CN111243766A - Tritium trapping device of molten salt cooling nuclear reactor and working method - Google Patents
Tritium trapping device of molten salt cooling nuclear reactor and working method Download PDFInfo
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- CN111243766A CN111243766A CN202010045262.5A CN202010045262A CN111243766A CN 111243766 A CN111243766 A CN 111243766A CN 202010045262 A CN202010045262 A CN 202010045262A CN 111243766 A CN111243766 A CN 111243766A
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- molten salt
- tritium
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- heat pipe
- pipeline
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21B—FUSION REACTORS
- G21B1/00—Thermonuclear fusion reactors
- G21B1/11—Details
- G21B1/115—Tritium recovery
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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
- Y02E30/10—Nuclear fusion reactors
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- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Vaporization, Distillation, Condensation, Sublimation, And Cold Traps (AREA)
Abstract
The invention belongs to the technical field of nuclear reactors and discloses a tritium trapping device of a molten salt cooling nuclear reactor and a working method. The tritium trapping device can be used for trapping tritium and preventing permeation of primary side tritium gas to a secondary side, can realize heat exchange of primary side molten salt and a secondary side working medium, and can effectively prevent solidification of the primary side molten salt by utilizing the working characteristics of the heat pipe, so that the tritium trapping device has the advantages of multiple functions, compact structure and high economical efficiency.
Description
Technical Field
The invention relates to the technical field of nuclear reactors, in particular to a tritium trapping device of a molten salt cooling nuclear reactor and a working method.
Background
Molten salt can be used as working medium in both molten salt reactor and nuclear fusion reactor. In molten salt piles, molten salt is used as a coolant, and in order to reduce the freezing point of the molten salt, lithium fluoride is often added into the molten salt, and the isotope of lithium6Under neutron irradiation conditions, Li produces tritium. In a nuclear fusion reactor, the addition of molten salt is higher6Lithium fluoride with Li enrichment asTritium breeder, while also being a fusion blanket coolant. Because the tritium gas has extremely strong permeability, the tritium gas is easy to permeate into the surrounding environment from the reactor core, and further causes irradiation dose to the public, therefore, the strengthening of the control of the tritium in the molten salt cooling nuclear reactor has great significance for the development of the molten salt reactor and the fusion reactor.
Currently, the control or capture strategies for tritium in molten salt cooled reactors mainly include: (1) tritium is absorbed in the molten salt through a graphite ball bed; (2) a tritium permeation window is made of a material with high tritium permeation rate, so that tritium extraction is realized; (3) discharging tritium gas dissolved in the molten salt into a tritium scavenging system by using an oxidation-reduction control mode; (4) a double-layer heat exchange tube is adopted in the heat exchanger, working media on the primary side and the secondary side are respectively arranged on the innermost layer and the outermost layer, and the middle layer is communicated with a tritium scavenging system.
The tritium trapping system is single in function, not compact enough in structure and low in economical efficiency, and although the mode (4) has the function of a heat exchanger, the heat resistance is increased due to the double-layer heat exchange tube, so that the heat exchange efficiency is reduced. In order to achieve compact collection of tritium capture, new tritium capture approaches need to be explored.
Disclosure of Invention
The invention aims to provide a multifunctional, intensive, compact and high-economical tritium trapping device for a molten salt cooling nuclear reactor and a working method thereof, so as to prevent tritium in primary side molten salt from permeating into a secondary side.
In order to achieve the purpose, the invention adopts the following technical scheme:
a tritium trapping device of a molten salt cooling nuclear reactor comprises a primary molten salt pipeline 1, a secondary working medium pipeline 4, a heat pipe 2 and a tritium blowing and scavenging device 3; the primary side molten salt pipeline 1 is communicated with a core of the molten salt cooling nuclear reactor, and primary side molten salt in the primary side molten salt pipeline 1 is molten salt flowing through the core of the molten salt cooling nuclear reactor; a gap is reserved between the primary side fused salt pipeline 1 and the secondary side working medium pipeline 4, a heat pipe evaporation section 2-1 of the heat pipe 2 is inserted into fused salt of the primary side fused salt pipeline 1, a heat pipe heat insulation section 2-2 is positioned in the gap of the primary side, a heat pipe condensation section 2-3 is inserted into a secondary side working medium of the secondary side working medium pipeline 4, and the primary side fused salt pipeline 1 and the secondary side working medium pipeline 4 realize heat exchange through the heat pipe 2; the tritium purging device 3 is used for purging tritium gas penetrating into the primary side molten salt and the secondary side gap to the tritium collecting device.
The working medium in the secondary side working medium pipeline 4 is a secondary circuit coolant of the molten salt cooling nuclear reactor, and the primary and secondary side working media are arranged in a concurrent flow or countercurrent flow mode.
The outer layer of the evaporation section 2-1 of the heat pipe inserted into the primary side molten salt of the primary side molten salt pipeline 1 is coated with metal tungsten, so that the permeation amount of tritium in the primary side molten salt to the heat pipe is obviously reduced.
The primary side fused salt pipeline 1-1 is made of high-temperature alloy which has high tritium permeability compared with tungsten, so that tritium gas in the primary side fused salt can permeate into the middle gap through the wall surface.
The heat pipes are arranged in a staggered manner in the primary side molten salt pipeline 1 and the secondary side working medium pipeline 4.
The working method of the tritium trapping device of the molten salt cooling nuclear reactor is characterized in that primary side molten salt from a reactor core of the molten salt cooling nuclear reactor washes a heat pipe evaporation section 2-1 from left to right through a main pump, heat is transferred to a heat pipe 2, and a heat pipe working medium is evaporated; the secondary side working medium scours the heat pipe condensation section 2-3 from right to left, the heat pipe working medium steam flows to the heat pipe condensation section 2-3 to be condensed, and heat is transferred to the secondary side working medium; tritium gas permeates into a middle gap from primary side molten salt through the pipe wall of the primary side molten salt pipeline 1, and gas is blown into the tritium scavenging device 3 to carry the tritium gas to the tritium collecting device.
Compared with the prior art, the invention has the following advantages:
1) the invention enables the tritium gas in the primary side molten salt to permeate into the middle gap through the primary side pipe wall, and realizes the capture of the tritium by using the tritium purging gas device, thereby effectively preventing the tritium gas in the primary side from permeating to the secondary side.
2) The heat pipe realizes the heat exchange between the primary side molten salt and the secondary side working medium, and the heat pipe can effectively transfer heat only when the temperature of the primary side is higher than the preset temperature, so that the temperature of the primary side molten salt is not lower than the set temperature (such as the molten salt solidification point temperature) under the normal operation condition of the reactor, the primary side molten salt is not solidified, and the reactor core of the nuclear reactor can be effectively cooled.
3) Because the device has multiple functions such as tritium entrapment, realization a secondary side heat transfer and prevention once side fused salt solidification simultaneously, has integrated original single function device, has improved system compactness and economic nature.
Drawings
FIG. 1 is a front view of a molten salt cooled nuclear reactor tritium trap apparatus of the present invention.
FIG. 2 is a top view of a molten salt cooled nuclear reactor tritium trap apparatus of the present invention.
FIG. 3 is a diagram of the connection relationship of the tritium trap device of the molten salt cooled nuclear reactor in the system of the molten salt cooled nuclear reactor.
Detailed Description
The present invention will be described in further detail with reference to the accompanying drawings.
As shown in fig. 1 and fig. 3, the tritium trapping device for a molten salt cooled nuclear reactor of the invention comprises a primary molten salt pipeline 4, a secondary working medium pipeline 1, a heat pipe 2 and a tritium scavenging system 3; the primary side molten salt pipeline 1 is communicated with a core of the molten salt cooling nuclear reactor, and primary side molten salt in the primary side molten salt pipeline 1 is molten salt flowing through the core of the molten salt cooling nuclear reactor; a gap is reserved between the primary side fused salt pipeline 1 and the secondary side working medium pipeline 4, a heat pipe evaporation section 2-1 of the heat pipe 2 is inserted into fused salt of the primary side fused salt pipeline 1, a heat pipe heat insulation section 2-2 is positioned in the gap of the primary side, a heat pipe condensation section 2-3 is inserted into a secondary side working medium of the secondary side working medium pipeline 4, and the primary side fused salt pipeline 1 and the secondary side working medium pipeline 4 realize heat exchange through the heat pipe 2; the tritium purging device 3 is used for purging tritium gas penetrating into the primary side molten salt and the secondary side gap to the tritium collecting device.
As shown in fig. 3, the primary side working medium is molten salt flowing through the reactor core of the nuclear reactor, the secondary side working medium is a secondary circuit coolant of the molten salt cooled nuclear reactor, and the primary side working medium and the secondary side working medium are arranged in a concurrent flow or a countercurrent flow.
As shown in fig. 3, the gap between the primary and secondary side pipes is purged by a tritium purge device 3, and the tritium gas penetrating into the gap in the primary side molten salt is purged to a tritium collection device.
As shown in fig. 1, the outer layer of the evaporation section 2-1 of the heat pipe inserted into the primary molten salt of the primary molten salt pipeline 1 is coated with metal tungsten, so as to significantly reduce the amount of tritium in the primary molten salt permeating into the heat pipe.
As shown in fig. 1, the primary molten salt pipeline 1 is made of a conventional high-temperature alloy, which has a higher tritium permeability than tungsten, so that tritium gas in the primary molten salt can permeate into gaps between pipe walls.
As shown in fig. 2, as a preferred embodiment of the present invention, the heat pipes are arranged in a staggered manner on the primary and secondary sides to enhance the heat exchange on the primary and secondary sides.
To better illustrate the present design, the working principle is now described.
Primary side molten salt from a reactor core of the molten salt cooling nuclear reactor flushes the heat pipe evaporation section 2-1 from left to right through the main pump, heat is transferred to the heat pipe 2, and a heat pipe working medium is evaporated; the secondary side working medium scours the heat pipe condensation section 2-3 from right to left, the heat pipe working medium steam flows to the heat pipe condensation section 2-3 to be condensed, and heat is transferred to the secondary side working medium; tritium gas enters the middle gap from the primary fused salt through the pipe wall of the primary fused salt pipeline 1, the tritium scavenging device 3 blows gas to bring the tritium gas to the tritium collecting device, and the secondary working medium flows to the steam generator.
Claims (6)
1. A molten salt cooling nuclear reactor tritium trapping device is characterized in that: the device comprises a primary side molten salt pipeline (1), a secondary side working medium pipeline (4), a heat pipe (2) and a tritium scavenging device (3); the primary side molten salt pipeline (1) is communicated with a core of the molten salt cooling nuclear reactor, and primary side molten salt in the primary side molten salt pipeline (1) is molten salt flowing through the core of the molten salt cooling nuclear reactor; a gap is reserved between the primary side fused salt pipeline (1) and the secondary side working medium pipeline (4), a heat pipe evaporation section (2-1) of the heat pipe (2) is inserted into fused salt of the primary side fused salt pipeline (1), a heat pipe heat insulation section (2-2) is positioned in the gap of the primary side, a heat pipe condensation section (2-3) is inserted into a secondary side working medium of the secondary side working medium pipeline (4), and the primary side fused salt pipeline (1) and the secondary side working medium pipeline (4) realize heat exchange through the heat pipe (2); the tritium purging device (3) is used for purging tritium gas penetrating into the primary side molten salt and the secondary side gap to the tritium collecting device.
2. A molten salt cooled nuclear reactor tritium trap apparatus according to claim 1, characterized in that: the working medium in the secondary side working medium pipeline (4) is a secondary circuit coolant of the molten salt cooling nuclear reactor, and the primary and secondary side working media are arranged in a concurrent flow or countercurrent flow mode.
3. A molten salt cooled nuclear reactor tritium trap apparatus according to claim 1, characterized in that: the outer layer of the evaporation section (2-1) of the heat pipe inserted into the primary side molten salt of the primary side molten salt pipeline (1) is coated with metal tungsten, so that the permeation amount of tritium in the primary side molten salt to the heat pipe is remarkably reduced.
4. A molten salt cooled nuclear reactor tritium trap apparatus according to claim 1, characterized in that: the primary side fused salt pipeline (1-1) adopts high-temperature alloy which has high tritium permeability compared with tungsten so that tritium gas in the primary side fused salt can permeate into the middle gap through the wall surface.
5. A molten salt cooled nuclear reactor tritium trap apparatus according to claim 1, characterized in that: the heat pipes are arranged in the primary side molten salt pipeline (1) and the secondary side working medium pipeline (4) in a staggered manner.
6. A method of operating a molten salt cooled nuclear reactor tritium trap as claimed in any one of claims 1 to 5, wherein: primary side molten salt from a reactor core of the molten salt cooling nuclear reactor flushes a heat pipe evaporation section (2-1) from left to right through a main pump, heat is transferred to a heat pipe (2), and a heat pipe working medium is evaporated; the secondary side working medium scours the heat pipe condensation section (2-3) from right to left, the heat pipe working medium steam flows to the heat pipe condensation section (2-3) to be condensed, and heat is transferred to the secondary side working medium; tritium gas permeates into a middle gap from primary side molten salt through the pipe wall of the primary side molten salt pipeline (1), and gas is blown into the tritium scavenging device (3) to bring the tritium gas to the tritium collecting device.
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| CN202010045262.5A CN111243766A (en) | 2020-01-16 | 2020-01-16 | Tritium trapping device of molten salt cooling nuclear reactor and working method |
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| CN202010045262.5A CN111243766A (en) | 2020-01-16 | 2020-01-16 | Tritium trapping device of molten salt cooling nuclear reactor and working method |
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Citations (6)
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| US20160019993A1 (en) * | 2014-07-17 | 2016-01-21 | Ut-Battelle, Llc | Apparatus and Method for Stripping Tritium from Molten Salt |
| CN107469628A (en) * | 2017-09-21 | 2017-12-15 | 中国科学院上海应用物理研究所 | The device and method of gaseous state tritium and its isotope in a kind of removal fused salt |
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| US20180374588A1 (en) * | 2017-06-16 | 2018-12-27 | Muons, Inc. | Method and apparatus for producing radioisotopes using fractional distillation |
| CN109509563A (en) * | 2018-11-13 | 2019-03-22 | 西安交通大学 | A kind of cooling high temperature nuclear reactor reactor core of small-sized villiaumite |
| CN109522510A (en) * | 2018-11-19 | 2019-03-26 | 西安交通大学 | A kind of molten salt reactor tritium transport property coupling calculation |
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2020
- 2020-01-16 CN CN202010045262.5A patent/CN111243766A/en active Pending
Patent Citations (6)
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| US20160019993A1 (en) * | 2014-07-17 | 2016-01-21 | Ut-Battelle, Llc | Apparatus and Method for Stripping Tritium from Molten Salt |
| US20180374588A1 (en) * | 2017-06-16 | 2018-12-27 | Muons, Inc. | Method and apparatus for producing radioisotopes using fractional distillation |
| CN107469628A (en) * | 2017-09-21 | 2017-12-15 | 中国科学院上海应用物理研究所 | The device and method of gaseous state tritium and its isotope in a kind of removal fused salt |
| CN108417277A (en) * | 2017-12-25 | 2018-08-17 | 中国科学院上海应用物理研究所 | A kind of reator body system and villaumite shut-down system |
| CN109509563A (en) * | 2018-11-13 | 2019-03-22 | 西安交通大学 | A kind of cooling high temperature nuclear reactor reactor core of small-sized villiaumite |
| CN109522510A (en) * | 2018-11-19 | 2019-03-26 | 西安交通大学 | A kind of molten salt reactor tritium transport property coupling calculation |
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| BAHMAN ZOHURI, STEPHEN LAM, AND CHARLES FORSBERG: "Heat-Pipe Heat Exchangers for Salt-Cooled Fission and Fusion Reactors to Avoid Salt Freezing and Control Tritium: A Review", 《NUCLEAR TECHNOLOGY》 * |
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Application publication date: 20200605 |