CN110728033A - Critical safety design method for fluidized bed in nuclear fuel post-treatment - Google Patents
Critical safety design method for fluidized bed in nuclear fuel post-treatment Download PDFInfo
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- 238000013461 design Methods 0.000 title claims abstract description 111
- 238000000034 method Methods 0.000 title claims abstract description 56
- 239000003758 nuclear fuel Substances 0.000 title claims abstract description 26
- 238000004364 calculation method Methods 0.000 claims abstract description 23
- 230000008569 process Effects 0.000 claims abstract description 17
- 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 91
- 238000010438 heat treatment Methods 0.000 claims description 17
- 238000012958 reprocessing Methods 0.000 claims description 13
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 11
- 230000000694 effects Effects 0.000 claims description 5
- 239000002245 particle Substances 0.000 claims description 4
- WZECUPJJEIXUKY-UHFFFAOYSA-N [O-2].[O-2].[O-2].[U+6] Chemical compound [O-2].[O-2].[O-2].[U+6] WZECUPJJEIXUKY-UHFFFAOYSA-N 0.000 claims description 2
- 239000000203 mixture Substances 0.000 claims description 2
- 239000007787 solid Substances 0.000 claims description 2
- ZIMRZUAJVYACHE-UHFFFAOYSA-N uranium;hydrate Chemical compound O.[U] ZIMRZUAJVYACHE-UHFFFAOYSA-N 0.000 claims description 2
- 229910052770 Uranium Inorganic materials 0.000 description 5
- 230000007704 transition Effects 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
- 239000002915 spent fuel radioactive waste Substances 0.000 description 4
- 238000012986 modification Methods 0.000 description 3
- 230000004048 modification Effects 0.000 description 3
- 238000012545 processing Methods 0.000 description 3
- 238000005202 decontamination Methods 0.000 description 2
- 238000001914 filtration Methods 0.000 description 2
- 230000005658 nuclear physics Effects 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
- 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
- 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
- 230000004992 fission Effects 0.000 description 1
- 238000004519 manufacturing process Methods 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
- 230000035755 proliferation Effects 0.000 description 1
- 238000003908 quality control method Methods 0.000 description 1
- 238000011084 recovery Methods 0.000 description 1
- 238000010008 shearing Methods 0.000 description 1
- 239000008247 solid mixture Substances 0.000 description 1
- 239000000126 substance Substances 0.000 description 1
- 229910002007 uranyl nitrate Inorganic materials 0.000 description 1
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- G16—INFORMATION AND COMMUNICATION TECHNOLOGY [ICT] SPECIALLY ADAPTED FOR SPECIFIC APPLICATION FIELDS
- G16C—COMPUTATIONAL CHEMISTRY; CHEMOINFORMATICS; COMPUTATIONAL MATERIALS SCIENCE
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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 post-treatment. The design method comprises the following steps: (1) determining preliminary design parameters and carrying out preliminary design on the fluidized bed; (2) performing infinite length cylinder critical calculation; (3) drawing a volume ratio curve; (4) judging whether the volume ratio curve obtained in the step (3) is below a limit value curve on the whole height; (5) modifying the equipment size and the process parameters, and then carrying out the preliminary design of the fluidized bed in the step (1), the volume ratio curve drawing in the step (3) and the judgment in the step (4) again, or judging whether a design optimization space exists; (6) and performing critical rechecking calculation on the design. By using the design method of the invention, under the condition of meeting critical safety, a large amount of design work can be saved, and simultaneously, the design size and the process parameters can be adjusted and optimized by equipment designers within 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 post-treatment.
Background
The development of the nuclear industry in China is rapid, and the number of the generated spent fuel assemblies is increased day by day, which puts forward higher requirements on the 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 processes of first-stage shearing and dissolving treatment, co-decontamination separation treatment, plutonium line and uranium line treatment, wherein the uranium line treatment is to further purify the uranyl nitrate solution subjected to the co-decontamination separation treatment, evaporate and concentrate feed liquid, and then depreciate and convert the solution into a final uranium trioxide product. Many process steps of spent fuel reprocessing, including uranium wire processing, require critical safety control design and analysis due to the processing of fission nuclides involved.
The fluidized bed is a key device for uranium line treatment in spent fuel post-treatment, is mainly used for finally forming a uranium trioxide product, and the treatment capacity of the fluidized bed is directly related to the uranium recovery production capacity of the whole process; the fluidized bed has a larger critical risk because the fluidized bed forms a uranium trioxide product and feed liquid enters the fluidized bed, and substances in the fluidized bed have a solid-liquid two-phase state. In addition, the fluidized bed is operated at high temperature, and devices such as heating, filtering and the like are arranged inside the fluidized bed, so that the neutron absorption material is not suitable for ensuring the critical safety, and the critical safety is usually ensured by adopting means such as geometric control, quality control and the like in the design.
However, fluidized bed equipment designers often design equipment to be large in order to increase the processing capacity during design, and limit the quality of uranium trioxide that can be processed by the equipment to be high, so that when a nuclear physics professional performs rechecking, the design often finds that the critical safety requirements are not met. Because nuclear physics professionals lack knowledge related to fluidized bed equipment design and often cannot give better suggestions, how to provide design guidance for fluidized bed designers conservatively under the condition of meeting critical safety is a urgent requirement for critical safety design of a fluidized bed in nuclear fuel aftertreatment.
Regarding the design of fluidized bed, there are some reports in the prior art, for example, chinese patent application 201710950743.9 discloses a design method of fluidized bed drying classification equipment, chinese patent application 201810770033.2 discloses a circulating fluidized bed feed back pipe structure optimization design method based on CFD, and chinese patent application 201210115667.7 discloses a multi-hearth circulating fluidized bed boiler based on module amplification design, but they do not relate to the 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, which can greatly save design work under the condition of meeting critical safety and simultaneously enable equipment designers to adjust and optimize design size and process parameters within a certain range.
To achieve this object, in a basic embodiment, the present invention provides a method for the critical safety design of a fluidized bed in nuclear fuel reprocessing, said design method comprising the steps of:
(1) determining preliminary design parameters and carrying out preliminary design on the fluidized bed;
(2) and (3) performing infinite length cylinder critical calculation: performing infinite-length cylinder critical calculation on the basis of the preliminary design parameters determined in the step (1);
(3) and (3) drawing a volume ratio curve: 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 volume ratio curve of the volume ratio of the fluidized bed at different heights and corresponding limitation;
(4) judging whether the volume ratio curve obtained in the step (3) is below a limit value curve on the whole height:
(5) if the conclusion in the step (4) is negative, modifying the equipment size and the process parameters, and then performing the preliminary design of the fluidized bed in the step (1), drawing the volume ratio curve in the step (3) and judging in the step (4) again;
(6) if the conclusion in the step (4) is yes, judging whether a design optimization space exists;
(7) if the conclusion of the step (6) is negative, performing critical rechecking calculation on the design; and (4) if the conclusion of the step (6) is yes, modifying the equipment size and the process parameters, and performing the preliminary design of the fluidized bed in the step (1), the volume ratio curve drawing in the step (3) and the judgment in the steps (4) and (6) again.
In a preferred embodiment, the present invention provides a method for the critical safety design of a fluidized bed in the reprocessing of nuclear fuels, wherein in step (1), determining preliminary design parameters comprises determining parameters for uranium trioxide.
In a more preferred embodiment, the invention provides a method for designing critical safety of a fluidized bed in nuclear fuel reprocessing, wherein the parameters of the uranium trioxide include uranium trioxide density, particle size range.
In a preferred embodiment, the invention provides a critical safety design method for a fluidized bed in nuclear fuel reprocessing, wherein in step (1), the fluidized bed is preliminarily designed to include physical dimensions and process parameter design.
In a preferred embodiment, the invention provides a critical safety design method for fluidized beds in nuclear fuel reprocessing, wherein in step (2), the infinite cylinder critical calculation is to calculate the infinite multiplication factor k for infinite cylinder of different radii based on the determined preliminary design parametersinfIn the calculation, the outer side of the cylinder should comprise a water layer with a thickness of at least 20cm, and the inside of the cylinder is a mixture of water and uranium trioxide solids, so that the non-uniform effect of uranium trioxide and water should be fully considered, and the situation of different uranium trioxide filling rates or volume fractions should be considered.
In a preferred embodiment, the present invention provides a method for the critical safety design of a fluidized bed in nuclear fuel reprocessing, wherein in step (3),
according to the k corresponding to the different uranium trioxide filling rates under different infinite cylinder radiuses obtained in the step (2)infDetermining the minimum filling rate of uranium trioxide reaching a certain set critical safety limit value, so that under a certain radius, a corresponding filling rate of uranium trioxide can be obtained, and when the filling rate of uranium trioxide is less than or equal to the value, corresponding to the k of the cylinderinfLess than or equal to a set critical safety limit value; when the filling rate of the uranium trioxide is greater than the value, the corresponding cylinder kinfIt may be greater than a set critical safety limit,
according to the infinite cylinder radius and the uranium trioxide filling rate corresponding relation under the certain limit value obtained by calculation, the preliminary design of the fluidized bed is combined, the relation curve of the uranium trioxide filling rate under the cylinder radius corresponding to the fluidized bed at different heights is drawn, and meanwhile, according to the loading capacity preliminarily designed by the fluidized bed, the real filling rate of the uranium trioxide at different heights is drawn.
In a more preferred embodiment, the invention provides a critical safety design method for a fluidized bed in nuclear fuel post-treatment, wherein in the step (4), according to the drawn real filling rate of uranium trioxide at different heights under the preliminary design, the critical safety condition can be met if the drawn curves under the preliminary design are all positioned below the limit value curve in the non-geometric safety zone of the fluidized bed; if the threshold value is above the limit curve, the critical safety condition may not be satisfied.
In a preferred embodiment, the invention provides a critical safety design method for a fluidized bed in nuclear fuel post-treatment, wherein in step (6), according to the condition of the volume ratio curve, if there is a point which may not meet the critical safety limit value, namely the volume ratio curve is above the limit value curve, the equipment size or the process parameters need to be modified, and the volume ratio curve is redrawn for judgment; if the volume ratio curve is below the limit curve and is far from the limit curve, the design loading of uranium trioxide of the fluidized bed can be increased or the equipment size of the fluidized bed can be enlarged simultaneously, so that a more optimized 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), the critical re-checking calculation is to perform re-checking calculation on the finally formed design scheme, and when the stacking height of the uranium trioxide is lower than the height of a heating section, the geometric safety is realized; when the stacking height of the uranium trioxide is higher than the height of the heating section, rechecking the maximum k of the uranium trioxideeff。
The method has the advantages that by using the method for designing the critical safety of the fluidized bed in the nuclear fuel post-treatment, a large amount of design work can be saved under the condition of meeting the critical safety, and simultaneously, equipment designers can adjust and optimize the design size and the process parameters within a certain range.
The invention establishes a set of method for rapidly 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 relevant limit value and drawing a limit value curve, and can be used in the initial stage and the optimization design of the fluidized bed equipment. The method has the advantages that during equipment design, before a large amount of detailed calculation, guidance is provided for selection of specific values of a plurality of design parameters influencing critical safety of the fluidized bed, whether optimization space exists in current design 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 fluidized bed used in nuclear fuel reprocessing.
FIG. 2 is a flow chart of an exemplary critical safety design method of a fluidized bed in nuclear fuel reprocessing of the present invention.
FIG. 3 is a graph of the effective multiplication factor of an infinite cylinder in an embodiment.
FIG. 4 is a graph showing the design of the fluidized bed in the embodiment.
Detailed Description
The following further describes embodiments of the present invention with reference to the accompanying drawings.
An exemplary structure of a fluidized bed used in nuclear fuel reprocessing 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 chart of the critical safety design method of fluidized bed in nuclear fuel reprocessing of the present invention is shown in fig. 2, and includes the steps of:
(1) determining preliminary design parameters: parameters of the uranium trioxide, such as the density, the particle size range and the like of the uranium trioxide, are determined, and simultaneously, the fluidized bed is preliminarily designed, mainly the external dimension and the process parameters of the fluidized bed.
(2) And (3) performing infinite length cylinder critical calculation: calculating the infinite multiplication factor k of cylinders with different radii and infinite lengths according to the determined uranium trioxide parametersinfIn calculation, the outside of the cylinder should include a water layer of at least 20cm thickness, and the inside of the cylinder should be water and UO3Solid mixture, fully considering UO3And water non-uniformity effects, while taking into account different UOs3Filling ratio (volume fraction).
(3) Determining a corresponding limit relation: obtaining different UOs at different infinite cylinder radiuses according to the step (2)3K corresponding to filling rateinfDetermining the minimum UO to reach a set critical safety limit3Filling ratio such that, at a certain radius, a corresponding UO can be derived3Filling rate when UO3When the filling rate is less than or equal to the value, the k of the corresponding cylinderinfLess than or equal to a set critical safety limit when the UO is not exceeded3When the filling rate is larger than the value, the corresponding cylinder kinfPossibly above a set critical safety limit.
(4) Drawing a curve: according to the calculated infinite cylinder radius and UO under a certain limit value3The corresponding relation of filling rate, combined with the preliminary design of the fluidized bed, can draw the UO of the fluidized bed under the corresponding cylinder radius at different heights3The relation curve of the filling rate can draw the UO at different heights under the primary design according to the primary design loading of the fluidized bed3The true fill factor. If the curves drawn under the preliminary design are all below the limit curve in the non-geometric safety zone of the fluidized bed, the critical safety condition can be satisfiedIf the threshold value is above the limit curve, the critical safety condition may not be satisfied.
(5) Optimizing and designing: according to the condition of the curve, if there is a point which may not meet the critical safety limit, i.e. the preliminarily designed curve is located above the limit curve, the equipment size or the process parameters need to be modified, and the curve is redrawn for judgment. If both of them satisfy the critical safety limit, it can be determined whether to perform the optimum design, for example, if the preliminary design curve is below the limit curve and is far from the limit curve, the UO of the fluidized bed can be increased3The loading is designed or at the same time the equipment size of the fluidized bed is enlarged to achieve a more optimal design.
(6) And (4) rechecking calculation: and carrying out rechecking calculation on the finally formed scheme. When UO is present3When the stacking height is lower than the height of the heating section, the device is geometrically safe. When UO is present3When the stacking height is higher than the heating section height, rechecking the maximum keff。
The application of the above exemplary critical safety design method of the fluidized bed in nuclear fuel reprocessing 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 expanding section 3. Since the feed liquid enters from the heating section 1, the heating section 1 is thin and should be geometrically safe in order to meet the critical safety requirements. The main function of the expansion section 3 is UO3The product is filtered, and the size of the product is designed to be larger, so that the filtering effect is facilitated. The expansion section 3 and the heating section 1 are connected by a transition section 2. When the equipment is in normal operation, the UO3The whole space is filled with water, and the water content is low, so that the equipment can easily meet the critical safety condition; but when the flooding accident occurs, and the UO is not used3When the stacking is started from the bottom, the stacking height is higher than that of the heating section 1, and under the condition of departing from the geometric safety range, a critical risk exists, and a critical safety design is required.
Selecting UO according to the step (1)3The density was 7.5g/cm3The particle size range is 0.001-3cm, and the preliminary design parameters of the fluidized bed are as follows: the heating section 1 has a radius of 15cm and a height of 280cm, the transition section 2 has a height of 90cm, the expansion section 3 has a radius of 30cm and a height of 100cm, and the planned loading UO3The mass was 200 kg.
According to the step (2), calculating different UOs when the radius of the infinite cylinder is respectively 15cm, 17cm, 20cm, 25cm and 30cm3Effective proliferation factor of the system at fill rate, as shown in figure 3.
According to the step (3), selecting 0.9 as a critical safety limit value, and when the radius of the infinite cylinder is 15cm, the effective multiplication factor of the cylinder is not more than 0.9, so that the cylinder is geometrically safe, namely the design of the heating section of the fluidized bed meets the requirement; when the infinite length cylinder is larger than 15cm, the effective multiplication factor reaches the minimum UO of 0.93The filling rate corresponding relation is as follows: the filling rate was 0.29 at a radius of 17cm, 0.2 at a radius of 20cm, 0.16 at a radius of 25cm and 0.14 at a radius of 30 cm.
Respectively calculating 200kg of UO according to the step (4)3At the loading, the UO is accumulated at different heights3Filling rate, drawing curve and corresponding to the UO with radius at height3The fill rate limit is plotted as shown in fig. 4.
According to the step (5), when the stacking height is lower, the corresponding radius is smaller, UO3In a geometric safety zone, without regard to UO3The effect of fill rate; when the stacking height is increased, UO3When the discharge zone is out of the geometric safety zone, it can be seen from FIG. 4 that the load is 200kg of UO3When the design is carried out, the initial design curve is positioned below the limit value curve and has a certain distance, the design can be optimized by the scheme, the optimization is carried out by adopting a mode of changing process parameters, and the UO is improved3Load, known as UO3When the loading capacity is 330kg, the initial design curve is very close to the limit value curve, namely, 330kg of UO can be loaded3. Because the design adopts an infinite-length cylinder which is actually finite-length and the transition section 2 is a circular truncated cone, the effective multiplication factor of the circular truncated cone is smaller than that of the corresponding cylinder, the design scheme provided by the method is conservative.
According to the step (6), for UO with a load of 330kg3Performing critical rechecking calculation, and when the stacking height is lower than the height of the heating section, the method is geometrically safe; when the stacking height is higher than the heating section height, the maximum keffIn the order of 0.8117, is,and the critical safety requirement is met.
It will be apparent to those skilled in the art that various changes and modifications may be made in the present invention without departing from the spirit and scope of the invention. Thus, if such modifications and variations of the present invention fall within the scope of the claims of the present invention and their equivalents, the present invention is intended to include such modifications and variations. The above-described embodiments are merely illustrative of the present invention, and the present invention may be embodied in other specific forms or 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 should be construed to be included therein.
Claims (9)
1. A method for designing critical safety of a fluidized bed in nuclear fuel reprocessing, said method comprising the steps of:
(1) determining preliminary design parameters and carrying out preliminary design on the fluidized bed;
(2) and (3) performing infinite length cylinder critical calculation: performing infinite-length cylinder critical calculation on the basis of the preliminary design parameters determined in the step (1);
(3) and (3) drawing a volume ratio curve: 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 volume ratio curve of the volume ratio of the fluidized bed at different heights and corresponding limitation;
(4) judging whether the volume ratio curve obtained in the step (3) is below a limit value curve on the whole height:
(5) if the conclusion in the step (4) is negative, modifying the equipment size and the process parameters, and then performing the preliminary design of the fluidized bed in the step (1), drawing the volume ratio curve in the step (3) and judging in the step (4) again;
(6) if the conclusion in the step (4) is yes, judging whether a design optimization space exists;
(7) if the conclusion of the step (6) is negative, performing critical rechecking calculation on the design; and (4) if the conclusion of the step (6) is yes, modifying the equipment size and the process parameters, and performing the preliminary design of the fluidized bed in the step (1), the volume ratio curve drawing in the step (3) and the judgment in the steps (4) and (6) again.
2. The design method according to claim 1, wherein: in the step (1), determining the preliminary design parameters includes determining parameters of uranium trioxide.
3. The design method according to claim 2, wherein: the parameters of the uranium trioxide comprise uranium trioxide density and particle size range.
4. The design method according to claim 1, wherein: in the step (1), the preliminary design of the fluidized bed comprises the design of the overall dimension and the technological parameters.
5. The design method according to claim 1, wherein: in the step (2), the infinite length cylinder critical calculation is to calculate the infinite multiplication factor k of the infinite length cylinders with different radiuses according to the determined preliminary design parametersinfIn the calculation, the outer side of the cylinder should comprise a water layer with a thickness of at least 20cm, and the inside of the cylinder is a mixture of water and uranium trioxide solids, so that the non-uniform effect of uranium trioxide and water should be fully considered, and the situation of different uranium trioxide filling rates or volume fractions should be considered.
6. The design method according to claim 1, wherein: in the step (3), the step (c),
according to the k corresponding to the different uranium trioxide filling rates under different infinite cylinder radiuses obtained in the step (2)infDetermining the minimum uranium trioxide filling rate reaching a certain set critical safety limit value,
according to the infinite cylinder radius and the uranium trioxide filling rate corresponding relation under the certain limit value obtained by calculation, the preliminary design of the fluidized bed is combined, the relation curve of the uranium trioxide filling rate under the cylinder radius corresponding to the fluidized bed at different heights is drawn, and meanwhile, according to the loading capacity preliminarily designed by the fluidized bed, the real filling rate of the uranium trioxide at different heights is drawn.
7. The design method according to claim 6, wherein: in the step (4), according to the drawn real filling rate of uranium trioxide at different heights under the preliminary design, judging that the critical safety condition can be met if the drawn curves are all below the limit value curve in the non-geometric safety zone of the fluidized bed under the preliminary design; if the threshold value is above the limit curve, the critical safety condition may not be satisfied.
8. 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 the volume ratio curve is positioned above the limit curve, the equipment size or the process parameters need to be modified, and the volume ratio curve is redrawn for judgment; if both of them meet the critical safety limit, it can be determined whether to perform the optimization design.
9. The design method according to claim 1, wherein: in the step (7), the critical rechecking calculation is to recheck the finally formed design scheme, and when the stacking height of the uranium trioxide is lower than the height of the heating section, the uranium trioxide is geometrically safe; when the stacking height of the uranium trioxide is higher than the height of the heating section, rechecking the maximum k of the uranium trioxideeff。
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|---|---|---|---|---|
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|---|---|---|---|---|
| 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 |
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| Title |
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| 许明霞等: "压水堆铀燃料元件加工设施的核安全审评", 核安全 * |
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