GB1604746A - Method of producing fuel pins for nuclear reactors - Google Patents
Method of producing fuel pins for nuclear reactors Download PDFInfo
- Publication number
- GB1604746A GB1604746A GB23790/78A GB2379078A GB1604746A GB 1604746 A GB1604746 A GB 1604746A GB 23790/78 A GB23790/78 A GB 23790/78A GB 2379078 A GB2379078 A GB 2379078A GB 1604746 A GB1604746 A GB 1604746A
- Authority
- GB
- United Kingdom
- Prior art keywords
- getter material
- cladding tube
- fuel
- oxygen getter
- oxygen
- 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
- 239000000446 fuel Substances 0.000 title claims description 81
- 238000000034 method Methods 0.000 title claims description 30
- 239000000463 material Substances 0.000 claims description 65
- QVGXLLKOCUKJST-UHFFFAOYSA-N atomic oxygen Chemical compound [O] QVGXLLKOCUKJST-UHFFFAOYSA-N 0.000 claims description 64
- 239000001301 oxygen Substances 0.000 claims description 64
- 229910052760 oxygen Inorganic materials 0.000 claims description 64
- 238000005253 cladding Methods 0.000 claims description 54
- 239000011248 coating agent Substances 0.000 claims description 21
- 238000000576 coating method Methods 0.000 claims description 21
- 239000008188 pellet Substances 0.000 claims description 10
- 238000005260 corrosion Methods 0.000 claims description 8
- 230000007797 corrosion Effects 0.000 claims description 8
- RTAQQCXQSZGOHL-UHFFFAOYSA-N Titanium Chemical compound [Ti] RTAQQCXQSZGOHL-UHFFFAOYSA-N 0.000 claims description 6
- WABPQHHGFIMREM-UHFFFAOYSA-N lead(0) Chemical compound [Pb] WABPQHHGFIMREM-UHFFFAOYSA-N 0.000 claims description 6
- 229910052770 Uranium Inorganic materials 0.000 claims description 5
- XKRFYHLGVUSROY-UHFFFAOYSA-N Argon Chemical compound [Ar] XKRFYHLGVUSROY-UHFFFAOYSA-N 0.000 claims description 4
- VYZAMTAEIAYCRO-UHFFFAOYSA-N Chromium Chemical compound [Cr] VYZAMTAEIAYCRO-UHFFFAOYSA-N 0.000 claims description 4
- PWHULOQIROXLJO-UHFFFAOYSA-N Manganese Chemical compound [Mn] PWHULOQIROXLJO-UHFFFAOYSA-N 0.000 claims description 4
- QCWXUUIWCKQGHC-UHFFFAOYSA-N Zirconium Chemical compound [Zr] QCWXUUIWCKQGHC-UHFFFAOYSA-N 0.000 claims description 4
- 239000003990 capacitor Substances 0.000 claims description 4
- 229910052804 chromium Inorganic materials 0.000 claims description 4
- 239000011651 chromium Substances 0.000 claims description 4
- 230000000694 effects Effects 0.000 claims description 4
- 229910052735 hafnium Inorganic materials 0.000 claims description 4
- VBJZVLUMGGDVMO-UHFFFAOYSA-N hafnium atom Chemical compound [Hf] VBJZVLUMGGDVMO-UHFFFAOYSA-N 0.000 claims description 4
- 229910052748 manganese Inorganic materials 0.000 claims description 4
- 239000011572 manganese Substances 0.000 claims description 4
- 229910052758 niobium Inorganic materials 0.000 claims description 4
- 239000010955 niobium Substances 0.000 claims description 4
- GUCVJGMIXFAOAE-UHFFFAOYSA-N niobium atom Chemical compound [Nb] GUCVJGMIXFAOAE-UHFFFAOYSA-N 0.000 claims description 4
- 229910052715 tantalum Inorganic materials 0.000 claims description 4
- GUVRBAGPIYLISA-UHFFFAOYSA-N tantalum atom Chemical compound [Ta] GUVRBAGPIYLISA-UHFFFAOYSA-N 0.000 claims description 4
- 229910052719 titanium Inorganic materials 0.000 claims description 4
- 239000010936 titanium Substances 0.000 claims description 4
- 229910052726 zirconium Inorganic materials 0.000 claims description 4
- 229910052778 Plutonium Inorganic materials 0.000 claims description 3
- 239000011261 inert gas Substances 0.000 claims description 3
- OYEHPCDNVJXUIW-UHFFFAOYSA-N plutonium atom Chemical compound [Pu] OYEHPCDNVJXUIW-UHFFFAOYSA-N 0.000 claims description 3
- 239000012857 radioactive material Substances 0.000 claims description 3
- 230000002411 adverse Effects 0.000 claims description 2
- 229910052786 argon Inorganic materials 0.000 claims description 2
- 238000002844 melting Methods 0.000 claims description 2
- 230000008018 melting Effects 0.000 claims description 2
- 230000002265 prevention Effects 0.000 claims description 2
- 230000005855 radiation Effects 0.000 claims description 2
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 claims 2
- 230000004992 fission Effects 0.000 description 3
- DNYWZCXLKNTFFI-UHFFFAOYSA-N uranium Chemical compound [U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U][U] DNYWZCXLKNTFFI-UHFFFAOYSA-N 0.000 description 3
- 229910000619 316 stainless steel Inorganic materials 0.000 description 1
- ZCYVEMRRCGMTRW-UHFFFAOYSA-N 7553-56-2 Chemical compound [I] ZCYVEMRRCGMTRW-UHFFFAOYSA-N 0.000 description 1
- 229910052792 caesium Inorganic materials 0.000 description 1
- TVFDJXOCXUVLDH-UHFFFAOYSA-N caesium atom Chemical compound [Cs] TVFDJXOCXUVLDH-UHFFFAOYSA-N 0.000 description 1
- 150000001875 compounds Chemical class 0.000 description 1
- 238000001816 cooling Methods 0.000 description 1
- 230000001419 dependent effect Effects 0.000 description 1
- 239000001307 helium Substances 0.000 description 1
- 229910052734 helium Inorganic materials 0.000 description 1
- SWQJXJOGLNCZEY-UHFFFAOYSA-N helium atom Chemical compound [He] SWQJXJOGLNCZEY-UHFFFAOYSA-N 0.000 description 1
- 229910052740 iodine Inorganic materials 0.000 description 1
- 239000011630 iodine Substances 0.000 description 1
- 229910052751 metal Inorganic materials 0.000 description 1
- 239000002184 metal Substances 0.000 description 1
- 239000000203 mixture Substances 0.000 description 1
- 239000000126 substance Substances 0.000 description 1
- 229910052714 tellurium Inorganic materials 0.000 description 1
- PORWMNRCUJJQNO-UHFFFAOYSA-N tellurium atom Chemical compound [Te] PORWMNRCUJJQNO-UHFFFAOYSA-N 0.000 description 1
- 238000003466 welding Methods 0.000 description 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/02—Fuel elements
- G21C3/04—Constructional details
- G21C3/16—Details of the construction within the casing
- G21C3/20—Details of the construction within the casing with coating on fuel or on inside of casing; with non-active interlayer between casing and active material with multiple casings or multiple active layers
-
- C—CHEMISTRY; METALLURGY
- C23—COATING METALLIC MATERIAL; COATING MATERIAL WITH METALLIC MATERIAL; CHEMICAL SURFACE TREATMENT; DIFFUSION TREATMENT OF METALLIC MATERIAL; COATING BY VACUUM EVAPORATION, BY SPUTTERING, BY ION IMPLANTATION OR BY CHEMICAL VAPOUR DEPOSITION, IN GENERAL; INHIBITING CORROSION OF METALLIC MATERIAL OR INCRUSTATION IN GENERAL
- C23C—COATING METALLIC MATERIAL; COATING MATERIAL WITH METALLIC MATERIAL; SURFACE TREATMENT OF METALLIC MATERIAL BY DIFFUSION INTO THE SURFACE, BY CHEMICAL CONVERSION OR SUBSTITUTION; COATING BY VACUUM EVAPORATION, BY SPUTTERING, BY ION IMPLANTATION OR BY CHEMICAL VAPOUR DEPOSITION, IN GENERAL
- C23C4/00—Coating by spraying the coating material in the molten state, e.g. by flame, plasma or electric discharge
- C23C4/12—Coating by spraying the coating material in the molten state, e.g. by flame, plasma or electric discharge characterised by the method of spraying
- C23C4/126—Detonation spraying
-
- 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
- Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- Chemical & Material Sciences (AREA)
- Plasma & Fusion (AREA)
- Organic Chemistry (AREA)
- Materials Engineering (AREA)
- Mechanical Engineering (AREA)
- Metallurgy (AREA)
- Chemical Kinetics & Catalysis (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Other Surface Treatments For Metallic Materials (AREA)
- Inorganic Compounds Of Heavy Metals (AREA)
- Preventing Corrosion Or Incrustation Of Metals (AREA)
- Furnace Charging Or Discharging (AREA)
Description
(54) METHOD OF PRODUCING FUEL PINS FOR NUCLEAR REACTORS
(71) We, DORYOKURO KAKUNEN
RYO KAIHATSU JIGYODAN, of No. 9-13, 1-chome, Akasaka, Minato-ku, Tokyo,
Japan, a body corporate organised under the laws of Japan, do hereby declare the invention, for which we pray that a patent may be granted to us, and the method by which it is to be performed, to be particularly described in and by the following statement:
The present invention relates to a method of producing fuel pins for nuclear reactors.
The present invention will be described in detail with reference to a fuel pin for fuels for a fast breeder reactor but it can also be applied to such a pin for some other kinds of fuels.
Fuel pins for fast breeder reactors are generally produced by processing a mixture of oxides consisting of uranium and plutonium into so-called fuel pellets of a small columnar shape, placing in a stack the resulting fuel pellets in a long fuel cladding tube having a thin wall and a small diameter and made mainly of SUS 316 stainless steel, and welding in helium the fuel cladding tube to seal the same. When a fuel pin thus prepared is irradiated, the fuel pellets inserted therein produce nuclear fission products and excess oxygen. However, among these produced substances, evaporative fission products, such as tellurium, cesium and iodine and excess oxygen are moved into a gap between the fuel pellets and fuel cladding tube to form complicated compounds, which cause the inner surface of the fuel cladding tube to be corroded.
Since the output density of fuel pins in a fast breeder reactor is high, it is strictly necessary that the fuel cladding tube has a thin wall and a small diameter as mentioned above. When corrosion in the inner surface of such a fuel cladding tube progresses, the functions of the tube are not sufficiently performed, namely, the tube does not satisfactorily protect the fuel pellets against the cooling material or ceases to satisfactorily prevent the fission products from escaping from the fuel pins. This causes to pose a significant problem.
The greatest factor of the corrosion in the inner surface of fuel cladding tube is the excess oxygen released from the fuel pellets being irradiated, and the degree of corrosion is dependent upon a partial pressure of oxygen in the fuel cladding tube, which depepends upon the O/M ratio (oxygen/metal ratio) of the fuel material.
Therefore, when the partial pressure of oxygen is reduced to a suitable level, the corrosion in the inner surface of the fuel cladding tube can be prevented.
This has been already proven in irradiation tests, and the present invention has been made on the basis of the above described fact.
An object of the present invention is to provide a method of producing fuel pins for nuclear reactors, which method serves to reduce a partial pressure of oxygen in the fuel cladding tube being irradiated and prevent the inner surface thereof from being corroded.
Another object of the present invention is to provide a method of producing fuel pins for nuclear reactors, which method allows an improvement of the reliability and safety of fuel pins.
A further objocet of the present invention is to provide a method of producing fuel pins for nuclear reactors, which method is carried out without any equpiment required for handling radioactive materials.
Another object of the present invention is to provide a method of producing fuel pins for nuclear reactors, in which the fuel cladding tube is free from the influence of heat and is not deformed.
According to the present invention, there is provided a method of producing fuel pins for nuclear reactors, comprising the steps of disposing an oxygen getter material in a fuel cladding tube, applying to the oxygen getter material an electric current high enough to melt and scatter the oxygen getter material to thereby form a coating of the oxygen getter material on the inner surface ofte c ad- ding tube and inserting a fuel material in the cladding tube, said coating of the oxygen getter material capturing oxygen released from the fuel material inserted during irradiation, thereby preventing the inner surface of the cladding tube from being corroded.
The present invention will be described in detail with reference to the accompanying drawings.
Fig. 1 is a partly sectioned perspective view of a fuel cladding tube forming part of an embodiment of the present invention; and
Fig. 2 is a cross-sectioned view of a fuel cladding tube forming part of an embodiment of the present invention, showing an oxygen getter material coating produced in accordance with the method of the present invention.
A pair of electrodes 2a, 2b are disposed in a fuel cladding tube 1, and these electrodes 2a, 2b are connected via lead wire 3a, 3b, respectively, to a high electric current sup plying means (not shown) provided with a capacitor. The electrode 2a and lead wire 3a on one side are provided with a passage 4 therein through which a getter material is supplied. An oxygen getter material 6 in the form of wire is fed into the passage 4 from the outside by rolls 5, and is thus placed in alignment with the axis of the cladding tube 1, between the electrodes 2a, 2b. The electrode 2b may be provided with chuck means for grasping the oxygen getter material wire 6. The fuel cladding tube 1 contains therein an inert gas, such as argon. A high electric current applying and controlling means is operated to apply a high electric current to the oxygen getter material wire 6 from the capacitor through the lead wire 3a, 3b.
Thus, the linear oxygen getter material 6 is explosively melted and scattered in the directions of arrows as shown in Fig. 2 to form a coating 7 of the oxygen getter material on the inner surface of the fuel cladding tube 1. When titanium wire having a diameter of 0.3 mm is used as the oxygen getter material, the electric voltage of 5 of 7 KV is suitably applied to the wire.
The oxygen getter material which can be used in the present invention includes, for example, titanium, zirconium, hafnium, chromium, niobium, tantalum, manganese and uranium. The thickness of the coating of oxygen getter material formed on the inner surface of the cladding tube is varied depending upon the types of the oxygen getter material in use, but 10-20,um is sufficient. The thickness of the coating of oxygen getter material may be easily determined with reference to the difference between the amount of oxygen able to be released from the fuel material during irradiation and the amount of oxygen unable to produce corrosion of the inner surface of the fuel cladding tube during irradiation, and also with reference to the weight of the fuel pellets. Until the O/M ratio is lowered to about 1.94 in the case of plutonium, the oxygen resulting in the course of irradiation should be captured by the oxygen getter material to avoid the corrosion of the inner surface of the cladding tube. In order to obtain a desired thickness of the coating of the oxygen getter material, the material to be subjected or the number of melting and scattering operations is suitably selected. Also, the porosity of the coating can be suitably controlled by controlling the voltage to be applied to the wire.
According to the method of the present invention constituted as described above, a fuel cladding tube which permits preventing the inner surface thereof from being corroded with radiation can be obtained. Consequently, various excellent effects which will be described below can be produced.
The reliability and safety of fuel pins can be improved. Equipment required for handling radioactive materials is not needed at all since no such materials are used in the method of the present invention and therefore the processing cost can be reduced to a great extent. The fuel cladding tube is free from the influence of heat and never deformed and thus, it is unnecessary that the tube be subjected to an additional treatment after the inner surface thereof has been processed. The processing rate is very high and the thickness of the coating to be formed on the inner surface of the fuel cladding tube can be easily controlled. The apparatus for practicing this method can be easily automated. The present invention may be a lied to the prevention of adverse mutual effects of the fuel cladding tube and fuel pellets by suitably selecting the oxygen getter material.
WHAT WE CLAIM IS:
1. A method of producing fuel pins for nuclear reactors, comprising the steps of disposing an oxygen getter material in a fuel cladding tube, applying to the oxygen getter material an electric current high enough to melt and scatter the oxygen getter material thereby to form a coating of the oxygen getter material on the inner surface of the cladding tube and inserting a fuel material in the cladding tube, said coating of the oxygen getter material capturing oxygen released from the fuel material during irradiation thereby preventing the inner surface of the cladding tube from being corroded.
2. A method according to claim 1, in which the oxygen getter material is wire shaped and is disposed in the fuel cladding tube in alignment with an axis of the fuel cladding tube.
3. A method according to claim 1 or 2, in which the oxygen getter material is selected from titanium, zirconium, hafnium, chromium, niobium, tantalum, manganese and uranium.
**WARNING** end of DESC field may overlap start of CLMS **.
Claims (7)
1. A method of producing fuel pins for nuclear reactors, comprising the steps of disposing an oxygen getter material in a fuel cladding tube, applying to the oxygen getter material an electric current high enough to melt and scatter the oxygen getter material thereby to form a coating of the oxygen getter material on the inner surface of the cladding tube and inserting a fuel material in the cladding tube, said coating of the oxygen getter material capturing oxygen released from the fuel material during irradiation thereby preventing the inner surface of the cladding tube from being corroded.
2. A method according to claim 1, in which the oxygen getter material is wire shaped and is disposed in the fuel cladding tube in alignment with an axis of the fuel cladding tube.
3. A method according to claim 1 or 2, in which the oxygen getter material is selected from titanium, zirconium, hafnium, chromium, niobium, tantalum, manganese and uranium.
4. A method according to any preceding
claim, in which the fuel cladding tube contains therein an inert gas.
5. A method according to any preceding claim, in which the coating of oxygen getter material formed has a thickness of from 10 to 20 um.
6. A method of producing fuel pins for nuclear reactors substantially as herein described with reference to the accompanying drawings.
7. A fuel pin when produced by a method according to any one of claims 1 to 6.
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP6815477A JPS543698A (en) | 1977-06-09 | 1977-06-09 | Internal production method of reactor fuel cladding tube |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| GB1604746A true GB1604746A (en) | 1981-12-16 |
Family
ID=13365531
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| GB23790/78A Expired GB1604746A (en) | 1977-06-09 | 1978-05-30 | Method of producing fuel pins for nuclear reactors |
Country Status (4)
| Country | Link |
|---|---|
| JP (1) | JPS543698A (en) |
| DE (1) | DE2825403C2 (en) |
| FR (1) | FR2394146A1 (en) |
| GB (1) | GB1604746A (en) |
Families Citing this family (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4751044A (en) * | 1985-08-15 | 1988-06-14 | Westinghouse Electric Corp. | Composite nuclear fuel cladding tubing and other core internal structures with improved corrosion resistance |
| FR2695507B1 (en) * | 1992-09-10 | 1994-10-07 | Pechiney Uranium | Sheath for nuclear fuel coated with a fission product trap and method for obtaining it. |
| FR3003991A1 (en) | 2013-03-29 | 2014-10-03 | Commissariat Energie Atomique | COMBUSTIBLE PEN COMPRISING AN ANTI-CORROSION ELEMENT BASED ON AN ELEMENT BELONGING TO THE PLATINUM GROUP |
Family Cites Families (15)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| BE624942A (en) * | 1962-11-16 | |||
| GB1081512A (en) * | 1965-01-22 | 1967-08-31 | Atomic Energy Authority Uk | Improvements in or relating to nuclear fuel elements |
| US3427222A (en) * | 1965-10-15 | 1969-02-11 | Westinghouse Electric Corp | Nuclear fuel elements |
| US3639150A (en) * | 1968-07-25 | 1972-02-01 | Toshiro Suhara | Electric explosion metal spraying for substrate |
| DE2127240A1 (en) * | 1970-06-11 | 1971-12-16 | Combustion Eng | Nuclear reactor fuel rod - of fuel tablets stacked in sheathing tube - with metal lining layer |
| JPS507996A (en) * | 1973-05-30 | 1975-01-27 | ||
| JPS5230157B2 (en) * | 1973-11-02 | 1977-08-05 | ||
| FR2285681A1 (en) * | 1974-09-20 | 1976-04-16 | Commissariat Energie Atomique | PROCESS FOR PROTECTING THE DUCTS OF NUCLEAR FUEL ELEMENTS |
| GB1525717A (en) * | 1974-11-11 | 1978-09-20 | Gen Electric | Nuclear fuel elements |
| ES440476A1 (en) * | 1974-11-11 | 1977-09-01 | Gen Electric | Nuclear fuel elements |
| US4022662A (en) * | 1974-11-11 | 1977-05-10 | General Electric Company | Nuclear fuel element having a metal liner and a diffusion barrier |
| SE7511582L (en) * | 1974-11-11 | 1976-05-12 | Gen Electric | IMPROVED ENCLOSURE FOR NUCLEAR FUEL ELEMENT |
| GB1528142A (en) * | 1974-11-11 | 1978-10-11 | Gen Electric | Nuclear fuel elements |
| US4029545A (en) * | 1974-11-11 | 1977-06-14 | General Electric Company | Nuclear fuel elements having a composite cladding |
| GB1453256A (en) * | 1975-05-07 | 1976-10-20 | Kawasaki Heavy Ind Ltd | Method of treating a sliding surface suing wire-explosion coating |
-
1977
- 1977-06-09 JP JP6815477A patent/JPS543698A/en active Pending
-
1978
- 1978-05-30 GB GB23790/78A patent/GB1604746A/en not_active Expired
- 1978-06-08 FR FR787817129A patent/FR2394146A1/en active Pending
- 1978-06-09 DE DE2825403A patent/DE2825403C2/en not_active Expired
Also Published As
| Publication number | Publication date |
|---|---|
| DE2825403C2 (en) | 1985-08-08 |
| JPS543698A (en) | 1979-01-11 |
| FR2394146A1 (en) | 1979-01-05 |
| DE2825403A1 (en) | 1978-12-21 |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PS | Patent sealed [section 19, patents act 1949] | ||
| PE20 | Patent expired after termination of 20 years |
Effective date: 19980529 |