CN101303906B - Reactor pressure vessel material irradiation control sample well type storing device - Google Patents
Reactor pressure vessel material irradiation control sample well type storing device Download PDFInfo
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- CN101303906B CN101303906B CN200810045430XA CN200810045430A CN101303906B CN 101303906 B CN101303906 B CN 101303906B CN 200810045430X A CN200810045430X A CN 200810045430XA CN 200810045430 A CN200810045430 A CN 200810045430A CN 101303906 B CN101303906 B CN 101303906B
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Abstract
The invention discloses a storage device of irradiation supervision test samples of reactor pressure vessel material. The device adopts a well-typed design and a storage well takes underground type, thus occupying no space of a thermal ventricular; a sample storage framework adopts a multi-level structure and makes full use of the space of the storage well, thus the number of the samples for storing is greatly increased and the cost is low. By adopting the storage device of the invention, the storage effect of the irradiation supervision test samples of reactor pressure vessel material can be easy to check and an excellent shielding is conducted on the irradiation of the specimen at the same time.
Description
Technical field
The present invention relates to a kind of test specimen save set, specifically is a kind of reactor pressure vessel material irradiation control sample well type save set.
Background technology
Reactor pressure vessel (RPV) is a non-exchange large component in the reactor, and its life-span has determined the life-span of entire reaction heap.For guaranteeing the reactor safety operation, must be with heap monitoring RPV material because neutron irradiation produces the practical extent that mechanical property worsens, checking designing and calculating and prediction accuracy, the accurately security of assessment reactor pressure vessel is simultaneously for the aging management and the life-span management of nuclear power station provide foundation from now on.Because the irradiation space in the reactor is very limited, irradiated sample quantity seldom, all require the disconnected sample after the RPV material irradiation control test and sample (as the bend specimen) long preservation that wouldn't test were tested or second development and utilization to the end of term in longevity, be processed into small sample as the sample that will break, be directly used in test or go into to pile irradiation again.
The hot of sample has increased the difficulty of its preservation behind the irradiation, and how the preservation that sample is carried out long-term safety is a very important problem.If storage method is improper, except making the sample rust corrosion, lose value, also may cause radioactive contamination to operating personnel, perform region.The present dry type save set that adopts is that sample is kept in the sample box in the hot cell, the temperature and humidity in the strict control hot cell, and feeding nitrogen reaches the purpose of preservation as blanket gas.But for the hot cell of high humidity, be difficult to control the temperature and humidity in the hot cell, the employing dry type is preserved costly and is difficult to reach ideal effect.
Summary of the invention
The objective of the invention is to: a kind of reactor pressure vessel material irradiation control sample well type save set is provided.This save set can make the metal material sample behind the irradiation, and rust corrosion not after long-time the placement still can satisfy the requirement of test or second development and utilization, is beneficial to the hot cell operation simultaneously.
The present invention is achieved in that
A kind of reactor pressure vessel material irradiation control sample save set, it is characterized in that: described save set is ground mo(u)ld bottom half well formula storage device, it comprises the carbon steel pipe of the bottom sealing of fixing with upper steel plate and lower steel plate, in carbon steel pipe, be placed with the stainless steel lining sleeve pipe as storing the borehole wall, in this lining pipe, be filled with the preservation medium, memory location is placed in this lining pipe and is immersed in and preserves in the medium, on the storage screen work, be welded with pallet, place sample box on the pallet, also be welded with a columned stainless steel shielding piece on the top that stores screen work, be welded with the storage well lid above the shielding slab at this, and on well lid, be welded with suspension ring.
Its supplementary features are:
Described storage screen work has multilayer;
Described pallet is circular, and its periphery has boss, and the bottom is a reticulate texture;
Described sample box has inside and outside two circle sample ducts, in the centre of sample box a tapped through hole is arranged, and is combined with screw rod.
Described storage screen work has 5 layers;
The inner ring of described sample box has 6 sample ducts, and there are 12 sample ducts the outer ring.
The preservation medium that is filled with in the described lining pipe is a polymethylphenyl siloxane fluid.
Described save set can have a plurality of, forms arranged, and casting cement is to the height concordant with carbon steel pipe between each save set.
Effect of the present invention is: because this device of preservation of the present invention adopts the design of well formula, store well and become the ground mo(u)ld bottom half, do not take the space, hot cell; The memory location frame is designed to multiple field, and the sample quantities of preservation is increased greatly, and with low cost; Adopt this device of preservation of the present invention, the preservation effect of pressure vessel material irradiation control sample is checked easily, simultaneously the radioactivity of sample has been carried out good shielding.
Description of drawings
Fig. 1 is a structural representation of the present invention.
Fig. 2 is a support holder structure synoptic diagram of the present invention.
Fig. 3 is a sample box structural representation of the present invention.
Fig. 4 is a storage well arrayed synoptic diagram of the present invention.
Among the figure: 1 is carbon steel pipe, and 2 is upper steel plate, and 3 is lower steel plate, and 4 is lining pipe, and 5 for storing screen work, 6 is pallet, and 7 is boss, and 8 is reticulate texture, and 9 is sample box, and 10 is the sample duct, 11 is tapped through hole, and 12 is screw rod, and 13 is shielding slab, and 14 for storing well lid, and 15 is suspension ring.
Embodiment
As shown in Figure 1, the present invention includes with upper steel plate 2 and lower steel plate 3 fixing the and carbon steel pipe 1 bottom sealing, in carbon steel pipe 1, put into the stainless steel lining sleeve pipe 4 of a bottom sealing as storing the boreholes wall, be filled with in the lining pipe 4 and preserve the medium polymethylphenyl siloxane fluid, must hunt leak before using, prevent to preserve the medium seepage.Storing screen work 5 and place in the lining pipe 4, and be immersed in the preservation medium, is to increase the space availability ratio that stores well, stores screen work 5 and has five layers; On storage screen work 5, be welded with pallet 6, on pallet 6, be placed with sample box 9; Also be welded with a columned stainless steel shielding piece 13 on the top that stores screen work 5, on shielding slab 13, be welded with and store well lid 14, store on the well lid 14 and be welded with suspension ring 15.
Pallet 6 is circle as shown in Figure 2, and periphery has boss 7, and the bottom is a reticulate texture 8, slides to prevent sample box 9, and reticulate texture 8 helps preserving flowing of medium when promoting storage screen work 5.
The present invention can have a plurality of arrangements as shown in Figure 4, forms the matrix array form.Casting cement is to the height concordant with carbon steel pipe 1 between each save set.A, b, c, d, e represent different lines among the figure, and A, B, C, D represent different rows, have 4 row, 5 row totally 20 save sets (storage well) among the figure.
During use, in the top of save set (storage well) hanging apparatus is installed, by the operating and remote controlling handle, the control crane carries out opening and closing to storing well lid 14 outside the hot cell.The sample that need are preserved is put into sample box 9, position with each sample of coordinate mark, by the remote-control handle control crane storage shelf of slinging, sample box 9 is put into the pallet 6 that stores on the screen work 5 with mechanical arm then, put back to and store screen work 5, sample all is immersed in the interior preservation medium polymethylphenyl siloxane fluid of well.As requested, regularly sample preservation situation is checked.
Claims (5)
1. reactor pressure vessel material irradiation control sample save set, it is characterized in that: described save set is ground mo(u)ld bottom half well formula storage device, it comprises the carbon steel pipe (1) of the bottom sealing of fixing with upper steel plate (2) and lower steel plate (3), in carbon steel pipe (1), be placed with stainless steel lining sleeve pipe (4) as storing the borehole wall, in lining pipe (4), be filled with the preservation medium, storage screen work (5) places in the lining pipe (4) and is immersed in preserves medium, on storage screen work (5), be welded with pallet (6), on pallet (6), be placed with sample box (9), also be welded with a columned stainless steel shielding piece (13) on the top that stores screen work (5), on shielding slab (13), be welded with and store well lid (14), store on the well lid (14) and be welded with suspension ring (15).
2. according to the described save set of claim 1, it is characterized in that: described storage screen work (5) has multilayer; Described pallet (6) is circular, and its periphery has boss (7), and the bottom is reticulate texture (8); Described sample box (9) has inside and outside two circle sample ducts (10), in the centre of sample box (9) tapped through hole (11) is arranged, and is combined with screw rod (12).
3. according to claim 1 or 2 described save sets, it is characterized in that: described storage screen work (5) has 5 layers; The inner ring of described sample box (9) has 6 sample ducts (10), and there are 12 sample ducts (10) outer ring.
4. according to the described save set of claim 1, it is characterized in that: the preservation medium in the described lining pipe (4) is a polymethylphenyl siloxane fluid.
5. according to the described save set of claim 1, it is characterized in that: described save set can have a plurality of, forms arranged, between each save set casting cement to the concordant height of carbon steel pipe (1).
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CN200810045430XA CN101303906B (en) | 2008-07-01 | 2008-07-01 | Reactor pressure vessel material irradiation control sample well type storing device |
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CN200810045430XA CN101303906B (en) | 2008-07-01 | 2008-07-01 | Reactor pressure vessel material irradiation control sample well type storing device |
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CN101303906A CN101303906A (en) | 2008-11-12 |
CN101303906B true CN101303906B (en) | 2011-08-10 |
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Families Citing this family (7)
Publication number | Priority date | Publication date | Assignee | Title |
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CN103971773B (en) * | 2014-05-26 | 2016-06-22 | 中国原子能科学研究院 | A kind of for the metal material irradiation devices in reactor |
CN106710656A (en) * | 2016-12-27 | 2017-05-24 | 中国石油天然气集团公司 | Source storage container structure used for small-diameter radioactive instrument |
CN110356716A (en) * | 2019-08-06 | 2019-10-22 | 中国原子能科学研究院 | Radioactive metal sample storage device |
CN112432968B (en) * | 2020-10-21 | 2022-08-30 | 中国核动力研究设计院 | Preparation method of irradiated reactor structure material thermal conductivity test sample and test sample box |
CN112304985A (en) * | 2020-10-21 | 2021-02-02 | 中国核动力研究设计院 | Preparation method of irradiated reactor structure material TEM sample and sample box |
CN112285141B (en) * | 2020-10-21 | 2022-09-13 | 中国核动力研究设计院 | Preparation method of irradiated reactor structural material SEM sample and sample box |
CN112366021B (en) * | 2020-11-09 | 2022-09-23 | 中国工程物理研究院核物理与化学研究所 | Equipment and method for realizing homogenization of reactor irradiation parameters |
Citations (3)
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US5793827A (en) * | 1995-09-22 | 1998-08-11 | General Electric Company | Material surveillance specimen holder for core shroud of boiling water reactor |
CN2861086Y (en) * | 2005-12-02 | 2007-01-24 | 天水星火机床有限责任公司 | Three-dimensional storage box |
CN101097177A (en) * | 2006-06-27 | 2008-01-02 | 中国原子能科学研究院 | Automation device for impact test after irradiation of nuclear power station pressure vessel steel |
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2008
- 2008-07-01 CN CN200810045430XA patent/CN101303906B/en active Active
Patent Citations (3)
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US5793827A (en) * | 1995-09-22 | 1998-08-11 | General Electric Company | Material surveillance specimen holder for core shroud of boiling water reactor |
CN2861086Y (en) * | 2005-12-02 | 2007-01-24 | 天水星火机床有限责任公司 | Three-dimensional storage box |
CN101097177A (en) * | 2006-06-27 | 2008-01-02 | 中国原子能科学研究院 | Automation device for impact test after irradiation of nuclear power station pressure vessel steel |
Non-Patent Citations (1)
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