CN213300890U - Detachable glass condenser pipe - Google Patents
Detachable glass condenser pipe Download PDFInfo
- Publication number
- CN213300890U CN213300890U CN202020693776.7U CN202020693776U CN213300890U CN 213300890 U CN213300890 U CN 213300890U CN 202020693776 U CN202020693776 U CN 202020693776U CN 213300890 U CN213300890 U CN 213300890U
- Authority
- CN
- China
- Prior art keywords
- tube
- shell
- pass
- glass sealing
- detachable
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Active
Links
Images
Landscapes
- Vaporization, Distillation, Condensation, Sublimation, And Cold Traps (AREA)
Abstract
The utility model discloses a detachable glass condenser tube, which comprises a shell pass and a tube pass, wherein the shell pass is in a bilateral symmetry open shape, the bottom of the shell pass is provided with a ground glass sealing interface, and clean cold water flows in the shell pass; the tube side can be inserted into the shell side from an opening above the shell side, and the lower part of the tube side is provided with a frosted glass sealing joint; the ground glass sealing joint can be inserted into the ground glass sealing interface to realize sealing; radioactive vapor flows inside the frosted glass sealing interface and the tube side. The utility model provides a detachable condenser pipe can reduce the secondary radioactive waste volume.
Description
Technical Field
The utility model relates to a radioactive liquid waste treatment field, concretely relates to detachable glass condenser pipe.
Background
A large amount of radioactive wastewater is generated in the processes of nuclear fuel production, nuclear power plant operation, isotope production and use, nuclear facility decommissioning and the like, and evaporation concentration is a common radioactive wastewater treatment process. The basic principle of the method is that the waste water entering an evaporator is heated to boiling by steam or an electric heater, the water in the waste water is evaporated into steam, and the steam is condensed into water after cooling, most of radioactive nuclides in the waste water have no volatility except for tritium, iodine and other few nuclides.
The small-sized radioactive waste water evaporation and concentration device usually adopts glass materials as an evaporation container and a condenser, the existing small-sized glass condenser is designed in an integral manner, namely, a tube pass with radioactive steam and a shell pass with flowing clean cold water are integrated, and the small-sized radioactive waste water evaporation and concentration device can not meet the radioactive waste minimization principle after being used as radioactive waste treatment.
Disclosure of Invention
To the defect that exists among the prior art, the utility model aims to provide a detachable glass condenser pipe accomplishes behind set waste water treatment task at evaporation plant and condenser pipe, can dismantle the condenser pipe, and the part is regarded as radioactive waste and is handled, is favorable to reducing the secondary waste volume, realizes the minimizing of radioactive waste.
In order to achieve the above object, the utility model adopts the following technical scheme:
a detachable condenser tube comprises a shell pass and a tube pass, wherein the shell pass is in a bilaterally symmetrical open shape, a ground glass sealing interface is arranged at the bottom of the shell pass, and clean cold water flows in the shell pass;
the tube side can be inserted into the shell side from an opening above the shell side, and the lower part of the tube side is provided with a frosted glass sealing joint;
the ground glass sealing joint can be inserted into the ground glass sealing interface to realize sealing;
radioactive vapor flows inside the tube side.
Furthermore, a cooling water inlet and a cooling water outlet are arranged on the shell pass, and the inner diameter of the cooling water outlet is larger than that of the cooling water inlet.
Further, a steam inlet and a steam outlet are arranged on the tube side.
Further, the tube side is in a spiral shape, a spherical shape or a straight tube type.
The beneficial effects of the utility model reside in that: when the evaporation device and the condenser pipe complete the set wastewater treatment task and need to be treated as radioactive waste, the pipe pass can be extracted from the shell pass, and only the pipe pass is treated as the radioactive waste, and the shell pass is treated as common waste or recycled. The method is beneficial to reducing the amount of secondary waste and realizing the minimization of radioactive waste.
Drawings
FIG. 1 is a schematic diagram of a shell-side structure of a condenser tube;
FIG. 2 is a schematic diagram of a tube pass structure of a condenser tube;
FIG. 3 is a schematic view of the overall structure of the condenser tube;
wherein: 1-cooling water inlet; 2-a cooling water outlet; 3-frosted glass sealing interface; 4-a steam inlet; 5-a steam outlet; 6-frosted glass sealing joint.
Detailed Description
The present invention will be described in further detail with reference to the drawings and the following detailed description.
Example 1
A detachable condenser tube comprises a shell pass and a tube pass, wherein the shell pass is provided with a cooling water inlet 1 and a cooling water outlet 2, the inner diameter of the cooling water outlet is slightly larger than that of the cooling water inlet, the shell pass is in a bilateral symmetry open shape, the bottom of the shell pass is provided with a ground glass sealing interface 3, and clean cold water flows in the shell pass;
radioactive steam flows in the tube side, a steam inlet 4 and a steam outlet 5 are arranged on the tube side, and a frosted glass sealing joint 6 is arranged at the lower part of the tube side. The tube pass is helical. The tube side can be inserted into the shell side from an opening above the shell side, and a ground glass sealing joint 6 is inserted into the ground glass sealing interface 3;
the detachable condenser pipe is arranged in a small radioactive wastewater comprehensive treatment device and is used for radioactive wastewater treatment tasks in a radioactive laboratory decommissioning project, the total number of the condenser pipes is two, the total weight of a single set of the condenser pipes is 1200g, after 300 liters of radioactive wastewater is treated together, the decommissioning project is finished, and the wastewater treatment device needs to be treated so as to be convenient to transport. After the condenser pipe is disassembled, 1000g of radioactive contaminated glass is produced in total, and compared with a non-detachable condenser pipe (2400 g of radioactive contaminated glass), the radioactive waste is reduced by 58%.
It will be apparent to those skilled in the art that various changes and modifications may be made without departing from the spirit and scope of the invention. Thus, if such modifications and variations of the present invention fall within the scope of the claims and their equivalent technologies, the present invention is also intended to include such modifications and variations.
Claims (4)
1. A detachable glass condenser tube is characterized by comprising a shell pass and a tube pass, wherein the shell pass is in a bilateral symmetry open shape, the bottom of the shell pass is provided with a ground glass sealing interface, and clean cold water flows in the shell pass;
the tube side can be inserted into the shell side from an opening above the shell side, and the lower part of the tube side is provided with a frosted glass sealing joint;
the ground glass sealing joint can be inserted into the ground glass sealing interface to realize sealing;
radioactive vapor flows inside the tube side.
2. The detachable glass condenser tube of claim 1, wherein the shell side is provided with a cooling water inlet and a cooling water outlet, and the inner diameter of the cooling water outlet is larger than that of the cooling water inlet.
3. The detachable glass condenser of claim 1, wherein the tube side is provided with a steam inlet and a steam outlet.
4. The detachable glass condenser tube of claim 1, wherein the tube pass is helical, spherical or straight.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CN202020693776.7U CN213300890U (en) | 2020-04-30 | 2020-04-30 | Detachable glass condenser pipe |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CN202020693776.7U CN213300890U (en) | 2020-04-30 | 2020-04-30 | Detachable glass condenser pipe |
Publications (1)
Publication Number | Publication Date |
---|---|
CN213300890U true CN213300890U (en) | 2021-05-28 |
Family
ID=75982693
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
CN202020693776.7U Active CN213300890U (en) | 2020-04-30 | 2020-04-30 | Detachable glass condenser pipe |
Country Status (1)
Country | Link |
---|---|
CN (1) | CN213300890U (en) |
-
2020
- 2020-04-30 CN CN202020693776.7U patent/CN213300890U/en active Active
Similar Documents
Publication | Publication Date | Title |
---|---|---|
CN206680295U (en) | A kind of field water purification device | |
US20110305309A1 (en) | Methods and apparatus for selective gaseous extraction of molybdenum-99 and other fission product radioisotopes | |
CN109147982B (en) | Nuclear power plant low-emission wastewater MVC evaporation process and device thereof | |
CN109701296A (en) | Corrosion-resistant more working method supercritical carbon dioxide extracting systems | |
CN213300890U (en) | Detachable glass condenser pipe | |
Boldyrev et al. | The Russian ARGUS solution reactor HEU-LEU conversion: LEU fuel preparation, loading and first criticality | |
CN103762005B (en) | A kind of distillation device for nuclear industry concentrate decrement | |
CN207986899U (en) | Use for laboratory sewage-treatment plant | |
CN203950562U (en) | A kind of vaporising device of processing radioactive liquid waste | |
RU126185U1 (en) | INSTALLATION FOR CLEANING LIQUID RADIOACTIVE WASTE FROM TRITIUM | |
CN206697244U (en) | Uranium contamination data analysis device is repaired in reduction | |
CN206580585U (en) | Simple water purification device | |
CN204066758U (en) | A kind of dissolver processing spent fuel element | |
CN206424601U (en) | A kind of evaporator internal washing system of nuclear power station | |
TWI537981B (en) | Method of disposing radioactive waste of molybdenum-99 | |
CN114111436A (en) | String piece formula heat exchanger with pipeline scale removal structure of touching frost | |
CN105651587A (en) | Environment-friendly digestion reflux device | |
US20210147271A1 (en) | System and method of rain water collection and purification | |
CN111681797A (en) | Method for treating radioactive wastewater of retired field of small nuclear facility | |
CN111681798B (en) | Small-size nuclear facility field radioactivity effluent treatment plant that retires | |
CN106091719A (en) | Steam condensed water waste heat reclamation set in cryogenic distillation apparatus | |
CN106186483A (en) | High chlorine high salt liquid waste treatment system | |
CN205252561U (en) | Control by temperature change vapor concentration evaporimeter | |
TW201911332A (en) | Apparatus of Treating Radioactive Waste of Molybdenum-99 | |
RU150156U1 (en) | INSTALLATION FOR CLEANING LIQUID RADIOACTIVE WASTE FROM TRITIUM |
Legal Events
Date | Code | Title | Description |
---|---|---|---|
GR01 | Patent grant | ||
GR01 | Patent grant |