CN107710333A - Radioisotopic method is produced using heavy water type nuclear power station - Google Patents
Radioisotopic method is produced using heavy water type nuclear power station Download PDFInfo
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- CN107710333A CN107710333A CN201680033989.3A CN201680033989A CN107710333A CN 107710333 A CN107710333 A CN 107710333A CN 201680033989 A CN201680033989 A CN 201680033989A CN 107710333 A CN107710333 A CN 107710333A
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- Prior art keywords
- heavy water
- reactor
- guiding tube
- target
- bulb
- Prior art date
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- XLYOFNOQVPJJNP-ZSJDYOACSA-N Heavy water Chemical compound [2H]O[2H] XLYOFNOQVPJJNP-ZSJDYOACSA-N 0.000 title claims abstract description 154
- 238000000034 method Methods 0.000 title claims abstract description 27
- 230000007246 mechanism Effects 0.000 claims abstract description 24
- 239000000446 fuel Substances 0.000 claims description 31
- 239000002826 coolant Substances 0.000 claims description 17
- 230000006698 induction Effects 0.000 claims description 16
- 230000005855 radiation Effects 0.000 claims description 7
- 238000006243 chemical reaction Methods 0.000 claims description 6
- 230000004048 modification Effects 0.000 claims description 4
- 238000012986 modification Methods 0.000 claims description 4
- 230000002285 radioactive effect Effects 0.000 claims description 4
- QCWXUUIWCKQGHC-UHFFFAOYSA-N Zirconium Chemical group [Zr] QCWXUUIWCKQGHC-UHFFFAOYSA-N 0.000 claims 1
- 229910052726 zirconium Inorganic materials 0.000 claims 1
- 230000004907 flux Effects 0.000 description 23
- 238000004519 manufacturing process Methods 0.000 description 9
- ZOKXTWBITQBERF-AKLPVKDBSA-N Molybdenum Mo-99 Chemical compound [99Mo] ZOKXTWBITQBERF-AKLPVKDBSA-N 0.000 description 7
- 230000005540 biological transmission Effects 0.000 description 6
- 238000011160 research Methods 0.000 description 6
- 239000011324 bead Substances 0.000 description 5
- 238000001514 detection method Methods 0.000 description 5
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 5
- 238000001816 cooling Methods 0.000 description 4
- 239000007788 liquid Substances 0.000 description 4
- 229910052770 Uranium Inorganic materials 0.000 description 3
- XAGFODPZIPBFFR-UHFFFAOYSA-N aluminium Chemical compound [Al] XAGFODPZIPBFFR-UHFFFAOYSA-N 0.000 description 3
- 229910052782 aluminium Inorganic materials 0.000 description 3
- 230000033228 biological regulation Effects 0.000 description 3
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 description 3
- 238000010521 absorption reaction Methods 0.000 description 2
- 230000032683 aging Effects 0.000 description 2
- OYLGJCQECKOTOL-UHFFFAOYSA-L barium fluoride Chemical compound [F-].[F-].[Ba+2] OYLGJCQECKOTOL-UHFFFAOYSA-L 0.000 description 2
- 229910001632 barium fluoride Inorganic materials 0.000 description 2
- 230000008859 change Effects 0.000 description 2
- 238000013461 design Methods 0.000 description 2
- 239000012530 fluid Substances 0.000 description 2
- 238000007789 sealing Methods 0.000 description 2
- 239000002915 spent fuel radioactive waste Substances 0.000 description 2
- YZCKVEUIGOORGS-OUBTZVSYSA-N Deuterium Chemical compound [2H] YZCKVEUIGOORGS-OUBTZVSYSA-N 0.000 description 1
- 229910000831 Steel Inorganic materials 0.000 description 1
- 229910001093 Zr alloy Inorganic materials 0.000 description 1
- 238000005299 abrasion Methods 0.000 description 1
- 230000008901 benefit Effects 0.000 description 1
- 230000015572 biosynthetic process Effects 0.000 description 1
- 238000009835 boiling Methods 0.000 description 1
- 230000003139 buffering effect Effects 0.000 description 1
- 239000000498 cooling water Substances 0.000 description 1
- 238000005260 corrosion Methods 0.000 description 1
- 230000007797 corrosion Effects 0.000 description 1
- 229910052805 deuterium Inorganic materials 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 230000005484 gravity Effects 0.000 description 1
- 238000010438 heat treatment Methods 0.000 description 1
- 238000001802 infusion Methods 0.000 description 1
- 230000002687 intercalation Effects 0.000 description 1
- 238000009830 intercalation Methods 0.000 description 1
- 230000001678 irradiating effect Effects 0.000 description 1
- 229950009740 molybdenum mo-99 Drugs 0.000 description 1
- 238000012544 monitoring process Methods 0.000 description 1
- 244000144985 peep Species 0.000 description 1
- 230000000149 penetrating effect Effects 0.000 description 1
- 230000009257 reactivity Effects 0.000 description 1
- 230000001105 regulatory effect Effects 0.000 description 1
- 239000000523 sample Substances 0.000 description 1
- 239000007787 solid Substances 0.000 description 1
- 229910001220 stainless steel Inorganic materials 0.000 description 1
- 239000010935 stainless steel Substances 0.000 description 1
- 239000010959 steel Substances 0.000 description 1
- 239000013077 target material Substances 0.000 description 1
- -1 uranium deuteride Chemical compound 0.000 description 1
- 239000002699 waste material Substances 0.000 description 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C23/00—Adaptations of reactors to facilitate experimentation or irradiation
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21G—CONVERSION OF CHEMICAL ELEMENTS; RADIOACTIVE SOURCES
- G21G1/00—Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation or particle bombardment, e.g. producing radioactive isotopes
- G21G1/02—Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation or particle bombardment, e.g. producing radioactive isotopes in nuclear reactors
-
- 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
Abstract
The invention provides one kind radioisotopic method is produced using heavy water type nuclear power station.Methods described includes inserting target (37) in the heavy water moderator of the heavy water reactor by the guiding tube (30) in the port (55) in the reactive mechanisms deck (45) of the heavy water reactor.The heavy water reactor operation to the target to irradiate, so as to which the target is converted into radio isotope.Methods described also includes taking out from the moderator of the heavy water reactor radio isotope via the reactive mechanisms deck.Present invention also offers a kind of heavy water nuclear reactor.
Description
Technical field
The disclosure relates generally to a kind of radio isotope, is produced more particularly, to one kind using heavy water type nuclear power station
The method of radioactive isotope power supply.
Background technology
Radio isotope is used for the various fields such as industry, research, agricultural and medical science.Generally, artificial radioactivity is same
Position element is by making suitable target material be exposed to neutron flux appropriate time in cyclotron or in research nuclear reactor
To produce.The irradiation place of research nuclear reactor is very expensive, and because reactor is closed because of aging, so in future
It can become more rare.Molybdenum -99 (Mo-99) is particularly useful in medical field, and is desired for Mo-99 and other radioactivity
Isotope provides the production site substituted.
EP 2093773A2 show radionuclide generation system, wherein being split in business light-water nuclear reactor by core
Become and produce the short-term radio isotope with medical applications.In the pressure boundary of reactor vessel and main coolant loop
The interior existing gauge pipe for being generally used for accommodating neutron detector is used to the generation radioactivity during normal operation in reactor
Nucleic.Spherical Target is linearly pushed into gauge pipe and linearly removed by Spherical Target from gauge pipe.When the reactor core of reactor
Axial Neutron flux distribution when being considered as known or computable, the reactor core of reactor is at least determined based on the parameter
In target optimum position and open-assembly time amount.Drive gear system, actuator or air impeller can be used for mobile and protect
Hold target.Automatic flow control system maintains the synchronism between all subsystems of the bead measuring system.
From the B2 of US 8842798 with the A1 of US 2013/0170927 it is also known that similar system, for example, it specific is recorded
Based on the existing TIP (moveable in-core detector (traversing in the pressure boundary of light-water reactor container
Incore probe)) embodiments (passage and conveying mechanism of target) of several drive systems of system.In special time with spy
Determine such as stop valve or gate valve part can be used in combination when mode distributes target.The A1 of US 2013/0315361 propose a kind of use
In the valve of sealing gauge pipe base portion.Alternative route is set to remain to existing TIP in the pressure boundary of reactor vessel
The entrance of pipe index (indexer), or the alternative route provided to desired destination.In the A1 of US 2013/0177126
In, holding component is shown, it includes such as fork limiting structure, for optionally stopping that irradiation target is moved through passage
And/or into/out gauge pipe.
The solid spherical of bead measuring system is popped one's head in (" gas particularly with the use of gas-pressurized driving pneumatic small-ball
Dynamic bead ") be incorporated into through the gauge pipe of the reactor core of reactor in measure the neutron of the heap in-core of some business nuclear reactors
Flux density.For example, this bead measuring system is disclosed in US patents No.3263081.
The content of the invention
Provide one kind and produce radioisotopic method using heavy water reactor or heavy water type nuclear power station.Base of the present invention
In following discovery：Its main purpose is/by be produce electric power existing or future nuclear power station can be used for producing radioactivity it is same
Position element.Preferred embodiment uses Canadian uranium deuteride (CANDU：CANada Deuterium Uranium) type pressurized heavy water is anti-
Answer heap.
Methods described includes will by the guiding tube in the port in the reactive mechanisms deck of the heavy water reactor
Target is inserted in the heavy water moderator of the heavy water reactor.The heavy water reactor is run to be irradiated to the target, so as to
The target is converted into radio isotope.Methods described also includes via the reactive mechanisms deck that the radioactivity is same
Position element takes out.
Additionally provide a kind of heavy water nuclear reactor.The heavy water nuclear reactor includes the reactor core involucrum of reactor；Described
The multiple pressure pipes for including fuel bundle in the reactor core involucrum of reactor, reactor core bag of the heavy water Main Coolant from the reactor
The flows outside of shell includes what is separated with the multiple pressure pipe by the multiple pressure pipe, the reactor core involucrum of the reactor
Heavy water moderator；With the reactive mechanisms deck above the reactor core involucrum of the reactor, the reactive mechanisms deck
Including extending through its port, the port accommodates the guiding tube including target, the guiding tube be configured to when be exposed to by
The target is converted into radio isotope during the radiation that the fuel bundle is sent.The heavy water nuclear reactor can include pressure
Solenoid reactor, the pressure pipe reactor are the pressure boundaries of main coolant loop, and the main coolant loop is in the heap
Having in core includes multiple pressure pipes (also referred to as fuel channel) of fuel bundle.Heavy water Main Coolant flows from Heat transmission branch pipe
Pass through pressure pipe.Reactor calandria includes heavy water moderator, and positioned at the outside of the pressure boundary of main coolant loop.Core
Power station also includes the reactive mechanisms deck above the reactor core involucrum of pressure pipe reactor.The reactive mechanisms deck bag
Include and extend through port therein.The port accommodates the new guiding tube including target, and the guiding tube is configured to when exposure
The target is changed into radio isotope when the radiation sent by the fuel bundle.New guiding tube formed with relatively low
The pressure boundary of moderator system under temperature and pressure, rather than formed with elevated pressures and at a temperature of include fuel rod
The pressure boundary of the main coolant loop of beam.
Brief description of the drawings
Below, the present invention will be described referring to the drawings, wherein：
Fig. 1 shows according to embodiments of the present invention by the typical CANDU6 irradiated to target reaction pile components.
Fig. 2 shows the local section side view of the reactor calandria (calandria) of the heavy water reactor shown in Fig. 1
Figure.
Fig. 3 shows the typical CANDU6 of the heavy water reactor shown in Fig. 1 top view, and it illustrates the position of peep-hole
Put, and schematically show reactive control device on the reactive mechanisms deck above reactor calandria
Position in (reactivity mechanisms deck).
Fig. 4 shows the typical CANDU6 of the heavy water reactor shown in Fig. 1 end-view, and it illustrates the position of peep-hole
Put.
Fig. 5 shows the typical CANDU6 of the heavy water reactor shown in Fig. 1 reactive mechanisms deck, and it illustrates peep
The position of window.
Fig. 6 shows the typical CANDU6 of the heavy water reactor shown in Fig. 1 end-view, and it illustrates wherein according to this
The position for the peep-hole that the new radio isotope production guiding tube of invention embodiment suitably positions.
Fig. 7 shows new radio isotope guiding tube assembly and the part thereof of enlarged drawing shown in Fig. 6.
Fig. 8 shows distributor, bulb and the pressure boundary pipe of the new radio isotope guiding tube assembly shown in Fig. 7
Details section.
Fig. 9 shows the sectional drawing of the bottom of the new radio isotope production guiding tube assembly shown in Fig. 7.
Figure 10 shows the typical netron-flux density of CANDU reactor cores.
Figure 11 shows the neutron-capture cross section in Mo-98, and it illustrates formant.
Embodiment
Heavy water type nuclear power station (particularly CANDU pressurized heavy water reactors) can activate the non-uranium base that can capture neutron
There is very high thermal neutron flux and high-caliber epithermal neutron flux in the resonance of the wide scope of target.This neutron absorption shows
Work reduces for acquisition radio isotope and caused waste, while the substantial amounts of radiation such as production Mo-99 of also having the ability
Property isotope, with substitute using retired aging research reactor production.
Several researchs have been carried out, these researchs are conceived to modification and are included in main coolant loop principal pressure pipe
CANDU fuel bundles, with including the irradiation target for allowing to produce isotope.This be directed to use with loading and unloading fuel machine online inserting and
Fetch amended fuel bundle so that reactor has operational risk, and reason is that handling fuel functional limits operating unit,
And the risk of the emergency shut-down caused by accident may be increased.The use of amended fuel bundle also requires
Nuclear power station design aspect makes great change, to handle amended fuel bundle and by fuel bundle from spentnuclear fuel storehouse (Spent
Fuel Bay) in take out to extract isotope.
Present disclose provides a kind of method inserted target and in heavy water type nuclear power station and fetched target, this method can be in core
Completed during running without producing significant impact to operational risk in power station.Guiding tube, the moderator are provided with moderator
Region be located at the outside of main coolant loop principal pressure pipe, separated with fuel bundle.
Fig. 1 shows typical CANDU6 reactions pile component according to embodiments of the present invention.In this embodiment, its
It is to be used for CANDU pressurized heavy water reactors, but in other embodiments, it can be another type of heavy water reaction
Heap.Typical CANDU6 reactions pile component has single pressure boundary, and it is classified as the main cooling circuit comprising fuel, made
For the moderator for slowing down neutron of autonomous system isolated with main cooling circuit and radiation shield is provided and supports master to cool back
The end profile shielding of road fuel channel.Main cooling circuit part shown in Fig. 1 is by fuel channel end fitting 10 and Heat transmission branch pipe
(feeder pipe) 11 is formed.Moderator system unit shown in Fig. 1 is reactor calandria 1, reactor calandria shell
2nd, reactor calandria tube 3, entrance-outlet filter 8, moderator export 12, moderator inlet tube 13, lead to moderator top
Pipeline 18, moderator discharge pipe 20, rupture disk 21, reactive control device ozzle 22 and the reactor calandria of portion's expansion tank
Side pipe plate 29.End profile shielding includes the pre-buried ring 4 of end profile shielding, fuel manipulator crane side pipe plate 5, end profile shielding rasterization pipeline 6, end profile shielding
Cooling tube 7 and steel ball shielding 9.Penetrating the port (port) of moderator system includes noting for Fluxes detection device and liquid
Enter device 14, ionisation chamber 15, peep-hole 23, shutdown bar device 24, regulation bar device 25, control absorption bar device 26, fluid zone
The port of domain control device 27 and Vertical Flux detection device 28.The component is contained in the concrete with barrier-type barricade 19
In reactor block wall 17, and protect whole component from the influence of seismic events using earthquake limiter 16.
The reactor core involucrum of reactor shown in Fig. 1 has the shape of the reactor calandria 1 defined by horizontal cylindrical shell 2
Formula.Multiple reactor calandria tubes 3 are contained in the inside of reactor calandria shell 2.Heavy water moderator is via in reactor
Defined between the inner surface of calandria shell 2, the outer surface of reactor calandria tube 3 and reactor calandria side pipe plate 29
Pipeline 12,13 flow into and flow out in the volume in reactor calandria 1.Main coolant loop comprising fuel bundle exists
Be physically it is independent and from Heat transmission branch pipe 11 flow through fuel channel end fitting 10, along pressure pipe (also referred to as
Fuel channel comprising fuel bundle) flow downward, flow out and flow into relative from relative fuel channel end fitting 10
In Heat transmission branch pipe 11.Schematic partial sectional view such as Fig. 2 is schematically shown, heavy water moderator is contained in reactor comb appearance
The volume defined between the inner surface of device shell 2, the outer surface of reactor calandria tube 3 and reactor calandria side pipe plate 29
Inside.Each reactor calandria tube 3, which is surrounded in it, to be accommodated the pressure pipes of multiple fuel bundles 51 (also referred to as fuel leads to
Road) 44.Reactor calandria tube 3 is together with the annular space 48 filled with gas kept by garter spring locating ring 46 in pressure pipe
Buffering is provided between 44 and moderator heavy water, the heavy water Main Coolant being thus heated in pressure pipe 44 will not make heavy water moderator
Boiling.Main Coolant is from the cold leg feed pressure pipe 44 by Heat transmission branch pipe 11 to the main coolant loop of end fitting 10
And flow to receive the heat from fuel bundle 51, then flowed out from the pressure pipe 44 at relative end fitting 10,
And the heat pipe section of main coolant loop is flowed out to from Heat transmission branch pipe 11, to flow through the steam hair for being located at heat pipe section downstream
Raw device.Closing cock 52 is located on each end fitting 10 to allow online handling fuel.
Referring back to Fig. 1, its further comprise for the moderator inlet tube 13 from moderator major loop supply cooling water,
For the moderator water of heating to be fed back into moderator major loop with the moderator outlet 12 that is cooled down and for releasing
Put the pressure release pipe 20 of the pressure in reactor calandria shell 2.Multiple horizontal-extending water of neutron flux detection device 14
Level land extends through reactor calandria 1, is led to monitoring the neutron in reactor operation present invention heap calandria 1
Amount.Extend vertically through reactor core is multiple reactive control devices therein.
Fig. 3 is to schematically show reactive control device in the reactive machine above reactor calandria 1
The top view of position in structure deck 45.Reactive mechanisms deck, which is maintained at, to be extended below reactive mechanisms deck and is passed through from top
Wear all reactive control devices of reactor calandria 1.From figure 1 it appears that reactive control device is included vertically
The neutron flux detection device 28 of extension, liquid regions control device 27, regulation bar device 25, control absorb bar device 26 and anti-
Heap shutdown bar device 24 is answered, they, which are required for, is available and can be operated during operation.Except reactive control device
Outside, reactive mechanisms deck 45 also includes extending through its two peep-holes 23.First peep-hole 49 (that is, examine by high flux
Look into port) high flux regional alignment with the reactor core of reactor, and the second peep-hole 50 (that is, small throughput checks port) with it is anti-
Answer the small throughput regional alignment of the reactor core of heap.During inspecting periodically being exposed to for reactor is monitored using peep-hole 49,50
Corrosion and abrasion at two regions of the neutron flux of varying level.
Fig. 4 is to show positioning of the reactive mechanisms deck 45 above reactor calandria 1 and the position of peep-hole 23
Cross-section side view.Existing sleeve pipe 53 is located in the appropriate position of peep-hole, is provided completely newly in reactor with allowing to work as
Guiding tube is inserted to monitor neutron flux during the initial start of reactor during fuel.Aluminum guiding tube is typically provided with to neutron
Flux has very highly sensitive barium fluoride detector.Once reactor start-up and neutron is detected by barium fluoride detector
Flux, then remove aluminum guiding tube.Permanent damage can be caused during normal operation by staying in aluminum guiding tube.In initial start
Afterwards, radio isotope production guiding tube can be inserted using peep-hole.
Fig. 5 shows the position on reactive mechanisms deck 45 and peep-hole 23 and its filled with shutdown bar device 24, regulating rod
Put 25, control and absorb the relative position of bar device 26, liquid regions control device 27 and Vertical Flux detection device 28.
Fig. 6 is show positioning of the reactive mechanisms deck above reactor calandria and the position of peep-hole 23 disconnected
Surface side view.Existing sleeve pipe 53 is located in the appropriate position of peep-hole to allow to insert guiding tube, and is inserted in illustrating
New radio isotope production guiding tube 30.
Fig. 7 shows the whole radio isotope for including distributor 36, dividing plate (bulkhead) 31 and upper flange 32
Produce the component of guiding tube 30.Top is the firm hollow tube 33 for having interfix bearing sleeve 34.In this embodiment, bottom
Portion is equipped with multiple holes 35 radially extended, to allow moderator water that guiding tube 30 is flowed into and flowed out along pressure boundary pipe 39
(Fig. 8 and Fig. 9), but if using the induction system substituted, then bottom can be firm pressure boundary pipe and/or can be with shape
Managed into pressure boundary.Bottom has guidance tip 40 to allow to be positioned in reactor calandria.The length of guiding tube 30 is big
About 46 feet (14 meters), a diameter of 3.5 inches (9 centimetres).
Fig. 8 shows a section together with the distributor 36 shown in Fig. 7 in the component of pressure boundary pipe 39.Distributor 36
Including forming its innermost diameter to the pressure boundary pipe 39 of its outermost radial surface of the bulb 38 on surface and formation.Distributor 36 provides
Target 37 is caused to input the energy output it in bulb 38 and from bulb via pneumatically actuated 41,42 from induction system
Power.Left side view shows top and the distributor 36 of pressure boundary pipe 39, and right side view shows pressure boundary pipe 39
Bottom.Target 37 is conveyed via the induction system proposed in US patents No.3,263,081 by distributor 36.By pushing down on
The Pneumatic pressure 41 of moving-target 37, target 37 drop in port 55 and bulb 38 on distributor 36, until they hit spherical stop
Move device 54 and stop at the bottom of bulb 38.There is spherical retainer 54 gap to allow Pneumatic pressure easy in the vertical direction
Ground passes through spherical retainer 54.After the irradiation phase, managed by another port 56 on distributor 36 along pressure boundary
39 are downwardly applied to Pneumatic pressure 42, make Pneumatic pressure reverse, and then the Pneumatic pressure returns to bulb 38, passed through bottom-up
Spherical retainer 54 simultaneously promotes target 37 to pass through bulb 38 to make target push up and be released from distributor 36.Single pressure boundary pipe
39 sealing moderator system pressure borders, and bulb 38 and spherical retainer 54 are accommodated wherein.In this embodiment,
As shown in fig. 7, depending on yield needed for radioisotopic expection, there can be many pressure boundaries in a guiding tube 30
Pipe 39.The diameter of target is nominally 2mm, but can be based on discussed radio isotope and rise to several centimetres.Target 37
External diameter defines the internal diameter of bulb 38 with small gap, to allow target 37 to be easily moved.The external diameter of bulb 38 defines pressure again
The internal diameter of force boundary pipe 39, radial clearance be present between bulb 38 and pressure boundary pipe 39, to allow air in the He of bulb 38
Flowed downward in the axial direction between pressure boundary pipe 39.Therefore, the diameter of target 37 ultimately limit each guiding tube 30
The maximum (reference picture 7) of pressure boundary pipe 39, or guiding tube 30 itself form pressure boundary pipe 39.
Fig. 9 is the sectional drawing of the bottom of radio isotope production guiding tube 30, shows that multiple (is in this example embodiment five
It is individual) pressure boundary pipe 39, each pressure boundary pipe includes bulb 38, and bulb 38 has and corresponding circular pressure boundary pipe 39
The external diameter that internal diameter is sufficiently spaced from.Two in pressure boundary pipe 39 show from outside, and two in the pipe of pressure boundary are with complete
Cross section is shown.5th pressure boundary pipe 39 is shown with local section, the inner section of corresponding bulb 38 is shown, wherein spherical
Retainer 54 supports target 37.The space bar 43 for Aseismic Design is also show, its length along guiding tube 30 is suitably
It is spaced apart.It also show guidance tip 40.
Figure 10 shows the typical netron-flux density of CANDU reactor cores.It can capture the non-of neutron can activate
There is very high thermal neutron flux and high constant epithermal neutron flux in the resonance of the wide scope of uranium base target.
Figure 11 shows the neutron-capture cross section in Mo-98, and it illustrates completely in CANDU pressurized heavy water reactors
Formant in the wide scope of sub- flux.
The target intercalation reaction that the disclosure will be formed by Mo-98 in preferred embodiments by using high flux peep-hole 49
It can be used for producing radioactive isotope power supply (in preferred embodiments, radioactive isotope power supply in heap calandria 1
It is the Mo-99 for medical domain).After initial startup operation whenever, when power station is currently running and radioactivity
When Isotope production guiding tube 30 is in the appropriate position shown in Fig. 6 and Fig. 7, target 37 can be transported to via induction system
Removed in guiding tube 30 and by it from guiding tube 30.In preferred embodiments, guiding tube 30 is formed by zircaloy.Another
In one embodiment, guiding tube 30 can be formed by stainless steel.
Target induction system can also removedly be added to reactive mechanisms deck area to insert target, for example, Mo-98.
In one embodiment, target induction system is US patent No.3, the pneumatic small-ball induction system disclosed in 263,081.The gas
Target 37 is sent into guiding tube 30 by dynamic bead induction system using aerodynamic force via distributor 36, and is being irradiated and be converted into
After Mo-99, it is drawn up irradiating target 37 from guiding tube 30.In an alternate embodiment, target can be dropped to by gravity and be drawn
In conduit 30, and removed upwards from guiding tube 30 by mechanical drive system.The mechanical conveying system is characterised by, mechanical
Drive system includes being used for the valve system being after irradiation discharged to irradiation target in collection vessel.Implement in another replacement
In scheme, induction system can be portable, and can be connected as needed with distributor 36, by using commercially available funnel by target
37 hand feeds are into the port 55 of the bulb 38 of distributor 36.Then, the standard available pneumatic tank with commercially available accessory can be with
It is connected to the port 55 of the bulb 38 of distributor 36 and for conveying gas to be supplied in bulb 38 to ensure that target 37 is complete
It is fully inserted into.After exposure time, on the port 55 for the bulb 38 that the commercially available transport bottle of standard can be connected into distributor 36,
And the standard available pneumatic tank with commercially available accessory can be connected to the port 56 of the pressure boundary pipe 39 of distributor 36.Connect
, commercially available pneumatic tank can be operated, to be sprayed target 37 from bulb 38, mark to be escaped and enter from distributor 36
Accurate commercially available transport bottle.
Advantageously, the target 37 of Mo-98 forms is provided to CANDU pressurized heavy water reactors using high flux peep-hole 49
Allow to make target 37 be exposed to enough radiation in reactor calandria 1, to change into Mo-99 in about 6~12 days.For
For in embodiment, the target 37 of other forms can be provided to other moderator ports and by the induction system of replacement with it
He produces other radio isotopes such as L-177 (Lu-177) time cycle.In preferred embodiments, for target 37
Moderator port is standby port, particularly peep-hole 23,49.In other embodiments, other standby ends can also be used
Mouthful, for example, the flux detector port that is not used by or not including other ports of device (for example, in port shown in Fig. 1
Any one), condition is due to that these ports of some reasons do not accommodate corresponding fluid infusion apparatus 14, ionisation chamber 15, peep-hole
23rd, shutdown bar device 24, regulation bar device 25, control absorb bar device 26, liquid regions control device 27 or Vertical Flux and visited
Survey device 28.As additional advantage, need not be removed using existing peep-hole 23 or other standby ports to provide target 37
Any device frequently used during power station is run, it is same to produce radioactivity without carrying out significant modification to reactor
Position element.
In the foregoing, with reference to specific illustrative embodiment and its example, the present invention is described.It is however, aobvious
And be clear to, can be to this hair in the case of the wider range of the invention illustrated in not departing from appended claims
It is bright to carry out various modifications and changes.Therefore, specification and drawings are considered as illustrative and not restrictive.
Claims (27)
1. a kind of method that radioactive isotope power supply is produced using heavy water reactor, including：
It is anti-that target is inserted by the heavy water by the guiding tube in the port in the reactive mechanisms deck of the heavy water reactor
In the heavy water moderator for answering heap, the heavy water reactor operation is put with being irradiated to the target so as to which the target be converted into
Injectivity isotope；With
The radio isotope is taken out from the heavy water reactor via the reactive mechanisms deck.
2. the method as described in claim 1, in addition to the modification port is with including induction system.
3. method as claimed in claim 2, wherein the induction system is pneumatic conveyer system.
4. method as claimed in claim 3, wherein the radio isotope is taken out from the heavy water reactor to be included
The radio isotope is forced to leave the guiding tube using the pneumatic conveyer system.
5. the method as described in claim 3 or 4, wherein the target is inserted in the heavy water moderator including the use of the gas
Dynamic induction system inserts the target in the guiding tube.
6. the method as any one of claim 3~5, wherein the pneumatic conveyer system is pneumatic small-ball delivery system
System.
7. such as method according to any one of claims 1 to 6, wherein the guiding tube is zirconium matter guiding tube.
8. such as method according to any one of claims 1 to 7, wherein the heavy water reactor is CANDU reactors.
9. method as claimed in claim 8, wherein the CANDU reactors include multiple pressure in it with fuel element
The heavy water Main Coolant of the multiple pressure pipe is managed and flows through, the heavy water moderator separates with the heavy water Main Coolant.
10. such as method according to any one of claims 1 to 9, wherein the port is standby port.
11. method as claimed in claim 10, wherein the standby port is peep-hole.
12. the method as any one of claim 1~11, wherein via the reactive mechanisms deck by the radiation
Property isotope takes out from the heavy water reactor to be carried out during the generating of the heavy water reactor.
13. the method as any one of claim 1~12, wherein the guiding tube is accommodated for receiving the target
At least one bulb.
14. method as claimed in claim 13, wherein the bulb or each bulb have the target answered for support phase in bulb
Spherical retainer, the target is inserted in the heavy water moderator and reacts the radio isotope from the heavy water
At least one of taking-up includes making conveying gas pass through the spherical retainer or each spherical retainer in heap.
15. the method as described in claim 13 or 14, wherein the guiding tube, which is accommodated or formed, surrounds the bulb or each
At least one pressure boundary pipe of bulb, the outer surface of the pressure boundary pipe contact the heavy water moderator.
16. the method as described in claim 13 or 14, wherein the guiding tube accommodates multiple bulbs, in the multiple bulb
Each surrounded by corresponding pressure boundary pipe, the guiding tube includes allowing the heavy water moderator along the multiple
Pressure boundary pipe flows in and out multiple holes of the guiding tube.
17. a kind of heavy water nuclear reactor, including：
The reactor core involucrum of reactor；
The multiple pressure pipes for including fuel bundle in the reactor core involucrum of the reactor, heavy water Main Coolant is from the reaction
The flows outside of the reactor core involucrum of heap is included and the multiple pressure by the multiple pressure pipe, the reactor core involucrum of the reactor
The separated heavy water moderator of solenoid；With
Reactive mechanisms deck above the reactor core involucrum of the reactor, the reactive mechanisms deck include extending through
Its port is crossed, the port accommodates the guiding tube including target, and the guiding tube is configured to when exposed to by the fuel rod
The target is converted into radio isotope during the radiation that beam is sent.
18. heavy water nuclear reactor as claimed in claim 17, in addition to induction system, the induction system be configured for by
The target inserts in the guiding tube and forces the radio isotope to leave the guiding tube.
19. heavy water nuclear reactor as claimed in claim 18, wherein the induction system is pneumatic conveyer system.
20. heavy water nuclear reactor as claimed in claim 19, wherein the pneumatic conveyer system is pneumatic small-ball Load System.
21. the heavy water nuclear reactor as any one of claim 17~20, wherein the heavy water nuclear reactor is CANDU
Type reactor.
22. the heavy water nuclear reactor as any one of claim 17~21, wherein the port is standby port.
23. heavy water nuclear reactor as claimed in claim 22, wherein the standby port is peep-hole.
24. the heavy water nuclear reactor as any one of claim 17~23, wherein the guiding tube is accommodated for connecing
Receive at least one bulb of the target.
25. heavy water nuclear reactor as claimed in claim 24, wherein the bulb or each bulb have answers ball for support phase
The spherical retainer of target in pipe, the target is inserted in the heavy water moderator and by the radio isotope from described
At least one of taking-up includes making conveying gas pass through the spherical retainer or each spherical retainer in heavy water nuclear reactor.
26. the heavy water nuclear reactor as described in claim 24 or 25, wherein the guiding tube is accommodated or formed described in encirclement
At least one pressure boundary of bulb or each bulb is managed, and the outer surface of the pressure boundary pipe contacts the heavy water moderator.
27. the heavy water nuclear reactor as described in claim 24 or 25, wherein the guiding tube accommodates multiple bulbs, it is described more
Each in individual bulb is surrounded by corresponding pressure boundary pipe, the guiding tube include allowing the heavy water moderator along
The multiple pressure boundary pipe flows in and out multiple holes of the guiding tube.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202310644462.6A CN117079853A (en) | 2015-06-22 | 2016-06-16 | Method for producing radioisotope using heavy water nuclear power station |
Applications Claiming Priority (3)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CA2895622A CA2895622A1 (en) | 2015-06-22 | 2015-06-22 | Method of producing radioisotopes using a heavy water type nuclear power plant |
| CA2,895,622 | 2015-06-22 | ||
| PCT/EP2016/063880 WO2016207054A1 (en) | 2015-06-22 | 2016-06-16 | Method of producing radioisotopes using a heavy water type nuclear power plant |
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| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202310644462.6A Division CN117079853A (en) | 2015-06-22 | 2016-06-16 | Method for producing radioisotope using heavy water nuclear power station |
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| CN107710333A true CN107710333A (en) | 2018-02-16 |
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| CN201680033989.3A Pending CN107710333A (en) | 2015-06-22 | 2016-06-16 | Radioisotopic method is produced using heavy water type nuclear power station |
| CN202310644462.6A Pending CN117079853A (en) | 2015-06-22 | 2016-06-16 | Method for producing radioisotope using heavy water nuclear power station |
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| Application Number | Title | Priority Date | Filing Date |
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| CN202310644462.6A Pending CN117079853A (en) | 2015-06-22 | 2016-06-16 | Method for producing radioisotope using heavy water nuclear power station |
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| Country | Link |
|---|---|
| CN (2) | CN107710333A (en) |
| AR (1) | AR105081A1 (en) |
| CA (2) | CA2895622A1 (en) |
| RO (1) | RO132736B1 (en) |
| WO (1) | WO2016207054A1 (en) |
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| CN108962417A (en) * | 2018-06-22 | 2018-12-07 | 中核核电运行管理有限公司 | heavy water reactor cobalt isotope production method |
| CN109884687A (en) * | 2019-02-19 | 2019-06-14 | 中国科学院上海应用物理研究所 | Sample delivery device and delivery method for high-temperature reactor |
| CN112334994A (en) * | 2018-07-31 | 2021-02-05 | 法马通有限公司 | Cartridge and use of a cartridge in a method for producing radioisotopes |
| CN112789689A (en) * | 2018-08-27 | 2021-05-11 | Bwxt同位素技术集团有限公司 | Target irradiation system for producing radioisotopes |
| CN113096836A (en) * | 2021-03-30 | 2021-07-09 | 陕西卫峰核电子有限公司 | Neutron detection system and installation method thereof |
| CN113351017A (en) * | 2021-06-23 | 2021-09-07 | 中国核动力研究设计院 | Extraction device for gaseous iodine in loop for producing iodine-125 |
| CN114758810A (en) * | 2022-04-19 | 2022-07-15 | 中核核电运行管理有限公司 | Device and method for producing isotope by using heavy water reactor detector pore passage on-line irradiation |
| CN114822901A (en) * | 2022-04-19 | 2022-07-29 | 中核核电运行管理有限公司 | Online irradiation device of heavy water reactor observation hole |
| CN115064295A (en) * | 2022-06-07 | 2022-09-16 | 上海核工程研究设计院有限公司 | System and method for producing radioactive isotope by using heavy water reactor nuclear power station |
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| US11286172B2 (en) | 2017-02-24 | 2022-03-29 | BWXT Isotope Technology Group, Inc. | Metal-molybdate and method for making the same |
| CN111066095A (en) | 2017-08-02 | 2020-04-24 | Bwxt同位素技术集团有限公司 | Fuel channel isotope irradiation at full operating power |
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| CN108962417A (en) * | 2018-06-22 | 2018-12-07 | 中核核电运行管理有限公司 | heavy water reactor cobalt isotope production method |
| CN112334994A (en) * | 2018-07-31 | 2021-02-05 | 法马通有限公司 | Cartridge and use of a cartridge in a method for producing radioisotopes |
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| CN112789689A (en) * | 2018-08-27 | 2021-05-11 | Bwxt同位素技术集团有限公司 | Target irradiation system for producing radioisotopes |
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| CN109884687A (en) * | 2019-02-19 | 2019-06-14 | 中国科学院上海应用物理研究所 | Sample delivery device and delivery method for high-temperature reactor |
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| CN113096836B (en) * | 2021-03-30 | 2022-03-01 | 陕西卫峰核电子有限公司 | Neutron detection system and installation method thereof |
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| CN114822901A (en) * | 2022-04-19 | 2022-07-29 | 中核核电运行管理有限公司 | Online irradiation device of heavy water reactor observation hole |
| CN114758810B (en) * | 2022-04-19 | 2023-01-24 | 中核核电运行管理有限公司 | Device and method for producing isotope by using heavy water reactor detector pore passage on-line irradiation |
| CN114758810A (en) * | 2022-04-19 | 2022-07-15 | 中核核电运行管理有限公司 | Device and method for producing isotope by using heavy water reactor detector pore passage on-line irradiation |
| CN115064295A (en) * | 2022-06-07 | 2022-09-16 | 上海核工程研究设计院有限公司 | System and method for producing radioactive isotope by using heavy water reactor nuclear power station |
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Also Published As
| Publication number | Publication date |
|---|---|
| WO2016207054A1 (en) | 2016-12-29 |
| CN117079853A (en) | 2023-11-17 |
| CA2986976A1 (en) | 2016-12-29 |
| AR105081A1 (en) | 2017-09-06 |
| CA2986976C (en) | 2019-04-23 |
| RO132736B1 (en) | 2021-04-29 |
| CA2895622A1 (en) | 2016-06-16 |
| RO132736A2 (en) | 2018-07-30 |
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