CN1016471B - Monitoring method and device for shell fault in nuclear fuel components - Google Patents
Monitoring method and device for shell fault in nuclear fuel componentsInfo
- Publication number
- CN1016471B CN1016471B CN85109072A CN85109072A CN1016471B CN 1016471 B CN1016471 B CN 1016471B CN 85109072 A CN85109072 A CN 85109072A CN 85109072 A CN85109072 A CN 85109072A CN 1016471 B CN1016471 B CN 1016471B
- Authority
- CN
- China
- Prior art keywords
- water
- inert gas
- protective cover
- fuel assembly
- gas
- 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.)
- Expired
Links
Images
Classifications
-
- 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
Landscapes
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The present invention relates to a test for shell faults in nuclear fuel components through increasing air pressure in a shell by temperature rise. The present invention has the technical scheme that fission products are released when the shell is leaked, a mixture of water and inert gas is led into a protecting cover provided with a fuel component, the gas and the water are separated at the upper part of the protecting cover and are circulated in respective loops, and water solubility fission products and fission products in the gas are continuously checked.
Description
The present invention relates to nuclear fuel assembly is carried out the method and apparatus that cladding defect detects in sipping test and the nuclear fuel assembly.The present invention is specially adapted to the fuel assembly in the water-cooled adjustable type reactor, and a branch of fuel element is kept combining by one " skeleton " structure in this kind reactor.
Under some situation, fuel assembly must be through systematically checking.During fuel changes the outfit, those the width of cloth penetrated but and unspent assembly, before they reload reactor core, must be checked.Those are handled after a while in the pond of deactivating, and the assembly that exhausts fully must be checked before they are sent to aftertreatment factory.When carrying out aftertreatment and to those, having the assembly of sewing fuel element to dismantle, must significant care.
The most popular method of check involucrum sealing is to sob leakage method, promptly, by increasing temperature (heating, or utilize the remaining heat energy of fuel) increase the gaseous tension in the involucrum, emit so when having defective, will have fission product, at this moment go to measure: radioactivity or radioactive increase of skimming over the fluid that is examined the assembly involucrum.
Various fission product is overflowed by possible crack, and they comprise for example water-soluble products such as xenon 133 gases such as grade and iodine 131.After being verified assembly and having deactivated, then gas fission product is not a lot, promptly, its parameter is difficult to record with the in-line analysis method, can not provide the result who is of practical significance to the airflow analysis that scanned assembly, yet from other aspect, containing water-soluble fission product in this assembly (there is iodine 131 after the short time cooling, after the long period cooling cesium isotope 134 and 137 is arranged), the current that scanned this assembly by monitoring then can carry out fault detection.On the contrary, in the assembly that early the stage pulls down from reactor, have the fission product that the involucrum of defective spills, can not take to survey current method Direct Test fission product, and adopt the method for monitoring air-flow can obtain significative results.
In the prior art (No. the 2389202nd, French Patent (FRP)) of a check nuclear fuel assembly involucrum sealing, this assembly is inserted in the protective cover that is immersed in the protection pond; Assembly is heated to predetermined temperature; Make a certain gas stream through cavity, so that the gas fission product that will spill through possible fault location is carried secretly out; The radioactivity of protective cover fluid is left in detection.According to this patent, this protective cover has heating plate.So that with respect to desired temperature, those assemblies of low-residual thermal power of only having heat rapidly for those.This device also includes carries out check water sucking-off mechanism required, that skim over this assembly or effervescing gas drawing mechanism.
An object of the present invention is to provide a kind of method and apparatus, side by side or one after the other, be actually and measure water-soluble fission product and gas fission product content in real time.
So far, proposed aforesaid a kind of method, wherein, water and inert gas are introduced simultaneously and are constituted fluid, and separate when leaving cavity; Water and inert gas flow in widely different road separately, so that detect fission product soluble in water simultaneously and by the entrained fission product of gas.Water is preferably kept a constant water capacity in " widely different road ".Generally be that the gentle protective cover bottom of introducing respectively of water is mixed, and before this potpourri skims over assembly, make it to pass together a homogenizing filtrator.
A kind of sniffer that is made of the double-walled chamber is also proposed, the double-walled chamber vertically is immersed in the pond, and a fuel assembly protective cover is housed, the double-walled chamber comprises and is used for regulating the high mechanism of double-walled internal water, and the mechanism that makes water and gas flow, water and gas skim over assembly, and in radioassay mechanism, flow, wherein, this widely different road comprises water route and gas circuit, have universal component and said protective cover, this cover comprises that one is positioned at the homogenizing filtrator of its bottom and is used for water, gas are injected into the mechanism of the protective cover of filtrator below.
According to above-mentioned arrangement, can keep the reproduction of test status, more specifically say, be meant that relevant physical parameter (temperature, pressure, response time) can reproduce.By measured value and expansion thereof, can derive dynamics tension and relaxation mechanism, and can estimate defects property and size.
Explanation by the following specific embodiment that provides with way of example will help to understand better the present invention.
Fig. 1 is the overall pattern that the double-walled chamber that belongs to apparatus of the present invention is shown, and it is the cut-open view by the vertical plane of its axis;
Fig. 2 be illustrate bottom, double-walled chamber among Fig. 1 amplification the office cut-open view;
Fig. 3 is a fluid flow graph in the device;
Fig. 4 a, 4b and 4c are illustrated in the water surface in the double-walled chamber under several operation conditionss.
Referring to Fig. 1 and Fig. 2, this device comprises sobs Lou chamber (10), and that describes in No. the 2 389202, its general structure and the French Patent (FRP) is similar, has by water flowing and the widely different road of measurement that (12) and gas circuit (14) form.
Chamber (10) is supported by biological protection pond diapire, and for reaching this purpose adjustable support leg (16) is housed.Its external structure comprises garden cylindrical wall (18) and (20) of two vertical, coaxial, defines a ring cavity (22) between two barrels, by the base plate that is fastened in the substrate (24) two is connected together, and said substrate (24) connects together with leg.Plate (26) connects the upper end of tank wall (18) and (20).Opening (28) is made to have in the bottom of barrel (18) and (20), so that introduce Chi Shui.At the top of ring cavity (22) tap (30) is arranged, so that by flexible tubing (31) supply gas.
Plate (26) is used to support water tank (32), and this water tank is positioned at the top of protective cover (34), and protective cover is for dressing fuel assembly to be looked into (its shape simply is shown among Fig. 1).Water tank has a tap (33) of linking rising pipe (34 ').Link on the rigid tubular member (35) the water tank bottom, this member has one and upwards opens portion (36), it is tapered that this opens portion, to be convenient to introduce fuel assembly, this tubular element (35) also has a post-cone-shaped end (37) that points to downwards, has an axis hole (38) on this termination, a back up pad that is used to support fuel assembly, have the large scale center pit that the air-water potpourri is passed through, this back up pad is being supported by termination (37).
Termination (37) is used for by solution-air, to its purification, and before the inswept fuel assembly that is contained in the chamber (10) of solution-air solution-air is fully mixed.
There are a water inlet (42) and air intake opening (44) in the termination, and this air intake opening (44) leads to (see figure 2) in the narrow annular gap that is limited by the termination wall (37) that is parallel to each other and (46).Gas and airflow must pass near wall (46), arrive a filtrator-screen cloth (48) that has towards the protective cover passage, and this filtrator contains emulsification material (50), and it can for example be made by wire gauze.
Substrate (24) has a sealing unit, is used for when protective cover is in place Chi Shui and protective cover inside being separated.There is a stopper (52) this unit, and stopper is subjected to the acting force of a compression spring (54).Referring to Fig. 2, spring (54) is supported on the plate (56), by a bar slidably, plate (56) withstands on plate (24), when chamber (10) and protective cover are under the operating condition, the weight compression spring (54) of protective cover, spring (54) withstands used stopper, also different expansion situations is compensated in addition.If chamber (10) and protective cover are picked up, then the plate (56) that no longer supported at the bottom of the pond of spring compresses, when protective cover is picked up because stopper 52 no longer is crushed on its seat, so just protective cover be drained.
Protective cover also has a removable top (58) that is used to introduce and shift out fuel assembly.This top cover has one to be used for pipe core (60) and an air hole (62) (see figure 1) that gas is overflowed.In general, top cover is suitable for being opened by rectilinear motion, for example can be by means of the effect (see figure 3) of percussion hammer (64).
Tubular element (35) and wall (18) define a ring cavity (66), and as ring cavity (22), it can fill with water or gas (by tap (30), introduce band and press inert gas, water is discharged).Gas directly enters chamber (22) by this way.This gas enters space (66) by the hole (70) on wall (18) top.Water in space (22) and (66) by gas displacement after, reduced the thermal loss of fuel assembly, and made it under the effect of residual heat power, to be adjusted to and require temperature, and tested by probe (68) to Chi Shui.
Owing to act on the mutual balance of pressure of indoor and outdoor, do not need sealing.Anchorage force provides enough sealings, can prevent the mixing of water and Chi Zhongshui in the test loop.
At last, electrical heating elements can be installed in language if necessary on shield body, so that increase the heating rate of waiting to look into fuel assembly.
Be shown among Fig. 1 and Fig. 2 sob Lou the chamber can with loop shown in Figure 3 coupling.
According to Fig. 3, shown in the water route (12) on widely different road form a loop system, this system comprises that one makes water along arrow (f
0) direction round-robin pump (72).This pump and other element except that chamber (10), all be positioned at the top of the pond water surface, and for example be in the biological protection shell that constitutes by stereotype, this water route comprises: a well heater (74), be generally resistance-type, and a refrigeratory (76), by turning round with for example water generation heat interchange from external loop, the water of described external loop enters in the pond.Be used for control heater and refrigeratory, make it accurately to keep mechanism's (not shown) of predetermined temperature.Water route (12) also comprises a sample devices (78), because it can be in fact conventional, so it is not illustrated at this; And comprise that one is used for the radioactive equipment of continuous coverage.This equipment comprises a detector (80), is used for the radiant quantity that water sent of measurement count chamber (82), and this counting chamber (82) is limited by cut-off valve, so that hold back sampling known, the amount of remaining unchanged (water).Chamber (82) should be designed to such an extent that reduce the deposition of radioactive product, and its inside is through polishing generally speaking, and is made of anodised aluminium.
The checkout equipment in water route (12) is used to measure the radioactivity of water-soluble fission product, and they mainly are through deactivate iodine 131 in the assembly of time of a weak point, and through the cesium isotope in the assembly of a long storage period of deactivating 134 and 137.
At last, water route (12) also comprise another set of mechanism, are used for water route (12) are charged into softening water or make it emptying.
Gas circuit (14) between air intake opening (44) and pipe core (60) comprises successively: an expansion condenser (84) (or the system of an equivalence, for example one permeates exsiccator), be used to eliminate condensable vapours, and a device (86) that prevents liter waterborne, this device has a float control shut-off valve.Gas circuit (14) also comprises a suction pump (88), and a gamma radiation detector (90).When will be to gas sample, a collateral branch on this widely different road be used for pump short circuit (being represented by dotted lines it at Fig. 3).Can carry out following operation in proper order:
Air in the-extraction sampling bottle.
-sampling bottle that becomes vacuum is filled to flow through the gas of gas circuit.
To finding time and the filling operation of sampling bottle, easily be automated.This just makes from once sample other sampling, can keep the reproducibility of good physical parameter (pressure, volume, temperature), and can be owing to the operator produces any error.In addition, because the security of systematic automatic operation can be made sampling work without glove box.
Gamma radiation detector (90) can be conventional pattern.It is used for measuring independently the content of xenon 133 and Krypton 85.More particularly, can use a kind of detector (94) that has MCA with sodium iodide (NaI) scintillation crystal.By a gas exhaust valve (96), make when temperature raises, the leakage loss of restriction gas process air hole, thus make the loop more perfect.
At last, comprise in this loop by the heat-insulating circuit of space (22) and (66) adjusting.This adjusting is as required, and open valve (98) or (100) is respectively introduced or discharged inert gas (for example nitrogen) and realize.
Method of the present invention can be implemented by different order.Will be illustrated below, in most of the cases, as if desirable.
-when fuel assembly sobbing Lou in chamber (10) in place after, filling fluid in the widely different road, and make it to begin circulation.Water route (12) and sob Lou the chamber for example available pump (72) be filled with by circulation.Afterwards, introduce gas, (see that Fig. 4 a) overflows from air hole (62) until it by pipe (60).Bubble is overflowed through air hole (62), and this pore (62) is corresponding to a trap that limits pressure in the gas circuit (14).In case supercharging is set up, the operator discharges the gas of selecting quantity by valve (96), so that free-water level is elevated to predetermined altitude H(Fig. 4 b of pore (62) top).The height h of one 40 millimeter
0Can meet the demands in general.Under normal running temperature, this can be avoided gas to be overflowed by pore (62).Consequently, the contained water yield and tolerance will be kept constant substantially (not considering the gas that water discharged in the chamber (10)) in corresponding water route and the gas circuit.
Afterwards, water and gas are flowed in widely different road (12) and (14), simultaneously, control heater (74) makes the measured temperature of detector (68) reach predetermined value.When reaching working temperature, free water plane stability water surface when being lower than elder generation, for example h
1=15 millimeters (seeing Fig. 4 C).When the gas in widely different road (14) too much expands then since gas by being positioned at h
1The air hole of=0 below (62) is overflowed, and still makes inner and outer air pressure keep balance.
The gas, the aqueous mixtures that skim over fuel assembly are separated in the portion of opening (36) that is protected by the water protective layer, and air accumulation is on the top of water tank (32).Because air hole (62) is higher than tap (33), so gas can not enter water route (12), in other words, tap (33) is always being protected by the water protective layer.
In the water route, available probes (80) is carried out radiological measuring to the sampling one by one that is isolated in the counting chamber (82).Detector (80) is generally calibrated in the laboratory together with chamber (82), so that in time compare radioactivity Changing Pattern from the fission product of fuel assembly, and the Changing Pattern of dissolved matter.By the sampling of equipment (78), can carry out offline inspection one by one.
Equally, can in time evaluate with detector (94) the characteristic peaks of xenon 133 and krypton 86.But also can utilize equipment (78) sampling, carry out next step detection.
In view of by water being discharged space (22) and (66), protective cover and pond form heat and isolate, and use the well heater (74) by the regulating system energize, it perhaps may be refrigeratory (76), the control temperature when fuel assembly remains on a constant temperature, is carried out radioactivity survey.
When a fuel assembly detection finishes, it is removed, and replace another assembly.When top cover (58) when opening, is utilized a remote control clamp by percussion hammer (64), finish this by conventional methods and remove.
Between twice sipping test, transmission is skimmed over the loop of check assembly gas and remove, be necessary.But the residual radioactivity value that is detected in the loop surpasses predetermined acceptance threshold, then must systematically carry out removing work.
This removing can be carried out as follows:
-pressurized air that purifies is injected all gas circuit pipelines and sobs Lou chamber, afterwards, it is discharged to exhaust apparatus.
-by the pump (88) in the gas circuit, to being positioned at the outer air path part degassing of water, this program is useful especially to the pollution that condensed steam in the counting chamber of detector causes, and it can exempt the operation that the explorer count chamber is shifted out of having to from the pig of adorning it.
One is similar to device device (86), that prevent liter waterborne, usually is installed in to be passed in the pipeline of sobbing bottom, chamber Lou, so that prevent that water floods widely different road during the degassing.
Claims (10)
1, a kind of method that detects defective fuel element in the nuclear fuel assembly comprises the steps:
--fuel assembly is put into one sobs Lou protective cover (34),
--fuel assembly is warmed up to give fixed temperature, increasing the gaseous tension in this fuel assembly involucrum,
--survey the radioactivity that sword flows through the fluid of fuel assembly, it is characterized in that this method also comprises:
--in the bottom of described protective cover, form and introduce described fluid: the potpourri of water and inert gas, so that in this protective cover, be full of upwards round-robin water and noble gas mixtures,
--on described protective cover top, the water and the inert gas that break away from the potpourri of this cover are separated, and are made water separately and inert gas through the widely different road circulation of detection separately,
--water-soluble fission product in the widely different road of continuous monitoring water, and be distributed in fission product in the inert gas in the widely different road of gas, and
--above-mentioned inert gas and water are circulated once more, to form said mixture.
2, a kind of method according to claim 1 is characterized in that, keeps a constant water yield in the widely different road of water.
3, a kind of method according to claim 1, it is characterized in that, bottom by water and inert gas being introduced above-mentioned protective cover (34) respectively and with its mixing, and, the cover in them before cocycle and skimming over described fuel assembly, make it to cycle through together a homogenizing filtrator (48).
4, a kind of method according to claim 3 is characterized in that, described inert gas and water separate at a water tank above being arranged in protective cover, and inert gas is extracted out in tank top, and water in water tank is lower than on the height of water protective layer and extracts out.
5, a kind of method according to claim 1 is characterized in that, between detection period, described fuel assembly is kept a predetermined constant temperature.
6, a kind of method according to claim 1, it is characterized in that, the radioactivity of the fission product in the described inert gas is detected by a detector with NaI scintillation crystal (94) that has MCA, so that detect the radioxenon in the inert gas and the content of krypton respectively.
7, a kind of device that detects defective fuel jacket in the nuclear fuel assembly is characterized in that, this device comprises:
-one double-walled chamber (10) is immersed in the pond with the erection position,
It is indoor that-one protective cover (34) is installed in above-mentioned double-walled, is used for dressing one fuel assembly to be detected,
-one is used to regulate the valve (98,100) of the water level between above-mentioned double-walled chamber two walls (18,20), and
-be used to make water and inert gas along the path round-robin mechanism that comprises above-mentioned protective cover,
It is characterized in that, described cycling mechanism has widely different road of water and the widely different road of inert gas, in above-mentioned protective cover, have shared parts, described common component comprises that one is positioned at the homogenizing filtrator of described protective cover bottom, and water and inert gas are injected into water inlet (42) and air intake opening (44) in the protective cover of above-mentioned filtrator below, and
-be arranged in widely different road of described water and the widely different road of inert gas, be respectively applied for detect fission product content that the water-soluble fission product content of water and inert gas carry secretly, by detector (80), counting chamber (82), r detector (90) with have the measuring mechanism that the detector (94) of NaI scintillation crystal is formed.
8, a kind of device according to claim 7, it is characterized in that the bottom in the space between two walls of described double-walled chamber has the mechanism logical with the ditch, pond, be provided with at an upper portion thereof compressed gas introducing mechanism wherein, so that water is discharged, and cause the heat insulation of this protective cover.
9, a kind of device according to claim 7, it is characterized in that, described protective cover is being positioned at the water tank of inert gas-aqueous phase separation, have one and open portion (36), described water tank is provided with the pipe core (60) of an inert gas, and a tap (33) of extracting water out, this side outlet is positioned at than above-mentioned and opens on the lower height of portion's coboundary.
10, a kind of device according to claim 9 is characterized in that, described water tank is provided with an air hole (62), and this hole is positioned at than above-mentioned and opens on the higher height of portion's coboundary and above-mentioned water out (33).
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CN85109072A CN1016471B (en) | 1985-12-20 | 1985-12-20 | Monitoring method and device for shell fault in nuclear fuel components |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CN85109072A CN1016471B (en) | 1985-12-20 | 1985-12-20 | Monitoring method and device for shell fault in nuclear fuel components |
Publications (2)
Publication Number | Publication Date |
---|---|
CN85109072A CN85109072A (en) | 1987-06-24 |
CN1016471B true CN1016471B (en) | 1992-04-29 |
Family
ID=4796232
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
CN85109072A Expired CN1016471B (en) | 1985-12-20 | 1985-12-20 | Monitoring method and device for shell fault in nuclear fuel components |
Country Status (1)
Country | Link |
---|---|
CN (1) | CN1016471B (en) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
WO2018108138A1 (en) * | 2016-12-15 | 2018-06-21 | 中广核工程有限公司 | Method and system for detecting integrity of fuel element cladding of nuclear power station |
Families Citing this family (15)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN102237149B (en) * | 2010-04-22 | 2013-05-22 | 中国核动力研究设计院 | Underwater sipping apparatus for nuclear reactor spent fuel damage detection |
CN103021485B (en) * | 2011-09-23 | 2015-11-25 | 中国核动力研究设计院 | A kind of fuel assembly method for off-line leakage detection |
CN103247359A (en) * | 2013-04-23 | 2013-08-14 | 中国核动力研究设计院 | Online sipping detection system for integrity detection for fuel element cladding in nuclear power plant |
ES2691943T3 (en) * | 2014-01-16 | 2018-11-29 | Dominion Engineering, Inc. | System and method to improve the sensitivity of a sipping system |
EA030889B1 (en) * | 2015-08-14 | 2018-10-31 | Акционерное общество "Диаконт" | Device for checking the hermeticity of a nuclear reactor fuel assembly and method for carrying out such control |
CN106932504B (en) * | 2015-12-31 | 2019-05-10 | 中核建中核燃料元件有限公司 | Cold space equivalent water content measuring device in a kind of fuel rod |
CN105761768B (en) * | 2016-04-12 | 2017-07-25 | 苏州热工研究院有限公司 | The Performance Appraisal System of used in nuclear power station zircaloy fuel can integrality under LOCA operating modes |
CN106373623B (en) * | 2016-09-23 | 2017-10-31 | 岭东核电有限公司 | The detection method of nuclear power plant reactor residual heat removal system leakage |
FR3062946B1 (en) | 2017-02-15 | 2021-07-23 | Areva Np | DEVICE AND PROCEDURE FOR TIGHTNESS CONTROL BY WIPING A NUCLEAR FUEL ASSEMBLY |
CN106952670B (en) * | 2017-03-30 | 2018-05-25 | 中国核动力研究设计院 | A kind of device of on-line measurement fuel fission gas release pressure |
CN111354488B (en) * | 2018-12-21 | 2022-08-19 | 核动力运行研究所 | Nuclear fuel assembly vacuum off-line sipping detection device and method |
CN110911022A (en) * | 2019-10-14 | 2020-03-24 | 湖南汉华京电清洁能源科技有限公司 | Method for quantitatively detecting damage degree of fuel assembly |
CN110970143A (en) * | 2019-10-28 | 2020-04-07 | 湖南汉华京电清洁能源科技有限公司 | Method for detecting damage degree of fuel assembly |
CN111524620B (en) * | 2020-04-25 | 2021-10-19 | 西安交通大学 | Device and method for simulating tiny gas diffusion and collection at break opening in off-line sipping of fuel assembly |
CN112781802B (en) * | 2020-12-25 | 2023-04-18 | 辽宁红沿河核电有限公司 | Method and device for detecting sip leak equipment of fuel assembly on line |
-
1985
- 1985-12-20 CN CN85109072A patent/CN1016471B/en not_active Expired
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
WO2018108138A1 (en) * | 2016-12-15 | 2018-06-21 | 中广核工程有限公司 | Method and system for detecting integrity of fuel element cladding of nuclear power station |
Also Published As
Publication number | Publication date |
---|---|
CN85109072A (en) | 1987-06-24 |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
CN1016471B (en) | Monitoring method and device for shell fault in nuclear fuel components | |
US5544208A (en) | Method and apparatus for in situ detection of defective nuclear fuel assembly | |
JPS5853758B2 (en) | Method and device for detecting defective nuclear fuel elements | |
JPS62204141A (en) | Measuring device for gas dissolved into water | |
US6570949B2 (en) | Method and apparatus for testing nuclear reactor fuel assemblies | |
KR0154771B1 (en) | Method and device for detecting leaks trough the bushings of the cover of a nuclear reactor vessel | |
JPH08220285A (en) | Leakage detection apparatus of fuel aggregate of pressurized-water reactor | |
SE459291B (en) | DEVICE AND PROCEDURE FOR CONTROL OF THE CAPACITY OF THE CAPS | |
US20010019106A1 (en) | Process and devices for characterising ground water measurement points by distinguishing ground water from subterranean water accumulation | |
US5009835A (en) | Nuclear fuel rod helium leak inspection apparatus and method | |
EP0328408A2 (en) | Method and apparatus for obtaining a water sample from the core of a boiling water reactor | |
KR102372548B1 (en) | Analytical device for detecting fission products by measurement of radioactivity | |
CN216870312U (en) | Sediment infiltration test device | |
JPH0843582A (en) | System for detecting defective fuel rod in fuel assembly | |
CN114113483A (en) | Method and system for collecting products of fission products released by lead bismuth alloy | |
US4446097A (en) | Post accident analysis | |
RU2186429C2 (en) | Method and device for recharging fuel assembly of liquid-cooled reactor and for checking its tightness | |
EP0684612B1 (en) | Leak-detection system and method for detecting an individual leaking nuclear fuel rod having radioactive material leaking therefrom | |
CN217931285U (en) | Multifunctional composite measuring system for measuring filtering efficiency of different devices | |
JPH0151937B2 (en) | ||
CN117491124A (en) | Sample preparation device and sample preparation method for tritium sample in water | |
JP3289010B2 (en) | Shipping equipment | |
JPH07167983A (en) | Method and equipment for detecting leakage from atomic fuel reactor core | |
JPH0142400B2 (en) | ||
JP3140015B1 (en) | Shipping equipment |
Legal Events
Date | Code | Title | Description |
---|---|---|---|
C06 | Publication | ||
PB01 | Publication | ||
C10 | Entry into substantive examination | ||
SE01 | Entry into force of request for substantive examination | ||
C44 | Succession or assignment of patent right | ||
TR01 | Transfer of patent right |
Address after: Kolb Watt, France Patentee after: Framatome Address before: The French right Baiwa Patentee before: Framatome et Cogema dite "Fragmea" |
|
ASS | Succession or assignment of patent right |
Owner name: FRAMATOME Free format text: FORMER OWNER: PHAMASIWEOPUJOHN AMERICA CO., LTD. |
|
C13 | Decision | ||
GR02 | Examined patent application | ||
C14 | Grant of patent or utility model | ||
GR01 | Patent grant | ||
C17 | Cessation of patent right | ||
CX01 | Expiry of patent term |