CN104143365B - Neutron poison sandwich structure with openings in continuous dissolver - Google Patents
Neutron poison sandwich structure with openings in continuous dissolver Download PDFInfo
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- CN104143365B CN104143365B CN201410323482.4A CN201410323482A CN104143365B CN 104143365 B CN104143365 B CN 104143365B CN 201410323482 A CN201410323482 A CN 201410323482A CN 104143365 B CN104143365 B CN 104143365B
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- neutron poison
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02W—CLIMATE CHANGE MITIGATION TECHNOLOGIES RELATED TO WASTEWATER TREATMENT OR WASTE MANAGEMENT
- Y02W30/00—Technologies for solid waste management
- Y02W30/50—Reuse, recycling or recovery technologies
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- Solid Fuels And Fuel-Associated Substances (AREA)
- Particle Accelerators (AREA)
Abstract
The invention relates to a criticality safety control technology used by spent fuel dissolution equipment of a reprocessing plant, and in particular relates to a neutron poison sandwich structure with openings in a continuous dissolver. The neutron poison sandwich structure comprises a container for containing a spent fuel pellet to be dissolved; a plurality of openings for exchanging solutions are formed in the top wall and the bottom wall of the container; the top wall and the bottom wall of the container respectively have a sandwich structure and respectively comprise a stainless steel inner wall and a stainless steel outer wall; neutron poison is arranged between each stainless steel inner wall and the corresponding stainless steel outer wall. With the neutron poison sandwich structure, the distance between the neutron poison and a criticality safety control object, namely, a fissile material, is short, so that the neutron absorption effect of the neutron poison is improved, the reactivity in the dissolver is weakened, and the processing capacity of the dissolver is improved.
Description
Technical field
The present invention relates to the control technology of criticality safety is and in particular to one kind is continuous in reprocessing plant spentnuclear fuel dissolution equipment
The neutron poison sandwich of perforate is contained in dissolvers.
Background technology
The policy of China's nuclear fuel cycle takes the nuclear fuel cycle mode of closure, send for the spentnuclear fuel drawing off in heap
Enter reprocessing plant, uranium, plutonium are separated from spentnuclear fuel and recycles.The post processing of spentnuclear fuel is the important rank of closure nuclear fuel cycle
Section, aftertreatment technology process mainly includes head end process, Chemical Decomposition and uranium, plutonium trail processing process.The technique of reprocessing plant
Many links are had to need to carry out criticality safety control design case and analysis in flow process, wherein head end is processed mainly to irradiated fuel assembly
Carry out cutting, dissolve, filter, flavoring agent, preparing for Chemical Decomposition, easy fissioner compares the position of concentration, and spentnuclear fuel with
Lysate defines a kind of dual uneven system of solid-liquid, is the equipment needing to pay close attention to criticality safety.
Manage ability and the requirement of the spentnuclear fuel amount processing in order to adapt to higher position in large-scale spentnuclear fuel reprocessing plant, to molten
Solution device has carried out the design of continuous processing technique.The structure of continuous-dissolution device compared with the complex structure of batch dissolvers, for equipment
Design and safety analysis are proposed higher requirement.In order that continuous-dissolution device can process the spentnuclear fuel of higher initial enrichment
Assembly, it usually needs jointly realize continuous-dissolution device for high initial enrichment with reference to several different criticality safety control devices
The processing requirement of fuel assembly, such as be a kind of more common criticality safety control device using solid neutron poison.
Content of the invention
The invention aims to ensureing continuous-dissolution device facing when dissolving the irradiated fuel assembly of high initial enrichment
Boundary's safety, provides the neutron poison sandwich containing perforate in a kind of continuous-dissolution device.
Technical scheme is as follows: contains the neutron poison sandwich of perforate in a kind of continuous-dissolution device, including use
In the container loading spentnuclear fuel pellet to be dissolved, the roof of described container and diapire are provided with some opening for solution exchange
Hole, wherein, the roof of described container and diapire are sandwich, include rustless steel inner and outer wall respectively, in rustless steel
It is provided with neutron poison between wall and outer wall.
Further, the neutron poison sandwich of perforate, wherein, described neutron are contained in continuous-dissolution device as above
Poisonous substance is containing b4The boron aluminium alloy of c percentage by weight 15%-30% or boron steel alloy, boracic percentage by weight 1.3%-1.8%
Boron steel, Gadolinia. or metal cadmium material.
Further, the neutron poison sandwich of perforate, wherein, described neutron are contained in continuous-dissolution device as above
The thickness of poisonous substance is 0.05cm-0.5cm.
Further, the neutron poison sandwich of perforate, wherein, described rustless steel are contained in continuous-dissolution device as above
Inner wall thickness is 0.1cm-0.2cm, and the thickness of rustless steel outer wall is 0.05cm-0.1cm.
Beneficial effects of the present invention are as follows: present invention directly contact in continuous-dissolution device dissolve pellet containing perforate
Add the solid neutron poison of sandwich type in chamber wall, make neutron poison be fissile material with the control object of criticality safety
Distance closer to, increase neutron poison neutron-absorbing effect, reduce dissolvers in reactivity, improve dissolvers process energy
Power, the size of perforate simultaneously and the spacing of perforate are conducive to the exchange of both sides solution, can stop that larger spentnuclear fuel is broken simultaneously
Block leaks.After technical scheme, the type according to selected neutron poison and the weight hundred of effective ingredient
Point ratio, continuous-dissolution device can be implemented in rely under normal and conceivable accident operating mode interpolation solid neutron poison critical in guarantee
The irradiated fuel assembly of dissolving initial enrichment higher (as initial enrichment 4.45%) in the case of the requirement of safety.
Brief description
Fig. 1 is dissolving structure (bailing bucket) schematic diagram loading spentnuclear fuel pellet；
Fig. 2 contains the vessel top wall schematic diagram of perforate for bailing bucket；
The solid neutron poison that Fig. 3 contains interlayer for bailing bucket wall arranges sectional view；
Fig. 4 be the bailing bucket containing solid neutron poison contain dissolving fuel pellet when longitudinal section.
Specific embodiment
With reference to the accompanying drawings and examples the present invention is described in detail.
In continuous-dissolution device, the container part structure of directly contact pellet is as shown in figure 1, the container of this dissolving (is referred to as below
For bailing bucket) in addition structure proximate, in there being certain thickness segment, for loading spentnuclear fuel pellet to be dissolved, and be placed on
Carry out the dissolution process of spentnuclear fuel in one flat tank therefor.Denote diapire 1 and the side wall 2 of bailing bucket in Fig. 1, do not show container
Roof.In dissolving in order to ensure the exchange of the solution in bailing bucket and the solution outside bailing bucket, in the top of container and bottom
All there is perforate 4, as shown in Figure 2 on chamber wall 3,1.
In whole dissolver, this bailing bucket thickness is less, and is head, between bailing bucket and outside flat tank therefor
Spacing is also narrower, cannot accommodate independent solid neutron poison in space, and is considered as neutron poison in the salpeter solution of high temperature
Neutron poison is therefore designed as sandwich type by the resistance to corrosion of thing and the guarantee of effectiveness, and neutron poison is filled in container
In wall, the section of the part of neutron poison arrangement is as shown in Figure 3.In Fig. 3,4 is the perforate on chamber wall, and 5 and 6 represent appearance respectively
The rustless steel outer wall of wall and inwall, rustless steel inner wall thickness is generally 0.1-0.2cm, and the thickness of rustless steel outer wall is generally
0.05-0.1cm, 7 expression neutron poisons being arranged therein.The material of neutron poison can be selected for containing b4C percentage by weight 15%-
30% boron aluminium alloy, the boron steel of boracic percentage by weight 1.3%-1.8%, Gadolinia. or metal cadmium material, also do not limit certainly
Due to above-mentioned four kinds of materials, the thickness of neutron poison is 0.05-0.5cm, can be carried out accordingly according to the concrete material of neutron poison
Calculating determining.
Using neutron poison arrangement as shown in Figure 3 as the chamber wall of bailing bucket version, Fig. 4 show containing
The longitudinal section of bailing bucket during the fuel pellet of dissolving, as shown in figure 4, fuel pellet 8 to be dissolved is arranged in bailing bucket with pellet shapes
Inside, this is a kind of distribution of hypothesis, in practice form in bailing bucket for the fuel pellet be in random distribution, fuel pellet 8 it
Between distribution for lysate 9, fuel pellet 8 and lysate 9 are loaded in bailing bucket.Neutron poison 7 is arranged in bailing bucket with sandwich format
Between the rustless steel inwall 6 of bucket capacity wall and outer wall 5, bailing bucket chamber wall leaves at certain intervals perforate 4 as shown in Figure 2 with
Just inside and outside solution exchanges.
The dissolvers reactivity implementing above-mentioned neutron poison arrangement will decline to a great extent, using this kind of criticality safety control mode
Afterwards, neutron poison be set to thickness 0.5cm containing b4The boron aluminum alloy materials of c percentage by weight 20%, fixing neutron poison
Introducing makes the reactivity of this dissolvers have dropped 0.1096, i.e. δ keffFor 10960pcm, calculate and show now, this dissolvers
The requirement of criticality safety all can be met under normal and conceivable accident operating mode, the fuel that initial enrichment is 4.45% can be processed
Assembly is it is seen that under this arrangement form, the area that neutron poison covers is larger, neutron-absorbing close together from fissile material
Effect is obvious.The absorption cross-section of different neutron poison materials is different, and therefore the type of neutron poison and thickness will affect critical peace
Full result of calculation, the CRITICAL CALCULATION result under different neutron poison types and thickness, the factor of effectively rising in value all should meet
The acceptance criterion of criticality safety.When the content keeping bailing bucket basic structure, continuous-dissolution device to be filled, neutron poison both sides are stainless
During steel inside and outside wall size constancy, the Critical Control effect that neutron poison is set to the cadmium metal of thickness 0.3cm can also meet continuously
The requirement of criticality safety when dissolvers process the fuel assembly that initial enrichment is 4.45%.
Obviously, those skilled in the art can carry out the various changes and modification essence without deviating from the present invention to the present invention
God and scope.So, if these modifications to the present invention and modification belong to the model of the claims in the present invention and its equivalent technology
Within enclosing, then the present invention is also intended to comprise these changes and modification.
Claims (4)
1. contain the neutron poison sandwich of perforate in a kind of continuous-dissolution device, including for loading spentnuclear fuel pellet to be dissolved
Container, the roof of described container and diapire be provided with some perforates for solution exchange it is characterised in that: the top of described container
Wall and diapire are sandwich, include rustless steel inner and outer wall respectively, are provided with neutron between rustless steel inner and outer wall
Poisonous substance.
2. in continuous-dissolution device as claimed in claim 1 contain perforate neutron poison sandwich it is characterised in that: described
Neutron poison can be containing b4The boron aluminium alloy of c percentage by weight 15%-30%, boracic percentage by weight 1.3%-1.8%
Boron steel, Gadolinia. or metal cadmium material.
3. in continuous-dissolution device as claimed in claim 1 or 2 contain perforate neutron poison sandwich it is characterised in that: institute
The thickness of the neutron poison stated is 0.05cm-0.5cm.
4. in continuous-dissolution device as claimed in claim 1 or 2 contain perforate neutron poison sandwich it is characterised in that: institute
Stating rustless steel inner wall thickness is 0.1cm-0.2cm, and the thickness of rustless steel outer wall is 0.05cm-0.1cm.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201410323482.4A CN104143365B (en) | 2014-07-08 | 2014-07-08 | Neutron poison sandwich structure with openings in continuous dissolver |
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201410323482.4A CN104143365B (en) | 2014-07-08 | 2014-07-08 | Neutron poison sandwich structure with openings in continuous dissolver |
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| CN104143365A CN104143365A (en) | 2014-11-12 |
| CN104143365B true CN104143365B (en) | 2017-02-01 |
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| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN105895176B (en) * | 2015-01-01 | 2018-07-17 | 杨宝光 | A kind of spent fuel element section continuous-dissolution device with spiral-push device |
| CN105931687B (en) * | 2016-06-14 | 2019-07-02 | 中国核电工程有限公司 | A kind of irradiated fuel store cell |
| CN110739093B (en) * | 2019-09-23 | 2022-11-18 | 中国核电工程有限公司 | Critical safety control method for solution storage tank in nuclear fuel post-treatment |
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| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| DE2715367A1 (en) * | 1977-04-06 | 1978-10-12 | Kernforschungsz Karlsruhe | REMOVER FOR RELEASING NUCLEAR FUEL FROM FUEL ELEMENT SECTIONS |
| JPH10132989A (en) * | 1996-10-31 | 1998-05-22 | Mitsubishi Heavy Ind Ltd | Solution tank |
| JP3524743B2 (en) * | 1997-12-12 | 2004-05-10 | 三菱重工業株式会社 | Reprocessing of spent LWR fuel |
| JP5193687B2 (en) * | 2008-05-30 | 2013-05-08 | 株式会社東芝 | Spent fuel reprocessing method |
| CN101777398B (en) * | 2010-01-20 | 2013-01-30 | 清华大学 | Pebble bed high-temperature reactor fuel storage tank |
| CN203663718U (en) * | 2013-12-10 | 2014-06-25 | 中核四〇四有限公司 | Novel continuous dissolver |
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