CN202816399U - Water rod applied to supercritical water cooled reactor - Google Patents
Water rod applied to supercritical water cooled reactor Download PDFInfo
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- CN202816399U CN202816399U CN2012204643406U CN201220464340U CN202816399U CN 202816399 U CN202816399 U CN 202816399U CN 2012204643406 U CN2012204643406 U CN 2012204643406U CN 201220464340 U CN201220464340 U CN 201220464340U CN 202816399 U CN202816399 U CN 202816399U
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- water rod
- water
- wall
- moderator
- inwall
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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Abstract
The utility model discloses a water rod applied to a supercritical water cooled reactor, belonging to the technical field of nuclear reactor design. The water rod consists of an outer water rod wall and an inner water rod wall, wherein the outer water rod wall is made of two materials and is divided into three layers; the inner and outer layers are both made of stainless steel materials; the middle layer is made of a thermal insulating silicon material in which germanium nanocrystals are embedded; and the inner water rod wall is made of one material and has only one layer. A square annular outer water rod tube is formed by the surrounding of the outer water rod wall and the inner water rod wall; and a square inner water rod tube is formed by the surrounding of the inner water rod wall. According to the design of the water rod of a supercritical water cooled reactor, the structural design of the water rod is improved, and outer water rod wall materials with lower heat conductivity and inner water rod wall materials with higher heat conductivity are adopted, so that the axial temperature rise of a moderator is reduced, the moderation effect of the moderator is enhanced, and the uniformity of the axial power distribution of an reactor core is improved. The water rod has the characteristics of being simple in structure and smaller in design improvement of an original supercritical water cooled reactor component, and the security of the reactor is improved.
Description
Technical field
The utility model belongs to the nuclear reactor designs technical field, particularly a kind of water bar structure that is applicable to Supercritical-Pressure Light Water Cooled Reactor.Specifically, be to adopt the Double-layer water bar structure to change the Working fluid flow mode, choose the larger water rod inner-wall material of the less water rod outer wall materials of thermal conductivity and thermal conductivity, the moderator axial temperature rise is reduced, thereby play better slowing down effect, obtaining more uniformly, axial power distributes.
Background technology
Supercritical-Pressure Light Water Cooled Reactor be international nuclear energy circle generally acknowledge the 4th generation one of nuclear energy heap type.Supercritical-Pressure Light Water Cooled Reactor is operated under the temperature and pressure above working medium thermal technology critical point, and Supercritical-Pressure Light Water Cooled Reactor core structure and Working fluid flow mode have its oneself characteristics.More even for the reactor core axial power is distributed, in reactor core, be provided with the water bar structure.Mobile and the heat exchange characteristic of working medium has produced material impact to reactor core thermal-hydraulic and reactivity coefficient in the water rod.Most adopts the assembly of water bar structure to adopt individual layer water rod more, although the material that has used less thermal conductivity in this design as water rod wall material, owing to material technology and Cost Problems, moderator still has largely temperature rise in the water rod.The nineties in last century, the Japanology personnel once proposed the design of the double-deck pipe water rod of employing homogenous material, but were not applied in the overcritical component design of various ways.For many years, the thermal conductivity of material is higher becomes the bottleneck problem that restricts water rod function with version.Only have by suitable design water bar structure, and choose the water bar material of appropriate thermal conductance, just can reduce the moderator temperature rise, could reduce the heat that fuel channel is derived to the moderator passage.Obtain thus more uniformly moderator Temperature Distribution and power distribution, thereby can improve the fuel channel coolant outlet temperature, improve the thermal efficiency.
The utility model content
The utility model provides a kind of water bar structure that is applicable to Supercritical-Pressure Light Water Cooled Reactor that has than lower thermal conductivity.In the Supercritical-Pressure Light Water Cooled Reactor design, reduce moderator axial temperature rise in the Supercritical-Pressure Light Water Cooled Reactor, axial power distributes thereby obtain more uniformly.
The technical solution adopted in the utility model is as follows:
A kind of water rod that is applicable to Supercritical-Pressure Light Water Cooled Reactor, this water rod is comprised of water rod outer wall and water rod inwall, wherein, water rod outer wall is made of bi-material, be divided into three layers, its inside and outside two-layer stainless steel material that all adopts, the adiabatic silicon materials that embed the germanium nanocrystal body are adopted in the middle layer; Water rod inwall is made of a kind of material, only has one deck.
Water rod outer wall and water rod inwall have surrounded square annular water rod outer tube, and water rod inwall has surrounded square water rod inner tube.
Water rod outer wall middle layer is made of the adiabatic silicon materials that embed the germanium nanocrystal body, and its coefficient of heat conductivity can be brought down below 1W/(mK).Because good heat-insulating property can reduce the heat transmission between fuel channel and the moderator, reduce the moderator temperature rise, also can reduce material thickness simultaneously, and then reduce the absorption intensity to neutron.
Water rod inwall is to be made of Zirconium alloy material.When zircaloy is lower than 380 ℃ in temperature, have preferably anticorrosion properties and preferably mechanical property.Because good heat conductivility so that in the water rod outer tube in moderator and the water rod inner tube between the moderator heat exchange strengthen, thereby so that the distribution of moderator axial temperature is more even.
The inside and outside two-layer wall thickness of water rod outer wall is preferred 0.1mm to 0.3mm all, the preferred 0.5mm to 1.5mm of middle layer wall thickness, the preferred 1mm to 2mm of wall thickness of water rod inwall.
Moderator reversed flow in water rod outer tube and the water rod inner tube.In the water rod outer tube that is surrounded by water rod outer wall and water rod inwall, moderator flows downward.
The beneficial effects of the utility model are:
In the design of Supercritical-Pressure Light Water Cooled Reactor water rod, by improving the structural design of water rod, adopt the larger water rod inner-wall material of the less water rod outer wall materials of thermal conductivity and thermal conductivity, thereby the moderator axial temperature rise is reduced, moderator slowing down effect strengthens, and improves the homogeneity that the reactor core axial power distributes.
In the water rod inner tube that is surrounded by water rod inwall, moderator upwards flows.In the water rod outer tube that is surrounded by water rod outer wall and water rod inwall, moderator flows downward.In Supercritical-Pressure Light Water Cooled Reactor, adopt this kind water bar structure, can reduce the temperature rise of moderator, prevent that moderator is issued to the plan critical temperature in supercritical pressure, can strengthen the slowing down effect, improve the axial power skewness factor of assembly.This water rod has simple in structure, and former supercritical water reactor component design is improved less characteristics, the security that can improve reactor.
Description of drawings
Fig. 1 is the reactor core Working fluid flow mode figure that adopts the utility model water rod assembly;
Fig. 2 is the horizontal sectional drawing of water bar structure of the present utility model.
Number in the figure:
1, upper chamber; 2, passage between hanging basket and pressure vessel; 3, reactor core entrance; 4, fuel rod; 5, water rod outer tube; 6, water rod inner tube; 7, fuel channel; 8, lower collecting box; 9, lower chambers; 10, core exit; 11, water rod outer wall stainless steel layer; 12, water rod outer wall heat insulation layer; 13, water rod inwall; 14, water rod outer wall.
Embodiment
The following examples can make those skilled in the art more fully understand the utility model, but limit never in any form the utility model.
The purpose of this utility model is larger for moderator temperature rise in the water rod in the present Supercritical-Pressure Light Water Cooled Reactor component design, makes the axial moderation of neutrons of assembly inhomogeneous, a kind of novel double-layer water bar structure of proposition.The water rod outer wall 14 of water rod adopts the less material of temperature conductivity, and water rod inwall 13 adopts the larger material of thermal conductivity, thereby reduces the moderator axial temperature rise.Be explained below in conjunction with accompanying drawing.
Fig. 1 is the reactor core Working fluid flow mode figure of Double-layer water rod assembly.What working medium was turned back in core flows three times, respectively by water rod inner tube 6, water rod outer tube 5 and fuel channel 7.The concrete type of flow is: working medium enters in the heap by entrance 3, is divided into two parts and flows through the passage 2 between hanging basket and pressure vessel, and a part upwards flows into upper chamber 1, and another part flows downward and enters lower chambers 9.The working medium that enters lower chambers 9 upwards flows into upper chamber 1 by water rod inner tube 6.Flow downward through water rod outer tube 5 after working medium in the upper chamber is mixed and enter lower collecting box 8, then from bottom to top by fuel channel 7, receive the heat that is produced by fuel rod 4.Working medium finally flows out reactor core by outlet 10.
Fig. 2 is the horizontal sectional drawing of water rod basic structure.The water rod that is applicable to Supercritical-Pressure Light Water Cooled Reactor is comprised of water rod outer wall 14 and water rod inwall 13, wherein, water rod outer wall 14 is made of bi-material, is divided into three layers, water rod outer wall inside and outside two-layer 11 all adopts stainless steel material, and the adiabatic silicon materials that embed the germanium nanocrystal body are adopted in middle layer 12; Water rod inwall 13 only has one deck, employing be Zirconium alloy material.
Water rod outer wall 14 inside and outside two-layer 11 wall thickness are 0.2mm, and middle layer 12 wall thickness are 1.0mm, and the wall thickness of water rod inwall 13 is 1.5mm.
Water rod outer wall 14 and water rod inwall 13 have surrounded square annular water rod outer tube 5, and water rod inwall 13 has surrounded square water rod inner tube 6.
In the water rod outer tube 5 that is surrounded by water rod outer wall and water rod inwall in the described water rod, moderator flows downward.
In the water rod inner tube 6 that is surrounded by water rod inwall in the described water rod, moderator upwards flows.
The adiabatic silicon materials of the embedding germanium nanocrystal body that adopt in related water rod outer wall middle layer 12, so that heat exchange amount minimizing between the moderator in fuel channel 7 and the water rod outer tube 5, thereby so that the moderator temperature rise reduces, coolant heat-up increases.
Related water rod inwall 13 adopts preferably Zirconium alloy material of heat conductivility, so that heat exchange enhancing between the moderator in moderator and the water rod inner tube 6 in the water rod outer tube 5, again because water rod outer tube 5 and water rod inner tube 6 interior moderator reversed flow, thereby so that the moderator axial temperature distributes more even.
The above; it only is the better embodiment of the utility model; but protection domain of the present utility model is not limited to this; anyly be familiar with those skilled in the art in the technical scope that the utility model discloses; the variation that can expect easily or replacement all should be encompassed within the protection domain of the present utility model.Therefore, protection domain of the present utility model should be as the criterion with the protection domain of claim.
Claims (6)
1. a water that is applicable to Supercritical-Pressure Light Water Cooled Reactor is excellent, it is characterized in that: this water rod is comprised of water rod outer wall (14) and water rod inwall (13), wherein, water rod outer wall (14) is made of bi-material, be divided into three layers, its inside and outside two-layer (11) all adopt stainless steel material, and middle layer (12) adopt the adiabatic silicon materials that embed the germanium nanocrystal body; Water rod inwall (13) is made of a kind of material, only has one deck.
2. water according to claim 1 is excellent, it is characterized in that: described water rod inwall (13) is made of Zirconium alloy material.
3. water according to claim 1 is excellent, it is characterized in that: inside and outside two-layer (11) wall thickness of water rod outer wall (14) is 0.1mm to 0.3mm, and middle layer (12) wall thickness is 0.5mm to 1.5mm, and the wall thickness of water rod inwall (13) is 1mm to 2mm.
4. water according to claim 1 is excellent, it is characterized in that: water rod outer wall (14) and water rod inwall (13) have surrounded square annular water rod outer tube (5), and water rod inwall (13) has surrounded the excellent inner tube (6) of square water.
5. water rod according to claim 4 is characterized in that: water rod outer tube (5) and the interior moderator reversed flow of water rod inner tube (6).
6. water according to claim 4 is excellent, it is characterized in that: in the water rod outer tube (5) that is surrounded by water rod outer wall and water rod inwall in the described water rod, moderator flows downward, and in the water rod inner tube (6) that is surrounded by water rod inwall in the described water rod, moderator upwards flows.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2012204643406U CN202816399U (en) | 2012-09-12 | 2012-09-12 | Water rod applied to supercritical water cooled reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2012204643406U CN202816399U (en) | 2012-09-12 | 2012-09-12 | Water rod applied to supercritical water cooled reactor |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN202816399U true CN202816399U (en) | 2013-03-20 |
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| Application Number | Title | Priority Date | Filing Date |
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| CN2012204643406U Expired - Fee Related CN202816399U (en) | 2012-09-12 | 2012-09-12 | Water rod applied to supercritical water cooled reactor |
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| CN (1) | CN202816399U (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102855946A (en) * | 2012-09-12 | 2013-01-02 | 华北电力大学 | Water rod used in supercritical water-cooled reactor |
| CN110828006A (en) * | 2019-11-18 | 2020-02-21 | 中国核动力研究设计院 | Coolant staggered flowing type fuel assembly and supercritical water cooled reactor |
-
2012
- 2012-09-12 CN CN2012204643406U patent/CN202816399U/en not_active Expired - Fee Related
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102855946A (en) * | 2012-09-12 | 2013-01-02 | 华北电力大学 | Water rod used in supercritical water-cooled reactor |
| CN102855946B (en) * | 2012-09-12 | 2015-10-21 | 华北电力大学 | A kind of water rod being applicable to Supercritical-Pressure Light Water Cooled Reactor |
| CN110828006A (en) * | 2019-11-18 | 2020-02-21 | 中国核动力研究设计院 | Coolant staggered flowing type fuel assembly and supercritical water cooled reactor |
| CN110828006B (en) * | 2019-11-18 | 2021-08-24 | 中国核动力研究设计院 | Coolant staggered flowing type fuel assembly and supercritical water cooled reactor |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C14 | Grant of patent or utility model | ||
| GR01 | Patent grant | ||
| C17 | Cessation of patent right | ||
| CF01 | Termination of patent right due to non-payment of annual fee |
Granted publication date: 20130320 Termination date: 20130912 |