GB2510798A - Process for drying radioactive waste containing water - Google Patents
Process for drying radioactive waste containing water Download PDFInfo
- Publication number
- GB2510798A GB2510798A GB1218845.4A GB201218845A GB2510798A GB 2510798 A GB2510798 A GB 2510798A GB 201218845 A GB201218845 A GB 201218845A GB 2510798 A GB2510798 A GB 2510798A
- Authority
- GB
- United Kingdom
- Prior art keywords
- container
- water
- gas stream
- process according
- heater
- 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.)
- Granted
Links
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 title claims abstract description 58
- 238000000034 method Methods 0.000 title claims abstract description 42
- 238000001035 drying Methods 0.000 title claims abstract description 18
- 239000002901 radioactive waste Substances 0.000 title claims abstract description 17
- 239000002699 waste material Substances 0.000 claims abstract description 28
- 238000010438 heat treatment Methods 0.000 claims abstract description 18
- 238000005259 measurement Methods 0.000 claims description 11
- 238000001704 evaporation Methods 0.000 claims description 10
- 230000008020 evaporation Effects 0.000 claims description 10
- 239000012530 fluid Substances 0.000 claims description 7
- 238000004891 communication Methods 0.000 claims description 2
- 239000007789 gas Substances 0.000 description 12
- 238000012546 transfer Methods 0.000 description 3
- 238000001291 vacuum drying Methods 0.000 description 3
- 238000001914 filtration Methods 0.000 description 2
- 231100001261 hazardous Toxicity 0.000 description 2
- 238000009413 insulation Methods 0.000 description 2
- 239000007788 liquid Substances 0.000 description 2
- 230000002285 radioactive effect Effects 0.000 description 2
- 238000013022 venting Methods 0.000 description 2
- 230000004071 biological effect Effects 0.000 description 1
- 238000009835 boiling Methods 0.000 description 1
- 239000000470 constituent Substances 0.000 description 1
- 238000005260 corrosion Methods 0.000 description 1
- 230000007797 corrosion Effects 0.000 description 1
- 230000007423 decrease Effects 0.000 description 1
- 238000013461 design Methods 0.000 description 1
- 238000000605 extraction Methods 0.000 description 1
- 230000001939 inductive effect Effects 0.000 description 1
- 230000007774 longterm Effects 0.000 description 1
- 239000002184 metal Substances 0.000 description 1
- 239000002245 particle Substances 0.000 description 1
- 238000012545 processing Methods 0.000 description 1
- 238000005086 pumping Methods 0.000 description 1
- 230000005855 radiation Effects 0.000 description 1
- 229920005989 resin Polymers 0.000 description 1
- 239000011347 resin Substances 0.000 description 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/04—Treating liquids
- G21F9/06—Processing
- G21F9/08—Processing by evaporation; by distillation
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/42—Reprocessing of irradiated fuel
- G21C19/44—Reprocessing of irradiated fuel of irradiated solid fuel
- G21C19/46—Aqueous processes, e.g. by using organic extraction means, including the regeneration of these means
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F5/00—Transportable or portable shielded containers
- G21F5/002—Containers for fluid radioactive wastes
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/28—Treating solids
- G21F9/30—Processing
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F5/00—Transportable or portable shielded containers
- G21F5/005—Containers for solid radioactive wastes, e.g. for ultimate disposal
-
- 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
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Plasma & Fusion (AREA)
- Drying Of Solid Materials (AREA)
Abstract
A process for drying radioactive waste containing water comprises a) heating the radioactive waste in a sealed container 102 using a heater 104 to evaporate the water; b) entraining water which evaporates from the waste into a gas stream 108 and removing this from the container 102; c) condensing the gas stream and removing the condensed water from this stream; and d) returning the gas stream back to sealed container 102. The container is heated to a temperature between 50°C - 95°C. The container is not depressurised. By keeping the temperature below 95°C and the system unpressurized, the present invention provides a process for drying radioactive waste which reduces the levels of created airborne particulates from the waste and which is more energy efficient than existing waste drying systems.
Description
PROCESS FOR DRYING RADIOACTIVE WASTE CONTAINING WATER
The present invention relates to a prooess for drying radioactive waste containing water.
Sludges, resins, metallic components and other waste materials arising from radioactive processing are typically stored in tanks and silos; they tend to be covered with water in order to attenuate the emission of radioactive particles. When these wastes are recovered for long term storage in metallic containments, one process known in the art is that of drying the waste. This fulfils a number of objectives. It reduces the overall volume of waste to be stored. It decreases the likelihood that the moisture content will corrode the containment over time, potentially leading to a breach of mechanical integrity. It prevents evolution of hazardous gases generated from internal corrosion of the waste material and it reduces biological activity which can also generate hazardous gas emissions.
One known process is vacuum drying, where the containment holding the waste is heated, the pressure is reduced and evaporation of water content occurs at a temperature below 100°C. The water is then condensed and collected in a condensate vessel. These systems are virtually closed loop apart from the final filtering of the output from the vacuum pump. This is to try to mitigate loss of containment.
A difficulty experienced with the vacuum drying process is that of maintaining vapour evolution. As the water vapour evolves, the energy required to evolve it is carried away in the vapour and therefore the temperature of the residual mass of waste can fall. If the rate of energy input to the waste is less than the energy output in the vapour, the process will stall until equilibrium is regained. Further, as the waste dries it tends to shrink away from the containment and therefore energy transfer through the containment into the waste via conduction varies throughout the process. Furthermore energy transfer by convection does not occur in a vacuum and heat radiation at temperatures below 100°C is minimal, so the process tends to be unpredictable and inefficient.
These problems are solved in the second type of drying process: atmospheric pressure drying. In this process, the containment holding the waste is heated to a temperature above 100°C and evaporation cf the water content by boiling ocours at atmospheric pressure.
A problem associated with this process, as with the vacuum drying process, is that very vigorous evolution of water vapour ocours, whioh creates airborne particulates.
This blocks and contaminates pipe-work and In extreme cases it can be deposited in the ccndensate tank. Both these events are undesirable.
Accordingly, the present invention provides a process for drying radioactive waste according to claim 1.
By keeping the temperature below 95°C and the system unpressurized, the present invention provides a process for drying radioactive waste which reduces the levels of created airborne particulates from the waste and which is more energy efficient than existing waste drying systems. Also, by returning the gas stream to the seaied container, the system is closed. In the prior art, the systems are not fully closed, so that some gas is vented to atmosphere.
This vented gas must be scrubbed prior to venting.
The heater may, for example, be an oil, water bath, or jacket type heater. However, preferably the heater is an electric heater. The benefit of an electric heater is that there is no need for a heat transfer medium which can be contaminated by the waste. The heater could be a resistive or inductive heater. However, preferably, the heater is an infrared heater and the part of the container which is configured to be heated is metallic. The use of an infrared heater with a metallic container provides an efficient heating regime to the container as only the metal from the container is heated.
The step of returning the gas stream back to the sealed container may also include pre-heating the gas stream prior to its entry back into the sealed container. Pre-heating the gas stream prior to its entry into the container promotes more efficient removal of water vapour and provides for direct heating of the waste material. This can be conveniently done if the gas stream is preheated by passing through a tortuous path in a region which receives heat emanated from the container. The waste can then be heated from below by the heater and from above by the hot gas stream. This provides uniform heating.
Preferably, the region is defined between the container and an insulating housing.
The sealed container may be mounted on a load cell, and the process configured to include the steps of; measuring the mass of the container over time using the load cell; and calculating the rate of water evaporation from the container based on this mass measurement.
The process may also include the steps of; collecting the condensed water from the gas stream in a tank which is mounted on a load cell; measuring the mass of the tank over time using the load cell; and calculating the rate of water collection in the tank based on this mass measurement.
The process may also include the steps of measuring the humidity of the air stream between the water entraining and water condensing steps using a humidity monitor, and calculating the rate of water evaporation from the container based on these humidity measurements.
By being able to measure any of the rate of water collection or evaporation or the humidity of the gas stream between the water entraining and water condensing steps, these measurements can be used to alter the amount of heat being delivered by the heater, and/or can be used to give an indication as to the remaining time until the water from the waste is fully evaporated.
The invention will now be described in detail, by way of example only, with reference to the accompanying drawings, in which: Figure 1 shows a schematic of a radioactive waste drying system.
The system therein shown is split into four general sections. The first section is a heating section 100. In this section 100, there is a container 102 holding radioactive waste, an infrared heater 104, a return air line 106, and an exit air line 108. The container 102 may he located on one or more load cells 110.
The container 102, and parts of the return and exit air lines 106; 108, are located in an insulating housing 112, wherein a region 114 is defined between the container and the housing. This region 114 may be around 100mm wide. The return line 106 then forms a tortuous path through this region 114.
The second section is the condensing section 200. This section 200 comprises a condenser 202 with air entry 204, air exit 206, condenser fluid entry 208, and condenser fluid exit 210 lines. The fluid entry and exit lines 208; 210 lead from/to a conventional condenser pumping system 212 which is known in the art.
The third section is the water collection section 300.
This section 300 comprises a water knock out apparatus 302, which is connected to one or more water tanks 304. The knock out apparatus 302 may be any conventional water separating apparatus, for example, a cyclonic type water separator.
The fourth section is the air control section 400. This section 400 comprises a dryer 402 and a filter 404 which are in fluid communication with an air venting / intake system 406 which are conventional in the art.
Connecting each of the four sections 100-400 together is ducting which, as appropriate, may be insulated. This insulation is shown in Figure 1 as component 51. The insulation 51 may also be present in the fluid entry and exit lines 208;210 of the condenser.
Shown throughout Figure 1 are various sensors / indicators. The key to these sensors is as follows (with nn being a number between 01 and 25) TInn -Temperature indicator FInn -Flow indicator WInn -Weight (mass) indicator RHnn -Relative humidity sensor Although not shown, pressure sensing devices may also be present in parts of the system. The purpose of all the above sensors is to measure flow characteristics of the air stream at various points around the process whose measurements can be used to determine the amount of power that should be delivered from the heater and confirm the progress towards the end point of the drying cycle.
In the unlikely event of a breach occurring, all four of the sections 100; 200; 300; 400 may be contained in an enclosure 60, whose interior atmosphere is controlled by an extraction fan 61 and an associated filtration unit (not shown) In use of the system, the heater 104 is configured to heat the container 102 storing the waste.
As the container 102 heats up, heat is transferred both to the waste and to the region 114 surrounding the container. Heat transferred to the waste causes water therein to evaporate into vapour form.
To collect this vapour, cool dry air is directed towards the container 102 through the air return line 106 by a fan 50. As the air passes along the tortuous path of the air return line, the constituents of the region 114 cause the cool air inside the air return line to heat up prior to entry into the container 102. When the resultant warmer air enters the container, water vapour which evaporates from the waste becomes entrained in this air.
The moist warm air passes out from the container 102 through the air exit line 108 towards the air entry line 204 of the condenser 200. As the moist air passes through the condenser, the condenser fluid condenses the vapour entrained in the air flow into liquid form. This liquid is then removed from the air flow via the water knock out apparatus 302, in this case shown in Figure 1 as a cyolonic separator, and collected in the tank 304.
The cool and dry air which passes out from the water knock out apparatus 302 is then driven back towards the fan for reoirculation to the container 102.
Preferably the air system is closed, however in some embodiments the air exiting from the water knock out apparatus 302 may be partially supplemented by air introduced via the control section 400 in order to maintain atmospheric pressure. This introduced air is initially filtered and dried by the filter 404 and dryer 402 respectively, and is driven by the fan 50 to the container 102.
A load cell is located underneath any of the container 102 or the collection tank 304 to monitor their mass. By recording the mass of either component over time, the rate of evaporation of water from the waste can be calculated.
This information can then be used to alter the amount of heat being delivered by the heater, and/or alternatively can be used to give an indication as to the remaining time until the water from the waste is fully evaporated.
To ensure the pre-heating in the air return line 108 is as effective as possible, a recirculation fan 52 may be used to assist the convection heating regime from the container 102 to the region 114.
Figure 1 also shows the possibility for connecting additional heating sections 100'; 100''; 100''', which are eguivalent in design to heating section 100, in a parallel type arrangement, to the overall heating system. In this operation the condensing section 200, the water collection section 300, and the air control section 400 remain unchanged. They may as appropriate, however, be sized for additional capacity.
The container 102 of the or each heating section 100 can be of any size. Once its size is known, the remaining parts of the or each heating section, for instance the insulated housing 114; the heater 104; the return air line 106; the exit air line 108; and the load cells 110, can be appropriately sized to fit around it. In this way, the system previously described can be used on any existing tank of undried radioactive waste.
Claims (10)
- -10 -Claims 1. A process for drying radioactive waste containing water, wherein the process comprises: heating the radioactive waste in a sealed container using a heater to evaporate the water; entraining water which evaporates from the waste into a gas stream and removing this from the container; condensing the gas stream and removing the condensed water from this stream; and returning the gas stream back to sealed container; wherein the container is heated to a temperature between 50°C -95°C; and wherein the container is not depressurised.
- 2. A process according to any preceding claim, wherein the heater is an electric heater.
- 3. A process according to claim 2, wherein the heater is an infrared heater and the part of the container which is configured to be heated is metallic.
- 4. The process according to any preceding claim, wherein the step of returning the gas stream back to the sealed container includes pre-heating the gas stream prior to its entry back into the sealed container.
- 5. The process according to claim 4, wherein the gas stream is preheated by passing through a tortuous path in a region which receives heat emanated from the container.-11 -
- 6. The process according to claim 5, wherein the region is defined between the container and an insulating housing.
- 7. The process according to any preceding claim, wherein the sealed container is mounted on a load cell and the process further includes the steps of; measuring the mass of the container over time using the load cell; and calculating the rate of water evaporation from the container based on this mass measurement.
- 8. The process according to any preceding claim, further including the steps of; collecting the condensed water from the gas stream in a tank which is mounted on a load cell; measuring the mass of the tank over time using the load cell; and calculating the rate of water collection in the tank based on this mass measurement.
- 9. The process according to any preceding claim, further including the steps of; measuring the humidity of the air stream between the water entraining and water condensing steps using a humidity monitor; and calculating the rate of water evaporation from the container based on these mass flow rate and humidity measurements.
- 10. A process for drying radioactive waste as herein before described and with reference to the accompanying drawings.AMENDMENTS TO THE CLAIMS HAVE BEEN FILED AS FOLLOWS: Claims 1. A process for drying radioactive waste containing water, wherein the process comprises: heating the radioactive waste in a sealed container using a heater to evaporate the water; entraining water which evaporates from the waste into a gas stream and removing this from the container; condensing the gas stream and removing the condensed water from this stream; and returning the gas stream back to sealed container; wherein the container is heated to a temperature between 5000 -95°C; and wherein the container is not depressurised; and wherein the heater is not in fluid communication with the gas stream. r2. A process according to any preceding claim, wherein the heater is an electric heater.3. A process according to claim 2, wherein the heater is an infrared heater and the part of the container which is configured to be heated is metallic.4. The process according to any preceding claim, wherein the step of returning the gas stream back to the sealed container includes pre-heating the gas stream prior to its entry back into the sealed container.5. The process according to claim 4, wherein the gas stream is preheated by passing through a tortuous path in a region which receives heat emanated from the container.6. The process according to claim 5, wherein the region is defined between the container and an insulating housing.7. The process according to any preceding claim, wherein the sealed container is mounted on a load cell and the process further includes the steps of; measuring the mass of the container over time using the load cell; and calculating the rate of water evaporation from the container based on this mass measurement.8. The process according to any preceding claim, further C') including the steps of; collecting the condensed water from the gas stream in a r tank which is mounted on a load cell; r measuring the mass of the tank over time unng the load cc, an caloulating the rate of water collection in the tank based on this mass measurement.9. The prooess a000rding to any preceding claim, further including the steps of; measuring the humidity of the air stream between the water entraining and water condensing steps using a humidity monitor; and calculating the rate of water evaporation from the container based on these mass flow rate and humidity measurements.10. A process for drying radioactive waste as herein before described and with reference to the accompanying drawings.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| GB1218845.4A GB2510798B (en) | 2012-10-19 | 2012-10-19 | Process for drying radioactive waste containing water |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| GB1218845.4A GB2510798B (en) | 2012-10-19 | 2012-10-19 | Process for drying radioactive waste containing water |
Publications (3)
| Publication Number | Publication Date |
|---|---|
| GB201218845D0 GB201218845D0 (en) | 2012-12-05 |
| GB2510798A true GB2510798A (en) | 2014-08-20 |
| GB2510798B GB2510798B (en) | 2016-10-26 |
Family
ID=47359179
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| GB1218845.4A Active GB2510798B (en) | 2012-10-19 | 2012-10-19 | Process for drying radioactive waste containing water |
Country Status (1)
| Country | Link |
|---|---|
| GB (1) | GB2510798B (en) |
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104299667A (en) * | 2014-09-18 | 2015-01-21 | 中国核动力研究设计院 | Movable radioactive waste water far infrared treatment device |
| CN104502577A (en) * | 2015-01-04 | 2015-04-08 | 上海核工程研究设计院 | Test bed of resin transfer technology and test method of test bed |
| GB2575518A (en) * | 2018-07-11 | 2020-01-15 | Edwards Vacuum Llc | Monitoring system and method |
Families Citing this family (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN108062990B (en) * | 2018-01-11 | 2024-06-07 | 航天晨光股份有限公司 | Radioactive waste liquid crystallization drying system and method thereof |
| CN112509723B (en) * | 2020-11-12 | 2024-04-12 | 中国核电工程有限公司 | Radioactive mud treatment method and system |
Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS6080795A (en) * | 1983-10-12 | 1985-05-08 | 株式会社日立製作所 | Drying treating method of radioactive waste |
| JPS6274401A (en) * | 1985-09-30 | 1987-04-06 | Toshiba Corp | Sea water treatment device |
| WO1995026556A1 (en) * | 1994-03-25 | 1995-10-05 | British Nuclear Fuels Plc | Drying wet radioactive, toxic or other hazardous waste |
| US5613244A (en) * | 1995-09-26 | 1997-03-18 | United States Of America | Process for preparing liquid wastes |
| JP2009156625A (en) * | 2007-12-25 | 2009-07-16 | Kobe Steel Ltd | Residual moisture measuring method in drying process of radioactive solid waste, and drying treatment apparatus for radioactive solid waste provided with residual moisture measuring apparatus |
-
2012
- 2012-10-19 GB GB1218845.4A patent/GB2510798B/en active Active
Patent Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS6080795A (en) * | 1983-10-12 | 1985-05-08 | 株式会社日立製作所 | Drying treating method of radioactive waste |
| JPS6274401A (en) * | 1985-09-30 | 1987-04-06 | Toshiba Corp | Sea water treatment device |
| WO1995026556A1 (en) * | 1994-03-25 | 1995-10-05 | British Nuclear Fuels Plc | Drying wet radioactive, toxic or other hazardous waste |
| US5613244A (en) * | 1995-09-26 | 1997-03-18 | United States Of America | Process for preparing liquid wastes |
| JP2009156625A (en) * | 2007-12-25 | 2009-07-16 | Kobe Steel Ltd | Residual moisture measuring method in drying process of radioactive solid waste, and drying treatment apparatus for radioactive solid waste provided with residual moisture measuring apparatus |
Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104299667A (en) * | 2014-09-18 | 2015-01-21 | 中国核动力研究设计院 | Movable radioactive waste water far infrared treatment device |
| CN104502577A (en) * | 2015-01-04 | 2015-04-08 | 上海核工程研究设计院 | Test bed of resin transfer technology and test method of test bed |
| CN104502577B (en) * | 2015-01-04 | 2016-08-24 | 上海核工程研究设计院 | The test-bed of a kind of resin transhipment technique and test method thereof |
| GB2575518A (en) * | 2018-07-11 | 2020-01-15 | Edwards Vacuum Llc | Monitoring system and method |
| US10845229B2 (en) | 2018-07-11 | 2020-11-24 | Edwards Vacuum Llc | Monitoring system and method |
Also Published As
| Publication number | Publication date |
|---|---|
| GB201218845D0 (en) | 2012-12-05 |
| GB2510798B (en) | 2016-10-26 |
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