CN106384616A - Medical isotope production reactor without compensation rod - Google Patents
Medical isotope production reactor without compensation rod Download PDFInfo
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- CN106384616A CN106384616A CN201610905575.7A CN201610905575A CN106384616A CN 106384616 A CN106384616 A CN 106384616A CN 201610905575 A CN201610905575 A CN 201610905575A CN 106384616 A CN106384616 A CN 106384616A
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- G21G—CONVERSION OF CHEMICAL ELEMENTS; RADIOACTIVE SOURCES
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Abstract
The present invention discloses a medical isotope production reactor without a compensation rod and a method of continuously operating to compensate a reserve reaction loss. The reactor does not need a compensation rod, through the increase of the concentration of reactor core solution uranium-235 in operation or a frequent feeding method of maintaining the reactor core solution uranium-235 to be unchanged basically, the reserve reaction of the reactor is improved, the function of the compensation rod is substituted, a reactor core structure and a control system are simplified, and the initial loading amount of uranium is reduced. Since a self concentrated liquid overflow port pipeline is added to a reactor compensation acidication tank, by way of a liquid discharge quantity indication tank, the washing water discharge pipeline of the tank and a feed liquid discharge pipeline connected to a core vessel, after accessing and washing an extraction column, the washing water acesses a storage tank from the washing water discharge pipeline of the extraction column, the washing water pipeline system of an acidication tank composite water washing extraction column is formed, abandoned uranium is recycled, and a large amount of uranium materials is saved.
Description
Technical field
The present invention relates to " homogeneous solution-type reactor " type solution nuclear reactor field.Specifically related to cancel the medical same position of reactor core shim rod
Element produces heap, and how to compensate the method that its standby loss of reactivity maintains the normal operation of reactor core.
Background technology
Up to the present, also do not build up high power " homogeneous solution-type reactor " the type solution core producing for medical-isotope in the world
Reactor.Just in the design, in terms of current data, this engineering is temporary for the 200kW Medical isotope production reactor (MIPS) of the U.S.
Stop.China's 200kW Medical isotope production reactor (MIPR) starts to research and develop for 1997, and elapsed-time standards is very long for various reasons, right
Reactor core control rod species and number quantifier elimination remain in solid fuel component stack.
Research finds:
Solid nuclear fuel component stack, also has five to change greatly after high power operation fuel burn-up in addition to U-235 minimizing:
1) due to the minimizing of U-235, H/U-235 becomes big.General heap selects H/U-235 in optimum state, i.e. this kind of shape
State KeffMaximum.After heap high power operation fuel burn-up, because the minimizing H/U-235 of U-235 becomes big, that is, cross slowing down, KeffReduce.
Solid fuel component stack can not change the H/U-235 after fuel burn-up.
2) after heap high power operation fuel burn-up, U-235 abundance reduces, i.e. identical U-235 amount, and U-238 amount increases, therefore
Reduce Keff.
3) after heap high power operation fuel burn-up, part U-235 fissions into fission product, and the toxicity of fission product reduces
Keff.
4), after heap high power operation fuel burn-up, the fuel assembly due to solid fuel component stack is fixing in reactor core position
, the therefore burnup of each assembly U-235 and fission product amount is all different with flux difference everywhere.
5), after heap high power operation fuel burn-up, produce iodo- 135, then decay into xenon-135.Therefore stack operation when to consider
Poisoning, iodine hole problem.
However, Medical isotope production reactor (MIPR), it is the UO with highly enricked uranium2(NO3)2Solution is the water-soluble of nuclear fuel
Liquid reactor.It is very different with solid nuclear fuel assembly reactor:
1) MIPR can realize H/U-235 minimizing by increasing solution uranium concentration, makes KeffIncrease.
2) MIPR can be cancelled U-235 fission product, made K by the purifying of fuel solutioneffIncrease.
3) MIPR can increase U-235 loading amount by feed supplement, improves U-235 abundance;Suitably many increase U-235 amount maintenances are arrived
K during initial criticalityeff.
4) MIPR has cooling tube so that solution is stired and make muddy evenly due to the mobility of solution, especially reactor core, therefore U-
235 burnup and fission product amount are uniform everywhere.
5) heap high power operation, the xenon-135 that fuel burn-up produces is gas, can run out of, therefore there is not xenon from solution
Malicious problem.
4) and 5) this 2 points critically important.It is the premise that following solution reactor reactor cores calculate.
Because, in solid fuel assembly reactor, the control rod of its reactor core has compensatory reactionBu Changfanying loss, adjusts reaction
Heap power and three kinds of functions of scram.Therefore, in the structure of its control rod, include the compensation of compensatory reactionBu Changfanying loss
Rod, these three structures of safety rod automatically adjusting rod and scram of regulation reactor capability.
The present invention, based on studying it is proposed that cancelling the shim rod in reactor core control rod to solution reaction heap feature, only protects
Stay and automatically adjust rod and safety rod, so that control rod mechanism and core structure is simplified, optimize the method for operation of heap, both solved no
In the case of benefit rod, the compensation to reactor core loss of reactivity, saves the new design of reactor core uranium loading amount again.
Because shim rod is the significant components of reactor core control rod, cancel in the structure design of Medical isotope production reactor and mending
After repaying rod, how to compensate its standby loss of reactivity during stack operation, to substitute the function of shim rod, be present invention research
Core and innovation point.
Content of the invention
It is an object of the invention to:Produce for China's medical-isotope, a kind of medical-isotope life of uncompensated rod is provided
Produce heap, and provide, for this heap, the method compensating excess reactivity loss.
The present invention is uncompensated rod Medical isotope production reactor it is characterised in that:Reactor core control rod mechanism in reactor
Middle cancellation shim rod, only safety rod and automatically adjust rod.
The core of this heap produces structure and mainly includes:
Built-in reactor core feed liquid UO2(NO3)2Flat column type stainless steel core vessel, built-in reactor core feed liquid and its top
Air cavity, reactor core feed liquid radially point inside and outside twoth area, inner region arrangement control rod includes safety rod and automatically adjusts rod, both control rods
The upper lid of conduit and core vessel and sealing welding of going to the bottom, the built-in water of conduit, conduit outer wall and fuel solution UO2(NO3)2Connect
Touch, the safety rod core that is divided in respective conduit, automatically adjust excellent core, move up and down in respective conduit respectively and heap is transported
Row situation is regulated and controled;
Core vessel top cover has gas circuit to connect air cavity with the hydrogen oxygen recombination device outside top cover, and hydrogen oxygen recombination device is provided with pipeline
Sour tank is mended in the Compound Water producing injection;
On mending a horizontal level in sour tank cavity, the funnel type of one opening upwards of setting mends sour overfall, and this overflows
Head piece bottom is connected with the air cavity above reactor core feed liquid by the pipeline with switch valve, the benefit acid loop of composition reactor core;
The bottom of core vessel is provided with feed liquid discharge line and connects extraction column, respectively have one in the bottom of this extraction column
Pipeline, connects storage tank and purification column respectively;Purifying column bottom has pipeline to be connected with storage tank;Storage tank is additionally provided with pipeline even
Connect core vessel bottom, constitute isotope extraction, feed liquid reclaims storage, feed liquid purifies storage and time shut-down system of feed liquid;Its
It is characterised by:
In the sour tank cavity of benefit, positioned at the lower position mending sour overfall, another horizontal opening funnel upwards is set
Type concentrates overfall, and this overfall bottom is by the pipeline connected drainage amount instruction tank with switch valve, lifting rate index pot bottom
There are two bye-passes in portion, and wherein one connects waste water tank by the pipeline with switch valve, and another by with switch valve
Pipeline is connected with the feed liquid discharge line of core vessel, so sequentially from mend sour tank concentrate overfall pipeline, via lifting rate
Index pot, the flushing water discharge line of lifting rate index pot, connect core vessel feed liquid discharge line, enter and rinse extraction
Post, then the flushing water with remaining uranium material is entered storage tank and realize remaining uranium material and return heap, constitute benefit sour tank Compound Water punching
Wash extraction column and reclaim the flushing water flow path system that uranium material dilutes feed liquid, mend in sour tankage size size and its sour tank of benefit and mend sour overfall
Determine with concentrating overfall position and being designed by core.
Set up described lifting rate index pot, use during concentration for doing to reactor core feed liquid.
It should be noted that:Mending sour tank script is to mend acid design for reactor core.Mend the acid water that there are about 1 mole in sour tank,
Reactor core solution initial acidity is about 0.1~0.3 mole.UO as reactor core feed liquid2(NO3)2It is the uranyl nitrtate aqueous solution, its nitre
Acid is decomposed into hydrogen and oxynitrides under fission fragment bombardment, leads to reactor core feed liquid constantly to be lost in nuclear reaction acid, because
This constantly will mend acid to it.And the water in reactor core solution is also decomposed into hydrogen and oxygen under fission fragment bombardment.Hydrogen, carrier of oxygen ease
Go out reactor core liquid level, water is combined into by the hydrogen oxygen recombination device on air circuit, the sour tank of benefit is entered by pipeline.Thus, mend acid
Acid Compound Water in tank, by the pipeline being connected with core vessel air cavity, reflowable enter heap and realize mending to reactor core feed liquid
Acid.
However, another problem occurring is:Because medical-isotope extraction column volume is larger, after extraction isotope thereon
Still remaining has a certain amount of uranium, and these remaining uranium just go out of use as waste material when medical-isotope extracts.The operation of heap
Generally 20 years phase in longevity, annual Operation at full power 200 days, each run 24~48 hours.Therefore, to enter within the phase in stack operation longevity
The medical-isotope extraction process that row is up to 2000~4000 times, extracts every time, and these remaining uranium all go out of use as waste material,
This result in pile up U-235 in the phase in longevity loss amount very big.
Save uranium material consumption for reducing U-235 loss it is necessary to rinse extraction column acid water to reclaim the uranium of remaining
Material.Rinse the water source of extraction column, be the most directly taken from mending the acid Compound Water in sour tank.Therefore, to the design mending sour tank, both
Consider with the acid Compound Water in tank to be that reactor core feed liquid mends acid, the acid Compound Water in consideration tank rinses extraction column again.
So it is necessary to transformation is original mends sour jar structure, adopt in design:Upper and lower two different horizontal planes in the sour tank of benefit
Position, is respectively provided with the funnel type overfall of opening upwards, and at position, the overfall of upper position is to mend sour overfall, at position
The overfall of lower position is to concentrate overfall, and each overfall bottom connects one and passes the pipeline mending sour tank, wherein connects
Logical this pipeline with switch valve mending sour overfall, is connected with the air cavity above core vessel feed liquid, and connection concentrates overflows
The pipeline of head piece, passes the sour tank of benefit by the pipeline connected drainage amount instruction tank with switch valve;The bottom of lifting rate index pot
There are two bye-passes, wherein one pipeline carrying switch valve connects waste water tank, another pipeline carrying switch valve is held with reactor core
The feed liquid discharge line of device is connected, and so mends the acid Compound Water in sour tank, sequentially concentrates overfall pipeline, warp from the sour tank of benefit
By lifting rate index pot, the flushing water discharge line of lifting rate index pot, connect core vessel feed liquid discharge line, enter and rush
Xian's extraction column, then by extraction column flushing water discharge line enter storage tank, constitute flushing water flow path system, by extract doctor
With the feed liquid dilution after isotope.Mend sour tankage size size and its determination is designed by core in the position of two overfalls.
The present invention is uncompensated rod Medical isotope production reactor, continuous service compensatory reactionBu Changfanying loss method:
Can be using raising UO2(NO3)2The concentration of the middle U-235 of solution, to improve excess reactivity KeffSo that fuel
Burnup can persistently be carried out, and to compensate the loss of reactivity of reactor core high power burnup, replaces the function of reactor core shim rod.
Described employing improves reactor core feed liquid UO2(NO3)2The concentration of middle U-235, to improve excess reactivity KeffRefer to:?
After high power operation shutdown, the feed liquid in core vessel enters extraction column by feed liquid discharge line, extracts medical same position
Feed liquid after element enters storage tank by discharge pipe;
And mend the acid Compound Water in sour tank, storage tank is entered by described flushing water flow path system, will store before this
Extract the feed liquid dilution after medical-isotope in storage tank, reducing solution uranium concentration becomes uranium -235 feed liquid of low concentration;
Before next reactor startup, the slightly enriched uranium feed liquid in storage tank is squeezed into core vessel;
After reactor startup, water in reactor core feed liquid, it is decomposed into hydrogen and oxygen, the oxyhydrogen of effusion liquid level under fission fragment bombardment
Body, is combined into water by the pipeline entrance hydrogen oxygen recombination device being connected with air cavity and drains into the sour tank of benefit, when acidity Compound Water in the sour tank of benefit
Liquid level rise to the sour overfall of benefit after, acid Compound Water just can be flowed back by acid Compound Water connect with core vessel air cavity
Pipeline, is back in core vessel and mends acid, and the feed liquid in core vessel is concentrated to previous flushing when starting to mend acid
Uranium -235 concentration of feed liquid during extraction column.
If before certain opens heap, in addition to from the flushing water mending sour tank discharge flushing extraction column, then discharge certain to waste water tank
The water of amount;After opening heap, when the liquid level in the sour tank of benefit rises to the sour overfall of benefit, uranium -235 concentration of core vessel feed liquid is super
Cross concentration during last time operation, reach the uranium concentration of new demand, improve excess reactivity, compensate the reactivity of high power burnup
Loss.
It should be noted that:The Medical isotope production reactor of uncompensated rod, under the uranium loading amount of the core structure determining and determination,
Excess reactivity K during full rod withdrawaleffWith the increase of uranium solution concentration, present and first rise the change declining afterwards.Therefore, open heap first
When, for improving reactor core liquor capacity, heap power is improved with profit, all uranium solution concentration is selected in alap region.So in heap
Concentrating with uranium solution in operation makes uranium -235 concentration improve, and under full rod withdrawal, the excess reactivity of uranium will increase.But can not
Maximum near or above excess reactivity under full rod withdrawal.Therefore, to UO2(NO3)2The adjusting range of U-235 concentration in solution
Have certain limitations.
The present invention is uncompensated rod Medical isotope production reactor, continuous service compensatory reactionBu Changfanying loss method:
Also using maintaining reactor core uranium -235 to be basically unchanged by diligent feed process or can have increased slightly, pile up rated power fortune
During row, automatically adjust rod height and be basically unchanged, the loss of reactivity of reactor core high power burnup can be compensated.
It is noted here that:Solid fuel component stack, refuelling assembly is highly difficult.It is related to want Cooling at reactor shutdown, uncap
(having heap sealing container), refuelling assembly, reactor startup extrapolation criticality again.And Medical isotope production reactor is solution reactor, stop
Heap cool time short it is not necessary to uncap, only can need to be fed by medical-isotope extraction loop.Because each feeding quantity is few,
Extrapolation criticality reactor startup that need not be complicated.But the operation of charging or complicated, should not all feed before reactor startup every time, should open several times
A defective material is added after heap.The reactivity of introducing of once feeding is less than effective delayed neutron fraction.Thus it is not required to extrapolation criticality, only
Need normal reactor startup.
To improve what excess reactivity had certain limitations in view of using improving uranium -235 concentration method, using diligent feed supplement side
Method is operationally also more more complicated, compensates the excess reactivity loss of heap high power burnup, two kinds of measures are reasonably combined can be more
Good.
The present invention compared with prior art, has the advantage that and beneficial effect:
In view of the U-235 amount that heap high power operation causes reduces, and excess reactivity is caused to reduce, can be by raising uranium concentration
To compensate excess reactivity loss or excess reactivity improved by diligent feed supplement.Therefore this heap needs not compensate for rod, heap in-core
Only safety rod and automatically adjust rod.After cancelling reactor core shim rod mechanism, simplify core structure and control system, by improving
UO2(NO3)2U-235 concentration method or maintain the diligent feed process that is basically unchanged of reactor core uranium -235 in solution, the standby of raising heap
Reactivity, replaces the function of reactor core shim rod, and reduces the first loading amount of uranium.
Brief description
Fig. 1 is that the Medical isotope production reactor of the uncompensated rod of the present invention mainly produces structural representation
In figure marks:1 is core vessel;2 is control rod guide tube;3 is reactor core feed liquid;4 is the reactor core above reactor core feed liquid
Container air cavity;5 is hydrogen oxygen recombination device;6 is to mend sour tank;7 is lifting rate index pot;8 is storage tank;9 is extraction column;10 is to purify
Post;11 is waste water tank;A is the feed liquid discharge line of core vessel, and a-1 is the switch valve on pipeline a;B is feed liquid in extraction column
Or flushing water is discharged into the pipeline of storage tank, b-1 is the switch valve on pipeline b;C is that the feed liquid in extraction column enters purification column
Pipeline, c-1 is the switch valve on pipeline c;D is drained into the pipeline of storage tank for the purifying feed liquid in purification column, and d-1 is pipeline d
On switch valve;E is that storage tank is pressed into the pipeline of dilution feed liquid toward core vessel, and e-1 is the switch valve on pipeline e;F is connection
Core vessel air cavity and the gas circuit of hydrogen oxygen recombination device;G is that hydrogen oxygen recombination device enters the pipeline of Compound Water toward the sour tank of benefit;H is connection
The Compound Water of the sour overfall of benefit and core vessel air cavity goes back to the benefit acid tube road of heap, and h-1 is the switch valve mended on the h of acid tube road;I is even
The logical pipeline concentrating overfall connected drainage amount instruction tank, i-1 is the switch valve on pipeline i;J be lifting rate index pot below with
The flushing water discharge line that core vessel feed liquid discharge line connects, j-1 is the switch valve on flushing water discharge line j;K is row
Liquid measure index pot connects the wastewater discharge pipe road of waste water tank, and k-1 is the switch valve on the k of wastewater discharge pipe road.
Specific embodiment
In conjunction with accompanying drawing 1 in detail the present invention is described in detail and cancels reactor core shim rod simplification core structure, build the medical-isotope life of 200kW
Produce the involved core content of heap (MIPR) design.
200kW is uncompensated rod Medical isotope production reactor, its core produce structure mainly include:
Built-in reactor core feed liquid UO2(NO3)2Flat column type stainless steel core vessel 1, built-in reactor core feed liquid 3 and top
Air cavity 4, reactor core feed liquid 3 radially point inside and outside twoth area, inner region arranges control rod 2:Automatically adjust excellent conduit and two peaces including two
Excellent conduit, four conduits of both control rods and the upper lid of core vessel 1 and sealing welding of going to the bottom, the built-in water of conduit, lead entirely
Pipe outer wall and fuel solution UO2(NO3)2Contact, is divided in and automatically adjusts excellent core, safety rod core, respectively each in respective conduit
From conduit in move up and down stack operation situation is regulated and controled;
Core vessel top cover has gas circuit f to connect air cavity 4 with the hydrogen oxygen recombination device 5 outside top cover, and hydrogen oxygen recombination device 5 is provided with
Pipeline g, the Compound Water that hydrogen oxygen recombination device during stack operation is produced enters the sour tank 6 of benefit;
On mending a horizontal level in sour tank 6 cavity, the funnel type of one opening upwards of setting mends sour overfall 6-1,
This overfall bottom, by the benefit acid tube road h with switch valve h-1, is connected with the air cavity 4 above core vessel 1 feed liquid, group
Reactor core is become to mend sour loop;
Mend mend in sour tank 6 cavity sour overfall 6-1 below, the funnel type concentration overflow of opening upwards is separately set
Mouthful 6-2, the bottom of this overfall by the pipeline i connected drainage amount instruction tank 7 with switch valve i-1,
Two bye-passes are arranged at the bottom of lifting rate index pot 7, and wherein one by the wastewater discharge pipe road with switch valve k-1
K connects waste water tank 11,
Another of lifting rate index pot 7 bottom, by the flushing water discharge line j with switch valve j-1, is held with reactor core
The feed liquid discharge line a of device 1 is connected;
So sequentially from mend sour tank concentrate overfall 6-2 pipeline, via lifting rate index pot 7, the rushing of lifting rate index pot
Wash water discharge line j, connect core vessel feed liquid discharge line a, enter and rinse medical-isotope extraction column 9, then rinse
Water enters storage tank 8 by drain line b of this extraction column, constitutes and mends the flushing water that the acid Compound Water of sour tank 6 rinses extraction column 9
Flow path system;
It is provided with the feed liquid discharge line a of belt switch valve a-1 in the bottom of core vessel 1, connect extraction column 9;This extraction
Pipeline b, c of one belt switch valve is respectively arranged at post 9 bottom, and pipeline b connects storage tank 8, and pipeline c connects purification column 10;Purification column bottom
Portion is connected with storage tank 8 by the pipeline d of belt switch valve d-1;The pipeline e that storage tank 8 is additionally provided with belt switch valve e-1 connects heap
The bottom of core container 1, constitutes isotope extraction, feed liquid reclaims storage, feed liquid purifies storage and feed liquid returns shut-down system.
1) with regard to the Medical isotope production reactor of the uncompensated rod of 200kW, after cancelling shim rod, asking of U-235 loading amount can be saved
Topic:
Calculate, below by assessing, the Medical isotope production reactor providing 200kW, (include two groups being provided with 6 groups of control rods
Shim rod, two groups of adjust automatically rods and two groups of safety rods) (include two groups of adjust automatically rods and two groups of safety with 4 groups of control rods
Rod) under, in core vessel fuel solution UO2(NO3)2U-235 concentration be 37.8g/L when, reactor core uranium -235 loading amount calculating
Changing value table.UO in calculating2(NO3)2Solution height between 27~32cm, liquor capacity~100L, the full rod withdrawal of initial full power
Keff is more than 1.005.Under initial excess reactivity remains essentially identical, provide the result of calculation of following table:
As can be seen from the table:The full rod withdrawal Keff of two kinds of control rods quite, and 4 groups of control rods of uncompensated rod, ratio has
The U-235 loading amount of 6 groups of control rods of shim rod decreases 141g.
2) with regard to improving UO2(NO3)2Uranium -235 concentration of solution, improves the problem of excess reactivity:
Research and propose with improving UO2(NO3)2Uranium -235 concentration of solution, improves excess reactivity, can compensate high power
The loss of reactivity of burnup.Concrete measure is:
The flushing water rinsing extraction column 9 carrys out self-complementary acid tank 6, so that the liquid level of benefit acid tank 6 is reduced.Rinse the flushing after extraction column
Water is drained into storage tank 8 and is mixed with feed liquid, reduces solution uranium concentration.
The feed liquid of low concentration uranium in storage tank 8 is squeezed into core vessel 1, the water in reactor core solution 3 after reactor startup is broken in fission
It is decomposed into hydrogen and oxygen, hydrogen or oxygen gas escape heap liquid level, then synthesize water by the hydrogen oxygen recombination device 5 of air circuit f, lead under piece bombardment
Cross pipeline g and drain into the sour tank 6 of benefit, but when the liquid level mending sour tank is less than it and mends sour overfall 6-1, mend the acid Compound Water in sour tank
Can not enter in core vessel 1.When sour tank 6 liquid level of benefit rises to benefit sour overfall 6-1, could be combined mending the acidity in acid tank
Water fills into reactor core.The concentration of reactor core solution uranium -235 is concentrated to uranium concentration when not rinsing extraction column before this by the realization of this stage,
The excess reactivity of loss is made to be compensated.
If before certain opens heap, in addition to from the flushing water mending sour tank 6 discharge flushing extraction column 9, then discharge to waste water tank 11
A certain amount of water.After opening heap when sour tank 6 liquid level of benefit rises to the sour overfall 6-1 of benefit, reactor core uranium -235 concentration being concentrated is
Exceed the previous uranium concentration opening heap, reach new requirement uranium concentration (discharging the water yield to waste water tank to be provided by core design), heap can be made
Excess reactivity be improved.
It is 700mm to reactor core internal diameter, 4 groups of control rods carry out assessing calculation, providing initial uranium -235 concentration is 37.8g/L,
During 39.6g/L and 41.4g/L, calculate full rod withdrawal K listed in TableeffEtc. each parameter value:
Can be seen that from this table:Under uranium -235 loading amount is constant (with gram as measurement unit), increase with uranium -235 concentration
Full rod withdrawal KeffAlso increase.It can compensate the full rod withdrawal K that heap high power burnup causes completelyeffDecline.
3) burnup calculates and provides full rod withdrawal K listed in TableeffShow:Reactor fuel solution concentration method, can compensate high power
The loss of reactivity of burnup:
Calculate from upper table burnup and find out:If the initial value with uranium -235 concentration as 37.8g/L for the heap starts high power operation,
Can run within 200 days, must feed by 200 days.If by 200 days, uranium solution being concentrated into uranium -235 concentration is 39.6g/
L, heap can extend operation to 400 days recyclings.If the concentration again uranium solution being concentrated into uranium -235 when running 400 days is
41.4g/L, the time that heap can extend operation is longer.It is of course possible to shorten uranium solution concentration time, concentrate one within such as every 50 days
Secondary.
Adopt reactor fuel solution concentration method in this explanation stack operation, the concentration of fuel solution uranium -235 can be effectively improved
And its excess reactivity Keff, the loss of reactivity of heap high power burnup can be compensated without shim rod completely, extend the fortune of heap
The row time.
4) diligent feed process can also compensate the loss of reactivity of heap high power burnup:
Maintain reactor core solution uranium -235 to be basically unchanged by diligent feed process or have increased slightly, high power burnup can be compensated
Loss of reactivity.
So that uranium -235 concentration is as 37.8g/L as a example, carries out diligent feed supplement and assess the following table parameter that calculation provides feed supplement in 100 days:
Digital the first row from table, the second row can be seen that:First under the U-235 loading amount of 3920.73g, Operation at full power
100 days, full rod withdrawal KeffIt is reduced to 1.01592.
Now adding uranium -235 solution body accumulated amount that concentration is 37.8g/L is:108.862-105.754=3.108L.
Digital the third line from table, fourth line can be seen that:Just loading amount is 4035.97g to uranium -235, and just loading amount is uranium -238
448.43g.Again when 0 burnup starts to calculate Operation at full power 100 days, it is 4009.96g that uranium -235 is measured and uranium -238 is measured and is
446.88g.And full rod withdrawal KeffReach 1.02167, the initially full rod withdrawal K with the first roweff=1.02073 is suitable.Can be again
Burnup 100 days.
Table numeral fifth line is to the 8th row:It is on the basis of fourth line, uranium -235 is concentrated, 37.8g/L is dense
It is reduced to 39.6g/L.The first row, the second row is burnup 100 days, the third line, fourth line burnup 100 days again, fifth line, the 7th row from
Again can burnup 100 days again from 200 days.
Claims (6)
1. uncompensated rod Medical isotope production reactor it is characterised in that:The reactor core control rod mechanism of reactor cancels and mends
Repay rod, only safety rod and automatically adjust rod.
2., according to the Medical isotope production reactor of rod uncompensated described in claim 1, its core produces structure and mainly includes:
Built-in reactor core feed liquid UO2(NO3)2Flat column type stainless steel core vessel (1), the built-in reactor core feed liquid of container (1) (3)
And its air cavity (4) of top, reactor core feed liquid (3) radially point inside and outside twoth area, inner region arrangement control rod includes safety rod and adjusts with automatic
Section rod, the conduit (2) of both control rods and the upper lid of core vessel (1) and sealing welding of going to the bottom, the built-in water of conduit (2), lead
Pipe (2) outer wall and fuel solution UO2(NO3)2Contact, the safety rod core that is divided in respective conduit (2), automatically adjusts excellent core, point
Do not move up and down stack operation situation is regulated and controled in respective conduit;
Core vessel (1) top cover has gas circuit (f) to connect air cavity (4) with the hydrogen oxygen recombination device (5) outside top cover, hydrogen oxygen recombination device
(5) it is provided with pipeline (g) and sour tank (6) is mended in the Compound Water producing injection;
On mending a horizontal level in sour tank (6) cavity, the funnel type of one opening upwards of setting mends sour overfall (6-1),
By the pipeline (h) with switch valve (h-1), air cavity (4) above is connected with reactor core feed liquid (3) for this overfall bottom, composition
The benefit acid loop of reactor core;
Feed liquid discharge line (a) being provided with switch valve (a-1) in the bottom of core vessel (1) connects extraction column (9), at this
One pipeline (b, c) carrying switch valve (b-1, c-1) is respectively arranged at the bottom of extraction column (9), connects storage tank (8) respectively and purifies
Post (10);The pipeline (d) that purification column (10) bottom is provided with switch valve (d-1) is connected with storage tank (8);Storage tank (8) is also
The pipeline (e) being provided with switch valve (e-1) connects core vessel (1) bottom, constitutes medical-isotope extraction, feed liquid reclaims
Storage, feed liquid purify time shut-down system of storage and feed liquid;It is characterized in that:
Mending in sour tank (6) cavity, positioned at the lower position mending sour overfall (6-1), another horizontal opening is set upwards
Funnel type concentrates overfall (6-2), and this overfall (6-2) bottom is by pipeline (i) the connected drainage amount with switch valve (i-1)
Index pot (7), two bye-passes are arranged at lifting rate index pot (7) bottom, and wherein one by the pipeline (k) with switch valve (k-1)
Connect waste water tank (11), and another feed liquid discharge pipe by the pipeline (j) with switch valve (j-1) and core vessel (1)
Road (a) is connected, and so sequentially refers to from benefit sour tank concentration overfall (6-2) pipeline, via lifting rate index pot (7), lifting rate
Show tank (7) flushing water discharge line (j), connect core vessel feed liquid discharge line (a), enter and rinse extraction column (9) and
Afterwards the flushing water with remaining uranium material is entered the remaining uranium material of storage tank (8) realization and return heap, constitute benefit sour tank (6) acidity and be combined
Water rinses extraction column (9), reclaims uranium material, the flushing water flow path system of dilution feed liquid.
3. according to described in claim 2 uncompensated rod Medical isotope production reactor it is characterised in that:Using raising reactor core feed liquid
UO2(NO3)2The concentration of middle U-235, to improve excess reactivity Keff, compensate the loss of reactivity of reactor core high power burnup.
4. according to described in claim 3 uncompensated rod Medical isotope production reactor it is characterised in that:Described employing improves reactor core
Feed liquid UO2(NO3)2The concentration of middle U-235, to improve excess reactivity Keff, compensate the loss of reactivity of high power burnup, be
Refer to:
After a high power operation shutdown, in core vessel (1), reaction feed liquid (3), is entered by feed liquid discharge line (a) and carries
Take post (9), extract the feed liquid after medical-isotope and storage tank (8) is entered by discharge pipe (b);
And mend the acid Compound Water in sour tank (6), pass through discharge opeing amount instruction via the discharge pipe (i) concentrating overfall (6-2)
Tank (7), flushing water discharge line (j) of lifting rate index pot, connect core vessel feed liquid discharge line (a), enter and rinse
Extraction column (9), then the flushing water with remaining uranium material is entered by storage tank (8) by its flushing water discharge pipe (b), by this
Before be stored in the feed liquid mixed diluting after extracting medical-isotope in storage tank (8), reducing solution uranium concentration becomes low concentration
Uranium -235 feed liquid;
Before next reactor startup, the feed liquid of low concentration uranium inner for storage tank (8) is squeezed into core vessel (1);
After reactor startup, water in reactor core feed liquid (3), it is decomposed into hydrogen and oxygen under fission fragment bombardment, the hydrogen or oxygen gas of effusion liquid level,
Water is combined into by the gas circuit (f) entrance hydrogen oxygen recombination device (5) connecting with air cavity (4) and drains into the sour tank (6) of benefit, when the sour tank (6) of benefit
After the liquid level of interior acidity Compound Water rises to the sour overfall of benefit, acid Compound Water just can be by connecting with core vessel air cavity (4)
Acid Compound Water return line (h), be back in core vessel (1) and mend acid, and when starting to mend acid by core vessel (1)
Interior feed liquid (3) is concentrated to previous uranium -235 concentration not rinsing feed liquid during extraction column, improves excess reactivity, compensates high power
The loss of reactivity of burnup;
If certain is in addition to discharging extraction column flushing water from the sour tank (6) of benefit more a certain amount of to waste water tank (11) discharge before opening heap
Water;After opening heap, when the liquid level in the sour tank (6) of benefit rises to sour overfall (6-1) of benefit, the uranium -235 of core vessel (1) feed liquid
Concentration, has exceeded concentration during previous operation, has reached the uranium concentration of new demand, improve excess reactivity, compensates high power combustion
The loss of reactivity of consumption.
5. according to described in claim 2 uncompensated rod Medical isotope production reactor it is characterised in that:Heap is maintained by diligent feed supplement
Core uranium -235 is basically unchanged or has increased slightly, pile up automatically adjust during rated power operation rod height be basically unchanged, compensate reactor core
The loss of reactivity of high power burnup.
6. according to described in claim 4 and 5 uncompensated rod Medical isotope production reactor it is characterised in that:Can be using raising
Reactor core feed liquid UO2(NO3)2The concentration of middle U-235 is combined with diligent feed supplement, improves heap excess reactivity, compensates heap high power burnup
Loss of reactivity.
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Citations (7)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN1355540A (en) * | 2002-01-08 | 2002-06-26 | 中国核动力研究设计院 | Low-temp nuclear reactor with dead fuel for nuclear power station |
RU2255389C1 (en) * | 2004-04-27 | 2005-06-27 | Горбунов Евгений Константинович | Uranium-graphite reactor irradiating device for irradiating materials |
RU2004121204A (en) * | 2004-07-13 | 2006-01-10 | Дмитрий Юрьевич Чувилин (RU) | METHOD FOR PRODUCING RADIOISOTOPE OF STRONTS-89 |
CN1992095A (en) * | 2005-12-29 | 2007-07-04 | 中国核动力研究设计院 | Water boiler solution nuclear reactor having inherent security |
CN101325092A (en) * | 2008-07-31 | 2008-12-17 | 中国核动力研究设计院 | Solution stack for burning plutonium and transmutation of neptunium-237 or americium-241 |
CN102831946A (en) * | 2011-06-15 | 2012-12-19 | 中国核动力研究设计院 | Medical isotope production reactor capable of reducing reactor core uranium inventory |
CN104376889A (en) * | 2013-08-12 | 2015-02-25 | 中国核动力研究设计院 | Reactor core of medical isotope production reactor |
-
2016
- 2016-10-18 CN CN201610905575.7A patent/CN106384616B/en active Active
Patent Citations (7)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN1355540A (en) * | 2002-01-08 | 2002-06-26 | 中国核动力研究设计院 | Low-temp nuclear reactor with dead fuel for nuclear power station |
RU2255389C1 (en) * | 2004-04-27 | 2005-06-27 | Горбунов Евгений Константинович | Uranium-graphite reactor irradiating device for irradiating materials |
RU2004121204A (en) * | 2004-07-13 | 2006-01-10 | Дмитрий Юрьевич Чувилин (RU) | METHOD FOR PRODUCING RADIOISOTOPE OF STRONTS-89 |
CN1992095A (en) * | 2005-12-29 | 2007-07-04 | 中国核动力研究设计院 | Water boiler solution nuclear reactor having inherent security |
CN101325092A (en) * | 2008-07-31 | 2008-12-17 | 中国核动力研究设计院 | Solution stack for burning plutonium and transmutation of neptunium-237 or americium-241 |
CN102831946A (en) * | 2011-06-15 | 2012-12-19 | 中国核动力研究设计院 | Medical isotope production reactor capable of reducing reactor core uranium inventory |
CN104376889A (en) * | 2013-08-12 | 2015-02-25 | 中国核动力研究设计院 | Reactor core of medical isotope production reactor |
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