CN110728033B - Critical safety design method of fluidized bed in nuclear fuel aftertreatment - Google Patents
Critical safety design method of fluidized bed in nuclear fuel aftertreatment Download PDFInfo
- Publication number
- CN110728033B CN110728033B CN201910899705.4A CN201910899705A CN110728033B CN 110728033 B CN110728033 B CN 110728033B CN 201910899705 A CN201910899705 A CN 201910899705A CN 110728033 B CN110728033 B CN 110728033B
- Authority
- CN
- China
- Prior art keywords
- design
- fluidized bed
- critical
- volume ratio
- curve
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Active
Links
- 238000013461 design Methods 0.000 title claims abstract description 121
- 238000000034 method Methods 0.000 title claims abstract description 45
- 239000003758 nuclear fuel Substances 0.000 title claims abstract description 26
- 238000004364 calculation method Methods 0.000 claims abstract description 15
- 238000005457 optimization Methods 0.000 claims abstract description 10
- JCMLRUNDSXARRW-UHFFFAOYSA-N trioxouranium Chemical compound O=[U](=O)=O JCMLRUNDSXARRW-UHFFFAOYSA-N 0.000 claims description 82
- 238000010438 heat treatment Methods 0.000 claims description 17
- 230000008569 process Effects 0.000 claims description 11
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 10
- 238000009825 accumulation Methods 0.000 claims description 4
- 230000000694 effects Effects 0.000 claims description 4
- 239000000203 mixture Substances 0.000 claims description 3
- 239000007787 solid Substances 0.000 claims description 3
- 230000007704 transition Effects 0.000 description 6
- 229910052770 Uranium Inorganic materials 0.000 description 5
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 description 5
- 239000007788 liquid Substances 0.000 description 4
- 238000012958 reprocessing Methods 0.000 description 4
- 239000002915 spent fuel radioactive waste Substances 0.000 description 4
- 238000001914 filtration Methods 0.000 description 3
- 239000002245 particle Substances 0.000 description 3
- 239000000047 product Substances 0.000 description 3
- 238000005202 decontamination Methods 0.000 description 2
- 238000004519 manufacturing process Methods 0.000 description 2
- 238000012986 modification Methods 0.000 description 2
- 230000004048 modification Effects 0.000 description 2
- 230000005658 nuclear physics Effects 0.000 description 2
- 238000012545 processing Methods 0.000 description 2
- 238000000926 separation method Methods 0.000 description 2
- 229910052778 Plutonium Inorganic materials 0.000 description 1
- 238000010521 absorption reaction Methods 0.000 description 1
- 230000004075 alteration Effects 0.000 description 1
- 230000003321 amplification Effects 0.000 description 1
- 238000004458 analytical method Methods 0.000 description 1
- 230000000712 assembly Effects 0.000 description 1
- 238000000429 assembly Methods 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 239000012141 concentrate Substances 0.000 description 1
- 238000011161 development Methods 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 238000001035 drying Methods 0.000 description 1
- 239000012467 final product Substances 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 238000003199 nucleic acid amplification method Methods 0.000 description 1
- OYEHPCDNVJXUIW-UHFFFAOYSA-N plutonium atom Chemical compound [Pu] OYEHPCDNVJXUIW-UHFFFAOYSA-N 0.000 description 1
- 238000012805 post-processing Methods 0.000 description 1
- 230000035755 proliferation Effects 0.000 description 1
- 238000003908 quality control method Methods 0.000 description 1
- 238000011084 recovery Methods 0.000 description 1
- 238000012552 review Methods 0.000 description 1
- 238000010008 shearing Methods 0.000 description 1
- 239000000126 substance Substances 0.000 description 1
- ZIMRZUAJVYACHE-UHFFFAOYSA-N uranium;hydrate Chemical compound O.[U] ZIMRZUAJVYACHE-UHFFFAOYSA-N 0.000 description 1
- 229910002007 uranyl nitrate Inorganic materials 0.000 description 1
Classifications
-
- G—PHYSICS
- G16—INFORMATION AND COMMUNICATION TECHNOLOGY [ICT] SPECIALLY ADAPTED FOR SPECIFIC APPLICATION FIELDS
- G16C—COMPUTATIONAL CHEMISTRY; CHEMOINFORMATICS; COMPUTATIONAL MATERIALS SCIENCE
- G16C10/00—Computational theoretical chemistry, i.e. ICT specially adapted for theoretical aspects of quantum chemistry, molecular mechanics, molecular dynamics or the like
Landscapes
- Engineering & Computer Science (AREA)
- Computing Systems (AREA)
- Theoretical Computer Science (AREA)
- Physics & Mathematics (AREA)
- Health & Medical Sciences (AREA)
- General Health & Medical Sciences (AREA)
- Spectroscopy & Molecular Physics (AREA)
- Life Sciences & Earth Sciences (AREA)
- Bioinformatics & Cheminformatics (AREA)
- Bioinformatics & Computational Biology (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention belongs to the technical field of nuclear safety design, and relates to a critical safety design method of a fluidized bed in nuclear fuel aftertreatment. The design method comprises the following steps: (1) Determining preliminary design parameters and performing preliminary design on the fluidized bed; (2) calculating the critical value of an infinitely long cylinder; (3) volume ratio curve drawing; (4) Judging whether the volume ratio curve obtained in the step (3) is below a limit value curve at the whole height; (5) Carrying out the primary design of the fluidized bed in the step (1), the drawing of the volume ratio curve in the step (3) and the judgment in the step (4) again by modifying the equipment size and the technological parameters, or judging whether a design optimization space exists; and (6) performing critical rechecking calculation on the design. By using the design method of the invention, a great amount of design work can be saved under the condition of meeting critical safety, and simultaneously, the design size and the technological parameters can be adjusted and optimized by equipment designers in a certain range.
Description
Technical Field
The invention belongs to the technical field of nuclear safety design, and relates to a critical safety design method of a fluidized bed in nuclear fuel aftertreatment.
Background
The development of the nuclear industry in China is rapid, and the generated spent fuel assemblies are increased increasingly, so that higher requirements are put forward on nuclear fuel post-treatment in China. The post-treatment of spent fuel is an important component of closed nuclear fuel circulation in China, and the treatment process mainly comprises the first-stage shearing and dissolving treatment, the co-decontamination separation treatment, and the plutonium line and uranium line treatment processes, wherein the uranium line treatment is to further purify the uranyl nitrate solution after the co-decontamination separation treatment, then evaporate and concentrate feed liquid, and then remove the production line to convert the uranium trioxide into a final product. Because of the processing of fissile nuclides, many process links of spent fuel post-processing, including uranium line processing, require critical safety control design and analysis.
The fluidized bed is key equipment for uranium line treatment in spent fuel post-treatment, and is mainly used for finally forming uranium trioxide products, and the treatment capacity of the fluidized bed is directly related to uranium recovery production capacity of the whole process; the fluidized bed has a higher critical risk because uranium trioxide products are formed and feed liquid enters the fluidized bed, wherein the substances have a solid-liquid two-phase state. In addition, the fluidized bed is operated at high temperature, and is internally provided with devices such as heating, filtering and the like, and neutron absorption materials are not suitable for being arranged to ensure critical safety, so that the critical safety is usually ensured by adopting means such as geometric control, quality control and the like in design.
However, fluidized bed equipment designers often design equipment with a relatively large design capacity for increasing throughput, and at the same time limit the quality of uranium trioxide which can be processed by the equipment to a relatively high value, so that the design often fails to meet critical safety requirements when a nuclear physics professional performs a review. Because nuclear physics professionals lack the relevant knowledge of fluidized bed equipment design and can not give better advice, how to provide design guidance for fluidized bed designers under the condition of meeting critical safety is more conservative, so that a great deal of design work is saved, and meanwhile, the adjustment and optimization of design size and process parameters by equipment designers in a certain range is an urgent requirement for critical safety design of a fluidized bed in nuclear fuel aftertreatment.
Regarding the design of the fluidized bed, some reports exist in the prior art, for example, chinese patent application 201710950743.9 discloses a design method of fluidized bed drying and classifying equipment, chinese patent application 201810770033.2 discloses a CFD-based optimization design method of circulating fluidized bed feed back pipe structure, and chinese patent application 201210115667.7 discloses a multi-hearth circulating fluidized bed boiler based on module amplification design, but none of them relates to critical safety design of fluidized bed in nuclear fuel post-treatment.
Disclosure of Invention
The invention aims to provide a critical safety design method of a fluidized bed in nuclear fuel post-treatment, so that a great deal of design work can be saved under the condition of meeting critical safety, and meanwhile, equipment designers can adjust and optimize design dimensions and process parameters in a certain range.
To achieve this object, in a basic embodiment, the present invention provides a critical safety design method of a fluidized bed in nuclear fuel reprocessing, the design method comprising the steps of:
(1) Determining preliminary design parameters and performing preliminary design on the fluidized bed;
(2) Calculating the critical value of an infinitely long cylinder: performing infinite long cylinder critical calculation on the basis of the preliminary design parameters determined in the step (1);
(3) Volume ratio curve drawing: calculating the volume ratio of the fluidized bed at different heights on the basis of the preliminary design of the fluidized bed in the step (1), and drawing a curve of the volume ratio of the fluidized bed at different heights and the volume ratio of the corresponding limit;
(4) Judging whether the volume ratio curve obtained in the step (3) is below a limit value curve at the whole height:
(5) If the conclusion of the step (4) is no, the primary design of the fluidized bed of the step (1), the drawing of the volume ratio curve of the step (3) and the judgment of the step (4) are carried out again by modifying the equipment size and the technological parameters;
(6) If the conclusion of the step (4) is yes, judging whether a design optimization space exists or not;
(7) If the conclusion in the step (6) is negative, carrying out critical rechecking calculation on the design; if the conclusion of the step (6) is yes, the preliminary design of the fluidized bed of the step (1), the drawing of the volume ratio curve of the step (3) and the judgment of the steps (4) and (6) are carried out again by modifying the equipment size and the technological parameters.
In a preferred embodiment, the invention provides a critical safety design method for a fluidized bed in nuclear fuel reprocessing, wherein in step (1) determining preliminary design parameters comprises determining parameters of uranium trioxide.
In a more preferred embodiment, the invention provides a critical safety design method of a fluidized bed in nuclear fuel post-treatment, wherein the parameters of uranium trioxide comprise uranium trioxide density and particle size range.
In a preferred embodiment, the invention provides a critical safety design method of a fluidized bed in nuclear fuel post-treatment, wherein in the step (1), preliminary design of the fluidized bed comprises design of external dimensions and process parameters.
In a preferred embodiment, the invention provides a critical safety design method of a fluidized bed in nuclear fuel post-treatment, wherein in the step (2), the critical calculation of the infinite cylinders is to calculate the infinite multiplication factors k inf of the infinite cylinders with different radiuses according to the determined preliminary design parameters, the outer side of the cylinders should comprise a water layer with the thickness of at least 20cm during calculation, the mixture of water and uranium trioxide solids is arranged in the cylinders, the inhomogeneous effect of uranium trioxide and water should be fully considered, and the situation when different uranium trioxide filling rates or volume ratios should be considered.
In a preferred embodiment, the present invention provides a critical safety design method for a fluidized bed in nuclear fuel reprocessing, wherein in step (3),
Determining the minimum uranium trioxide filling rate reaching a certain set critical safety limit according to k inf corresponding to different uranium trioxide filling rates under different infinite cylinder radiuses obtained in the step (2), so that under a certain radius, a corresponding uranium trioxide filling rate can be obtained, and when the uranium trioxide filling rate is smaller than or equal to the value, the k inf of the corresponding cylinder is smaller than or equal to the set critical safety limit; when the uranium trioxide filling rate is greater than this value, the corresponding cylinder k inf may be greater than the set critical safety limit,
According to the calculated corresponding relation between the infinite cylindrical radius and the uranium trioxide filling rate under a certain limit value, and combining the preliminary design of the fluidized bed, drawing a relation curve of the uranium trioxide filling rate under the cylindrical radius corresponding to the fluidized bed at different heights, and simultaneously drawing real uranium trioxide filling rates at different heights under the preliminary design according to the loading capacity of the preliminary design of the fluidized bed.
In a more preferred embodiment, the invention provides a critical safety design method of a fluidized bed in nuclear fuel post-treatment, wherein in the step (4), according to the actual filling rate of uranium trioxide at different heights under the drawn preliminary design, if the curves drawn under the preliminary design are all positioned below a limit value curve in a non-geometric safety area of the fluidized bed, the critical safety condition can be met; if it is above the limit curve, the critical safety condition may not be satisfied.
In a preferred embodiment, the present invention provides a critical safety design method for a fluidized bed in nuclear fuel post-treatment, wherein in the step (6), according to the condition of the volume ratio curve, if there is a point that may not meet the critical safety limit, i.e. the volume ratio curve is above the limit curve, the equipment size or the process parameters need to be modified, and the volume ratio curve is redrawn to determine; if the critical safety limit values are all met, whether the optimization design is performed can be determined, for example, if the volume ratio curve is below the limit value curve and is far away from the limit value curve, the uranium trioxide design loading capacity of the fluidized bed can be improved or the equipment size of the fluidized bed can be enlarged at the same time, so that more optimal design can be realized.
In a preferred embodiment, the invention provides a critical safety design method of a fluidized bed in nuclear fuel post-treatment, wherein in the step (7), critical re-checking calculation is performed on a finally formed design scheme, and when the stack height of uranium trioxide is lower than the height of a heating section, the design method is geometrically safe; when the uranium trioxide accumulation height is higher than the heating section height, the maximum k eff of the uranium trioxide accumulation height is rechecked.
The method has the advantages that by utilizing the critical safety design method of the fluidized bed in the nuclear fuel post-treatment, a great amount of design work can be saved under the condition of meeting the critical safety, and meanwhile, the design size and the technological parameters can be adjusted and optimized by equipment designers in a certain range.
The invention establishes a set of method for quickly and effectively judging whether the design of the fluidized bed in the nuclear fuel post-treatment meets the critical safety requirement or not by pre-calculating the related limit value and drawing the limit value curve, and can be used in the initial stage and the optimized design of the fluidized bed equipment. The method has the advantages that during equipment design, a guide is provided for selecting specific values of a plurality of design parameters affecting critical safety of the fluidized bed before a large amount of fine calculation is performed, meanwhile, whether the current design has an optimized space can be judged, and an optimization mode is determined, so that multi-parameter optimization design is realized.
Drawings
Fig. 1 is a block diagram of an exemplary nuclear fuel aftertreatment employing a fluidized bed.
FIG. 2 is a flow chart of an exemplary method of critical safety design of a fluidized bed in nuclear fuel reprocessing of the present invention.
FIG. 3 is a graph showing effective multiplication factors of an infinitely long cylinder in the embodiment.
FIG. 4 is a graph showing the design of a fluidized bed in an embodiment.
Detailed Description
The following describes the embodiments of the present invention further with reference to the drawings.
An exemplary nuclear fuel aftertreatment using a fluidized bed is shown in fig. 1 and includes a heating section 1, a transition section 2, and an expansion section 3 connected in sequence from bottom to top.
An exemplary flow of the critical safety design method of the fluidized bed in nuclear fuel aftertreatment of the present invention is shown in FIG. 2, comprising the steps of:
(1) Determining preliminary design parameters: parameters of uranium trioxide, such as the density, the particle size range and the like of the uranium trioxide, are determined, and meanwhile, the fluidized bed is primarily designed, and the parameters are mainly the outline dimension and the technological parameters of the fluidized bed.
(2) Calculating the critical value of an infinitely long cylinder: according to the determined uranium trioxide parameters, calculating an infinite multiplication factor k inf of an infinite cylinder with different radiuses, wherein the outside of the cylinder is required to comprise a water layer with the thickness of at least 20cm, a mixture of water and UO 3 solids is required to be arranged in the cylinder, the inhomogeneous effect of UO 3 and water is required to be fully considered, and meanwhile, the situation when the filling rate (volume ratio) of UO 3 is required to be different is required to be considered.
(3) Determining a corresponding limit value relation: and (3) determining the minimum UO 3 filling rate reaching a certain set critical safety limit according to the k inf corresponding to the different UO 3 filling rates under different infinite cylinder radiuses obtained in the step (2), so that under a certain radius, a corresponding UO 3 filling rate can be obtained, when the UO 3 filling rate is smaller than or equal to the value, the k inf of the corresponding cylinder is smaller than or equal to the set critical safety limit, and when the UO 3 filling rate is larger than the value, the k inf of the corresponding cylinder is possibly larger than the set critical safety limit.
(4) Drawing a curve: according to the calculated corresponding relation between the infinite cylinder radius and the UO 3 filling rate under a certain limit value, the relation curve of the UO 3 filling rate under the cylinder radius corresponding to the fluidized bed at different heights can be drawn by combining the primary design of the fluidized bed, and meanwhile, the real UO 3 filling rate at different heights under the primary design can be drawn according to the loading capacity of the primary design of the fluidized bed. If the curves drawn under the preliminary design are all below the limit curves in the non-geometric safe region of the fluidized bed, the critical safety conditions can be satisfied, and if the curves are above the limit curves, the critical safety conditions may not be satisfied.
(5) And (3) optimizing design: according to the condition of the curve, if there is a point which possibly does not meet the critical safety limit, namely when the primary design curve is positioned above the limit curve, the equipment size or the process parameters are required to be modified, and the curve is drawn again for judgment. If the critical safety limit values are all met, it can be determined whether to perform the optimization design, for example, if the preliminary design curve is below the limit value curve and is far away from the limit value curve, the UO 3 design load capacity of the fluidized bed can be increased or the equipment size of the fluidized bed can be enlarged at the same time, so as to realize a more optimized design.
(6) Rechecking and calculating: and (5) rechecking and calculating the finally formed scheme. The UO 3 is geometrically safe when its stack height is lower than the heating section height. When the UO 3 stack height is higher than the heating section height, its maximum k eff is rechecked.
The above-described exemplary application of the critical safety design method of the fluidized bed in the nuclear fuel post-treatment of the present invention is exemplified as follows.
As shown in fig. 1, the fluidized bed apparatus is composed of a heating section 1, a transition section 2, and an expansion section 3. Because the feed liquid enters from the heating section 1, the heating section 1 is thinner and should be geometrically safe in order to meet the critical safety requirement. The main function of the expansion section 3 is the filtration of UO 3 products, and the size design is larger, which is beneficial to the filtration effect. The expansion section 3 and the heating section 1 are connected by a transition section 2. When the equipment is in normal operation, the UO 3 fills the whole space, the water content is low, and the equipment is easy to meet critical safety conditions; however, when a flooding accident occurs and UO 3 is stacked from the bottom, the stacking height is higher than that of the heating section 1, and when the flooding accident is out of the geometric safety range, a critical risk exists, and a critical safety design is required.
According to the step (1), selecting a UO 3 density of 7.5g/cm 3 and a particle size range of 0.001-3cm, wherein the initial design parameters of the fluidized bed are as follows: the radius of the heating section 1 is 15cm, the height is 280cm, the height of the transition section 2 is 90cm, the radius of the expanding section 3 is 30cm, the height is 100cm, and the planned loading UO 3 is 200kg.
As shown in step (2), the effective multiplication factors of the system at different UO 3 filling rates at infinite cylinder radii of 15cm, 17cm, 20cm, 25cm, 30cm, respectively, were calculated as shown in FIG. 3.
According to the step (3), 0.9 is selected as a critical safety limit value, and when the radius of the infinitely long cylinder is 15cm, the effective proliferation factor of the cylinder is not more than 0.9, so that the geometric safety is realized, namely the design of the heating section of the fluidized bed meets the requirement; when the infinite cylinder is larger than 15cm, the minimum UO 3 filling rate corresponding relation when the effective multiplication factor reaches 0.9 is as follows: the filling rate at the radius of 17cm is 0.29, the filling rate at the radius of 20cm is 0.2, the filling rate at the radius of 25cm is 0.16, and the filling rate at the radius of 30cm is 0.14.
When 200kg of UO 3 loading capacity is calculated respectively according to the step (4), the UO 3 filling rate at different heights is piled up, a curve is drawn, and meanwhile, the UO 3 filling rate limit value corresponding to the radius at the height is drawn, as shown in fig. 4.
According to the method shown in the step (5), when the stacking height is low, the corresponding radius is small, the UO 3 is positioned in a geometric safety area, and the influence of the filling rate of the UO 3 is not needed to be considered; when the stacking height is increased and UO 3 is separated from the geometric safety zone, as can be seen from fig. 4, when the loading capacity is 200kg of UO 3, the preliminary design curve is positioned below the limit curve and has a certain distance, the scheme can be used for optimizing design, the process parameter changing mode is adopted for optimizing, the loading capacity of UO 3 is improved, and when the loading capacity of UO 3 is 330kg, the preliminary design curve is very close to the limit curve, and 330kg of UO 3 can be loaded. Because the design is an infinitely long cylinder, but is finite in practice, and the effective multiplication factor of the transition section 2 is smaller than that of the corresponding cylinder when the transition section 2 is a round table, the design scheme given by the method is conservative.
According to the method, as shown in the step (6), critical rechecking calculation is carried out on UO 3 with the loading capacity of 330kg, and the geometric safety is realized when the stacking height is lower than the heating section height; when the stacking height is higher than the heating section height, the maximum k eff is 0.8117, and the critical safety requirement is met.
It will be apparent to those skilled in the art that various modifications and variations can be made to the present invention without departing from the spirit or scope of the invention. Thus, it is intended that the present invention also include such modifications and alterations insofar as they come within the scope of the appended claims or the equivalents thereof. The above embodiments are merely illustrative of the present invention, and the present invention may be embodied in other specific forms or with other specific forms without departing from the spirit or essential characteristics thereof. The described embodiments are, therefore, to be considered in all respects as illustrative and not restrictive. The scope of the invention should be indicated by the appended claims, and any changes that are equivalent to the intent and scope of the claims are intended to be encompassed within the scope of the invention.
Claims (4)
1. A critical safety design method for a fluidized bed in nuclear fuel aftertreatment, characterized by comprising the following steps:
(1) Determining preliminary design parameters and performing preliminary design on the fluidized bed;
(2) Calculating the critical value of an infinitely long cylinder: performing infinite long cylinder critical calculation on the basis of the preliminary design parameters determined in the step (1);
(3) Volume ratio curve drawing: calculating the volume ratio of the fluidized bed at different heights on the basis of the preliminary design of the fluidized bed in the step (1), and drawing a curve of the volume ratio of the fluidized bed at different heights and the volume ratio of the corresponding limit;
(4) Judging whether the volume ratio curve obtained in the step (3) is below a limit value curve at the whole height:
(5) If the conclusion of the step (4) is no, the primary design of the fluidized bed of the step (1), the drawing of the volume ratio curve of the step (3) and the judgment of the step (4) are carried out again by modifying the equipment size and the technological parameters;
(6) If the conclusion of the step (4) is yes, judging whether a design optimization space exists or not;
(7) If the conclusion in the step (6) is negative, carrying out critical rechecking calculation on the design; if the conclusion of the step (6) is yes, the primary design of the fluidized bed of the step (1), the drawing of the volume ratio curve of the step (3) and the judgment of the steps (4) and (6) are carried out again by modifying the equipment size and the technological parameters;
In step (1), determining preliminary design parameters includes determining parameters of uranium trioxide;
In the step (2), the critical calculation of the infinite cylinders is to calculate the infinite multiplication factors k inf of the infinite cylinders with different radiuses according to the determined preliminary design parameters, and the outer side of the cylinders should include a water layer with the thickness of at least 20cm during the calculation, and the mixture of water and uranium trioxide solids is arranged in the cylinders, so that the inhomogeneous effects of the uranium trioxide and the water should be fully considered, and the situation when the uranium trioxide filling rates or the volume ratios are different should be considered;
In the step (3), the minimum uranium trioxide filling rate reaching a certain set critical safety limit is determined according to k inf corresponding to different uranium trioxide filling rates under different infinite cylinder radiuses obtained in the step (2),
Drawing a relation curve of uranium trioxide filling rates under corresponding cylindrical radii of the fluidized bed at different heights according to the corresponding relation between the infinite cylindrical radius and the uranium trioxide filling rates under a certain limit value, which are obtained by calculation, and combining the preliminary design of the fluidized bed, and drawing real uranium trioxide filling rates at different heights under the preliminary design according to the loading capacity of the preliminary design of the fluidized bed;
In the step (4), judging that if curves drawn under the preliminary design are all positioned below limit curves in a non-geometric safety zone of the fluidized bed according to the actual filling rate of uranium trioxide at different heights under the drawn preliminary design, the critical safety condition can be met; if the threshold value curve is above the limit value curve, the critical safety condition may not be satisfied;
In the step (7), the critical re-checking calculation is carried out on the finally formed design scheme, and the critical re-checking calculation is geometrically safe when the stacking height of uranium trioxide is lower than the height of the heating section; when the uranium trioxide accumulation height is higher than the heating section height, the maximum k eff of the uranium trioxide accumulation height is rechecked.
2. The design method according to claim 1, wherein: the parameters of the uranium trioxide comprise the density and the grain size range of the uranium trioxide.
3. The design method according to claim 1, wherein: in the step (1), the preliminary design of the fluidized bed comprises the design of the external dimension and the technological parameters.
4. The design method according to claim 1, wherein: in the step (6), according to the condition of the volume ratio curve, if a point possibly not meeting the critical safety limit exists, namely, if the volume ratio curve is positioned above the limit curve, the equipment size is required to be modified or the process parameters are required to be modified, and the volume ratio curve is drawn again to judge; if the critical safety limit values are all met, whether the optimization design is performed can be determined.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201910899705.4A CN110728033B (en) | 2019-09-23 | 2019-09-23 | Critical safety design method of fluidized bed in nuclear fuel aftertreatment |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201910899705.4A CN110728033B (en) | 2019-09-23 | 2019-09-23 | Critical safety design method of fluidized bed in nuclear fuel aftertreatment |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN110728033A CN110728033A (en) | 2020-01-24 |
| CN110728033B true CN110728033B (en) | 2024-05-17 |
Family
ID=69218252
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201910899705.4A Active CN110728033B (en) | 2019-09-23 | 2019-09-23 | Critical safety design method of fluidized bed in nuclear fuel aftertreatment |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN110728033B (en) |
Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4399106A (en) * | 1980-09-02 | 1983-08-16 | Kimio Ueda | Reactor for preparing uranium trioxide |
| JP2000284084A (en) * | 1999-03-31 | 2000-10-13 | Japan Atom Energy Res Inst | Fuel rod for high temperature gas reactor |
| CN103137221A (en) * | 2013-01-15 | 2013-06-05 | 西安交通大学 | Subcritical wrapping layer of transmutation of pressure pipe type long-lived fission product |
Family Cites Families (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN114239226A (en) * | 2021-11-23 | 2022-03-25 | 中国核电工程有限公司 | Simplified pipeline equipment room integral critical safety analysis method |
-
2019
- 2019-09-23 CN CN201910899705.4A patent/CN110728033B/en active Active
Patent Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4399106A (en) * | 1980-09-02 | 1983-08-16 | Kimio Ueda | Reactor for preparing uranium trioxide |
| JP2000284084A (en) * | 1999-03-31 | 2000-10-13 | Japan Atom Energy Res Inst | Fuel rod for high temperature gas reactor |
| CN103137221A (en) * | 2013-01-15 | 2013-06-05 | 西安交通大学 | Subcritical wrapping layer of transmutation of pressure pipe type long-lived fission product |
Non-Patent Citations (1)
| Title |
|---|
| 压水堆铀燃料元件加工设施的核安全审评;许明霞等;核安全;全文 * |
Also Published As
| Publication number | Publication date |
|---|---|
| CN110728033A (en) | 2020-01-24 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| Nagy et al. | The effects of core zoning on the graphite lifespan and breeding gain of a moderated molten salt reactor | |
| CN110728033B (en) | Critical safety design method of fluidized bed in nuclear fuel aftertreatment | |
| US20190074097A1 (en) | Method of determining conditions for accommodating radioactive waste in container, radioactive waste accommodating method, and waste body produced using said method | |
| Hou et al. | 3D in-core fuel management optimization for breed-and-burn reactors | |
| Boer et al. | In-core fuel management optimization of pebble-bed reactors | |
| Norouzi et al. | Nuclear reactor core optimization with parallel integer coded genetic algorithm | |
| CN108875207B (en) | Nuclear reactor optimization design method and system | |
| CN111799003A (en) | Method for positioning damaged fuel assembly | |
| CN110739093B (en) | Critical safety control method for solution storage tank in nuclear fuel post-treatment | |
| JP4247410B2 (en) | Method for reusing spent fuel and core structure of fast reactor | |
| JP4940114B2 (en) | Criticality safety management method for continuous dissolution tank in reprocessing facility | |
| EP3885851A1 (en) | System and method for optimization of industrial processes | |
| CN112231897B (en) | Dissolver spent fuel shearing section modeling method for nuclear critical safety analysis | |
| CN204029402U (en) | A kind of batch formula spentnuclear fuel dissolver | |
| CN104239615B (en) | A kind of cylinder door frame automated analysis method | |
| Liu et al. | Burnup-dependent core neutronics analysis of plate-type research reactor using deterministic and stochastic methods | |
| Hunter et al. | A method for reducing the largest relative errors in Monte Carlo iterated-fission-source calculations | |
| CN111625962B (en) | Group optimization method and system of nano-photonics structure based on sequencing prediction | |
| US20080144763A1 (en) | Method for perturbating a nuclear reactor core fuel bundle design to generate a group of designs | |
| Philipov | CFD Analysis of Boron Distribution at Core Entrance in Case of Reverse Flow Induced From PRISE | |
| Lüley et al. | Assembly homogenization technique for VVER-440 reactor multi-group calculations | |
| CN113889202A (en) | Method for estimating fission times of nuclear critical accident in cylindrical uranium solution storage tank | |
| Andrianov et al. | Simulation of neutron-physical processes in the surface layer of a fuel kernel | |
| CN108073733B (en) | Reactor critical safety analysis method and system | |
| Volkov et al. | Reactivity Runaway Reduction When Using Enriched Uranium in a Lead Fast Reactor |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PB01 | Publication | ||
| PB01 | Publication | ||
| SE01 | Entry into force of request for substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| GR01 | Patent grant | ||
| GR01 | Patent grant |