power raw rod fuel element simulation apparatus, characterized by: comprises a cylinder body (1) and a heating component (2);
the heating component (2) is sleeved in the cylinder body (1), and a medium circulation channel is formed between the heating component (2) and the cylinder body (1);
the heating assembly (2) comprises a heat conducting core rod (21), a screw plug (22), an outer electric conducting tube (23), a ceramic inner tube (24), a ceramic outer tube (25), a connecting tube (26) and a positioning head (27);
the outer conductive tube (23) is coaxially sleeved outside the heat conducting core rod (21), a ceramic inner tube (24) is arranged on the outer wall of the part, located in the outer conductive tube (23), of the heat conducting core rod (21), a ceramic outer tube (25) is arranged on the inner wall of the corresponding outer conductive tube (23), and an annular cavity (29) is formed between the ceramic inner tube (24) and the ceramic outer tube (25);
the heat conducting core rod (21) comprises an upper non-heating section (211), a middle heating section (212) and a lower non-heating section (213);
a rapid heat conducting tube (28) is sleeved on the outer wall of the outer conductive tube (23) corresponding to the middle heating section (212);
a first thermocouple interface for installing the temperature of the measured medium is arranged on the middle heating section (212) corresponding to the cylinder;
an external pressure gauge (5) mounting interface is arranged at the heating starting point of the middle heating section (212) and is used for measuring the pressure of the heating starting point;
an external differential pressure gauge (6) mounting interface is arranged at the heating end point of the middle heating section (212) and is used for measuring the differential pressure of the heating section;
a second thermocouple interface for installing and measuring the temperature of the rapid heat-conducting cylinder (28) is arranged on the middle heating section (212) corresponding to the cylinder body;
the upper end of the outer conductive tube (23) is in threaded connection with the screw plug (22), the lower end of the outer conductive tube (23) is connected with a positioning head (27) through a connecting tube (26), and the positioning head (27) is matched with the cylinder body (1) to fix the whole heating assembly (2) in the cylinder body;
the heat conducting core rod (21) and the outer electric conduction tube (23) are respectively connected with the positive pole and the negative pole of an external power supply.
2. The high power slim fuel element simulation device of claim 1, wherein: the number of the first thermocouple ports is four, and the first thermocouple ports are arranged on the cylinder body corresponding to the middle heating section from bottom to top along the medium flow direction; nine second thermocouple interfaces are arranged on the middle heating section corresponding barrel from bottom to top in sequence along the medium flow direction, and the distance between every two adjacent second thermocouple interfaces is gradually reduced from bottom to top.
3. The high power slim fuel element simulation device of claim 2, wherein: the distance between the nine second thermocouple interfaces and the terminal point of the middle heating section along the axial direction is respectively 10mm, 30mm, 50mm, 70mm, 100mm, 150mm, 200mm, 300mm and 390 mm.
4. The high power slim fuel element simulation device of claim 3, wherein: the cylinder (1) comprises an inlet pipe (11) and an outlet pipe (12); the inlet pipe (11) is of a bent pipe structure with flanges at two ends; the outlet pipe (12) comprises a vertical section (121), an expansion section (122) and a horizontal section (123); the vertical section (121) and the expansion section (122) are sequentially communicated, the horizontal section (123) is communicated with the middle of the expansion section (122), and flanges are arranged at the lower end of the vertical section (121), the upper end of the expansion section (122) and the left end of the horizontal section (123); the lower end of the vertical section (121) is communicated with the inlet pipe (11) through a flange; the left end of the horizontal section (123) is communicated with external equipment through a flange; the pipe diameter of the lower half part of the expansion section (122) is gradually increased from bottom to top, and the pipe diameters of the upper half part of the expansion section are the same.
5. The high power slim fuel element simulation device of claim 4, wherein: the quick heat conducting cylinder (28) is made of Inconel 625, the thickness is 0.6mm, and the effective length is 390 mm.
6. The high power slim fuel element simulation device of claim 5, wherein: the length of the middle heating section (212) is 390mm, the outer diameter is 37.2mm, the length of the upper non-heating section (211) is 400mm, and the length of the lower non-heating section (213) is 700 mm.
7. The high power slim fuel element simulation device of claim 6, wherein: the conductive core rod (21) and the outer conductive tube (23) are both made of copper materials, wherein the temperature resistance of the conductive core rod is 350 ℃.
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Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN111505428A (en) * 2020-05-25 2020-08-07 西安交通大学 Test section for simulating heating fluid of cylindrical heating rod in pipe

Citations (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB1457670A (en) * 1973-06-11 1976-12-08 Varian Associates Nuclear reactor fuel rod thermal simulator
US5200144A (en) * 1992-06-22 1993-04-06 The United States Of America As Represented By The United States Department Of Energy Simulated nuclear reactor fuel assembly
JPH08240688A (en) * 1994-10-25 1996-09-17 General Electric Co <Ge> Apparatus for simulation of transient change of nuclear fuelrod bundle
US6704385B1 (en) * 1998-08-18 2004-03-09 Campagnie General Des Matieres Nucleaires Method for simulating the response of a detector of radiation emitted by radioactive objects and method for controlling nuclear fuel elements using said simulation
CN101335058A (en) * 2008-08-06 2008-12-31 中国原子能科学研究院 Fuel assembly simulation piece of sodium-cooled fast reactor
CN105788680A (en) * 2016-03-30 2016-07-20 中国核动力研究设计院 Heating simulation element for reactor core
CN107146643A (en) * 2016-11-25 2017-09-08 中国核动力研究设计院 A kind of novel reaction heap analogue body
CN107945895A (en) * 2017-06-19 2018-04-20 重庆大学 A kind of non-homogeneous electrically heated nuclear fuel simulation rod

Patent Citations (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB1457670A (en) * 1973-06-11 1976-12-08 Varian Associates Nuclear reactor fuel rod thermal simulator
US5200144A (en) * 1992-06-22 1993-04-06 The United States Of America As Represented By The United States Department Of Energy Simulated nuclear reactor fuel assembly
JPH08240688A (en) * 1994-10-25 1996-09-17 General Electric Co <Ge> Apparatus for simulation of transient change of nuclear fuelrod bundle
US6704385B1 (en) * 1998-08-18 2004-03-09 Campagnie General Des Matieres Nucleaires Method for simulating the response of a detector of radiation emitted by radioactive objects and method for controlling nuclear fuel elements using said simulation
CN101335058A (en) * 2008-08-06 2008-12-31 中国原子能科学研究院 Fuel assembly simulation piece of sodium-cooled fast reactor
CN105788680A (en) * 2016-03-30 2016-07-20 中国核动力研究设计院 Heating simulation element for reactor core
CN107146643A (en) * 2016-11-25 2017-09-08 中国核动力研究设计院 A kind of novel reaction heap analogue body
CN107945895A (en) * 2017-06-19 2018-04-20 重庆大学 A kind of non-homogeneous electrically heated nuclear fuel simulation rod

Non-Patent Citations (1)

* Cited by examiner, † Cited by third party
Title
郎雪梅: "5×5全长棒束非均匀加热管设计", 《核动力工程》 *

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN111505428A (en) * 2020-05-25 2020-08-07 西安交通大学 Test section for simulating heating fluid of cylindrical heating rod in pipe

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