SE469997B - Fuel rod for nuclear reactor - Google Patents
Fuel rod for nuclear reactorInfo
- Publication number
- SE469997B SE469997B SE9200584A SE9200584A SE469997B SE 469997 B SE469997 B SE 469997B SE 9200584 A SE9200584 A SE 9200584A SE 9200584 A SE9200584 A SE 9200584A SE 469997 B SE469997 B SE 469997B
- Authority
- SE
- Sweden
- Prior art keywords
- zirconium
- ppm
- less
- beryllium
- fuel rod
- Prior art date
Links
- 239000000446 fuel Substances 0.000 title claims abstract description 7
- QCWXUUIWCKQGHC-UHFFFAOYSA-N Zirconium Chemical compound [Zr] QCWXUUIWCKQGHC-UHFFFAOYSA-N 0.000 claims abstract description 16
- 229910052726 zirconium Inorganic materials 0.000 claims abstract description 16
- 229910052790 beryllium Inorganic materials 0.000 claims abstract description 13
- ATBAMAFKBVZNFJ-UHFFFAOYSA-N beryllium atom Chemical compound [Be] ATBAMAFKBVZNFJ-UHFFFAOYSA-N 0.000 claims abstract description 13
- 239000011241 protective layer Substances 0.000 claims abstract description 10
- 229910045601 alloy Inorganic materials 0.000 claims abstract description 4
- 239000000956 alloy Substances 0.000 claims abstract description 4
- 239000003758 nuclear fuel Substances 0.000 claims abstract description 4
- 241000233866 Fungi Species 0.000 claims description 2
- 239000012535 impurity Substances 0.000 claims description 2
- 239000000126 substance Substances 0.000 claims description 2
- 238000005253 cladding Methods 0.000 claims 4
- 238000005336 cracking Methods 0.000 claims 1
- 230000007797 corrosion Effects 0.000 abstract description 5
- 238000005260 corrosion Methods 0.000 abstract description 5
- 238000007789 sealing Methods 0.000 abstract 4
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 7
- XEEYBQQBJWHFJM-UHFFFAOYSA-N Iron Chemical compound [Fe] XEEYBQQBJWHFJM-UHFFFAOYSA-N 0.000 description 6
- 229910001093 Zr alloy Inorganic materials 0.000 description 6
- PXHVJJICTQNCMI-UHFFFAOYSA-N Nickel Chemical compound [Ni] PXHVJJICTQNCMI-UHFFFAOYSA-N 0.000 description 4
- QVGXLLKOCUKJST-UHFFFAOYSA-N atomic oxygen Chemical compound [O] QVGXLLKOCUKJST-UHFFFAOYSA-N 0.000 description 4
- 239000001301 oxygen Substances 0.000 description 4
- 229910052760 oxygen Inorganic materials 0.000 description 4
- VYZAMTAEIAYCRO-UHFFFAOYSA-N Chromium Chemical compound [Cr] VYZAMTAEIAYCRO-UHFFFAOYSA-N 0.000 description 3
- ATJFFYVFTNAWJD-UHFFFAOYSA-N Tin Chemical compound [Sn] ATJFFYVFTNAWJD-UHFFFAOYSA-N 0.000 description 3
- 239000000654 additive Substances 0.000 description 3
- 230000000996 additive effect Effects 0.000 description 3
- 229910052804 chromium Inorganic materials 0.000 description 3
- 239000011651 chromium Substances 0.000 description 3
- 229910052742 iron Inorganic materials 0.000 description 3
- 239000010410 layer Substances 0.000 description 3
- FRWYFWZENXDZMU-UHFFFAOYSA-N 2-iodoquinoline Chemical compound C1=CC=CC2=NC(I)=CC=C21 FRWYFWZENXDZMU-UHFFFAOYSA-N 0.000 description 2
- IJGRMHOSHXDMSA-UHFFFAOYSA-N Atomic nitrogen Chemical compound N#N IJGRMHOSHXDMSA-UHFFFAOYSA-N 0.000 description 2
- 238000000137 annealing Methods 0.000 description 2
- LTPBRCUWZOMYOC-UHFFFAOYSA-N beryllium oxide Inorganic materials O=[Be] LTPBRCUWZOMYOC-UHFFFAOYSA-N 0.000 description 2
- 239000003344 environmental pollutant Substances 0.000 description 2
- 229910052759 nickel Inorganic materials 0.000 description 2
- OOAWCECZEHPMBX-UHFFFAOYSA-N oxygen(2-);uranium(4+) Chemical compound [O-2].[O-2].[U+4] OOAWCECZEHPMBX-UHFFFAOYSA-N 0.000 description 2
- 231100000719 pollutant Toxicity 0.000 description 2
- FCTBKIHDJGHPPO-UHFFFAOYSA-N uranium dioxide Inorganic materials O=[U]=O FCTBKIHDJGHPPO-UHFFFAOYSA-N 0.000 description 2
- 229910000967 As alloy Inorganic materials 0.000 description 1
- 229910000952 Be alloy Inorganic materials 0.000 description 1
- ZOXJGFHDIHLPTG-UHFFFAOYSA-N Boron Chemical compound [B] ZOXJGFHDIHLPTG-UHFFFAOYSA-N 0.000 description 1
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 description 1
- RYGMFSIKBFXOCR-UHFFFAOYSA-N Copper Chemical compound [Cu] RYGMFSIKBFXOCR-UHFFFAOYSA-N 0.000 description 1
- FYYHWMGAXLPEAU-UHFFFAOYSA-N Magnesium Chemical compound [Mg] FYYHWMGAXLPEAU-UHFFFAOYSA-N 0.000 description 1
- PWHULOQIROXLJO-UHFFFAOYSA-N Manganese Chemical compound [Mn] PWHULOQIROXLJO-UHFFFAOYSA-N 0.000 description 1
- ZOKXTWBITQBERF-UHFFFAOYSA-N Molybdenum Chemical compound [Mo] ZOKXTWBITQBERF-UHFFFAOYSA-N 0.000 description 1
- XUIMIQQOPSSXEZ-UHFFFAOYSA-N Silicon Chemical compound [Si] XUIMIQQOPSSXEZ-UHFFFAOYSA-N 0.000 description 1
- RTAQQCXQSZGOHL-UHFFFAOYSA-N Titanium Chemical compound [Ti] RTAQQCXQSZGOHL-UHFFFAOYSA-N 0.000 description 1
- 229910052770 Uranium Inorganic materials 0.000 description 1
- 239000012790 adhesive layer Substances 0.000 description 1
- 238000005275 alloying Methods 0.000 description 1
- XAGFODPZIPBFFR-UHFFFAOYSA-N aluminium Chemical compound [Al] XAGFODPZIPBFFR-UHFFFAOYSA-N 0.000 description 1
- 229910052782 aluminium Inorganic materials 0.000 description 1
- 230000015572 biosynthetic process Effects 0.000 description 1
- 229910052796 boron Inorganic materials 0.000 description 1
- 229910052793 cadmium Inorganic materials 0.000 description 1
- BDOSMKKIYDKNTQ-UHFFFAOYSA-N cadmium atom Chemical compound [Cd] BDOSMKKIYDKNTQ-UHFFFAOYSA-N 0.000 description 1
- 239000002775 capsule Substances 0.000 description 1
- 229910052799 carbon Inorganic materials 0.000 description 1
- 239000007795 chemical reaction product Substances 0.000 description 1
- 239000010941 cobalt Substances 0.000 description 1
- 229910017052 cobalt Inorganic materials 0.000 description 1
- GUTLYIVDDKVIGB-UHFFFAOYSA-N cobalt atom Chemical compound [Co] GUTLYIVDDKVIGB-UHFFFAOYSA-N 0.000 description 1
- 239000002131 composite material Substances 0.000 description 1
- 239000002826 coolant Substances 0.000 description 1
- 229910052802 copper Inorganic materials 0.000 description 1
- 239000010949 copper Substances 0.000 description 1
- 230000007547 defect Effects 0.000 description 1
- 238000005538 encapsulation Methods 0.000 description 1
- 235000012438 extruded product Nutrition 0.000 description 1
- 229910052735 hafnium Inorganic materials 0.000 description 1
- VBJZVLUMGGDVMO-UHFFFAOYSA-N hafnium atom Chemical compound [Hf] VBJZVLUMGGDVMO-UHFFFAOYSA-N 0.000 description 1
- 238000010438 heat treatment Methods 0.000 description 1
- 239000001257 hydrogen Substances 0.000 description 1
- 229910052739 hydrogen Inorganic materials 0.000 description 1
- 125000004435 hydrogen atom Chemical class [H]* 0.000 description 1
- 229910052749 magnesium Inorganic materials 0.000 description 1
- 239000011777 magnesium Substances 0.000 description 1
- 229910052748 manganese Inorganic materials 0.000 description 1
- 239000011572 manganese Substances 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 239000000203 mixture Substances 0.000 description 1
- 229910052750 molybdenum Inorganic materials 0.000 description 1
- 239000011733 molybdenum Substances 0.000 description 1
- 229910052758 niobium Inorganic materials 0.000 description 1
- 239000010955 niobium Substances 0.000 description 1
- GUCVJGMIXFAOAE-UHFFFAOYSA-N niobium atom Chemical compound [Nb] GUCVJGMIXFAOAE-UHFFFAOYSA-N 0.000 description 1
- 229910052757 nitrogen Inorganic materials 0.000 description 1
- 230000003647 oxidation Effects 0.000 description 1
- 238000007254 oxidation reaction Methods 0.000 description 1
- 239000002245 particle Substances 0.000 description 1
- 238000001953 recrystallisation Methods 0.000 description 1
- 238000005096 rolling process Methods 0.000 description 1
- 229910052710 silicon Inorganic materials 0.000 description 1
- 239000010703 silicon Substances 0.000 description 1
- 239000010936 titanium Substances 0.000 description 1
- 229910052719 titanium Inorganic materials 0.000 description 1
- WFKWXMTUELFFGS-UHFFFAOYSA-N tungsten Chemical compound [W] WFKWXMTUELFFGS-UHFFFAOYSA-N 0.000 description 1
- 229910052721 tungsten Inorganic materials 0.000 description 1
- 239000010937 tungsten Substances 0.000 description 1
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 description 1
Classifications
-
- C—CHEMISTRY; METALLURGY
- C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
- C22C—ALLOYS
- C22C16/00—Alloys based on zirconium
-
- 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
-
- 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)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Materials Engineering (AREA)
- Mechanical Engineering (AREA)
- Metallurgy (AREA)
- Organic Chemistry (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Physical Vapour Deposition (AREA)
Abstract
Description
469 997 z resistens mot av spänningskorrosion orsakade skador. I skyddsskiktet där en legeringstillsats däremot föreligger som'utskiljd fas kan utskiljda partik- lar utgöra inhomogeniteter, där spänningskorrosion kan initiera sprickbild- ning. 469 997 z resistance to stress corrosion damage. In the protective layer where a alloying additive, on the other hand, is present as the separated phase can separate particles constitute inhomogeneities, where stress corrosion can initiate crack formation. ning.
Den föreliggande uppfinningen baserar sig på insikten att väsentliga för- bättringar kan uppnås hos ett skyddsskikt genom användning av beryllium som legeringstillsats till zirkonium. Genom att beryllium har en större affini- tet till syre än zirkonium kommer beryllium i vatten eller vattenånga att bilda berylliumoxid ovanpå zirkonium-beryllium-legeringen. Berylliumoxiden ger därvid ett tätt och vidhäftande skikt, som effektivt skyddar kapslings- rörets insida mot vidare oxidation/korrosion. Vatten eller vattenånga kan vid defekter i kapslingsröret strömma in i kapslingsrörets inre. Användning av beryllium medför också att risken för spänningskorrosion reduceras på grund av att beryllium är en löslig legeringstillsats. Beryllium har vidare en mycket låg tendens att absorbera termiska neutroner.The present invention is based on the insight that essential Improvements can be achieved in a protective layer by using beryllium as alloy additive to zirconium. Because beryllium has a greater affinity for to oxygen other than zirconium, beryllium in water or water vapor will form beryllium oxide on top of the zirconium-beryllium alloy. Beryllium oxide thereby providing a dense and adhesive layer, which effectively protects the enclosure the inside of the pipe against further oxidation / corrosion. Water or water vapor can in case of defects in the enclosure pipe flow into the interior of the enclosure pipe. Use of beryllium also means that the risk of stress corrosion is reduced due to the fact that beryllium is a soluble alloy additive. Beryllium has further a very low tendency to absorb thermal neutrons.
Det som kännetecknar den föreliggande uppfinningen är att skyddsskiktet på kapslingsrörets invändiga yta består av zirkonium innehållande 0,1-5 vikt- procent beryllium och att övriga i zirkoniumet i skyddsskiktet ingående ämnen utgöres av i zirkoniumsvamp av rektorkvalitet normalt förekommande föroreningar. Normala halter av föroreningarna i zirkonium av sådan kvali- tet är för syre 200-1200 ppm, för aluminium 75 ppm eller mindre, för bor 0,4 ppm eller mindre, för kadmium 0,4 ppm eller mindre, för kol 270 ppm eller mindre, för krom 200 ppm eller mindre, för kobolt 20 ppm eller mindre, för koppar 50 ppm eller mindre, för hafnium 100 ppm eller mindre, för väte 25 ppm eller mindre, för järn 1500 ppm eller mindre, för magnesium ppm eller mindre, för mangan 50 ppm eller mindre, för molybden 50 ppm eller mindre, för nickel 70 ppm eller mindre, för niob 100 ppm eller mindre, för kväve 80 ppm eller mindre, för kisel 120 ppm eller mindre, för tenn 50 ppm eller mindre, för volfram 100 ppm eller mindre, för titan 50 ppm eller mindre samt för uran 3,5 ppm eller mindre. Företrädesvis innehåller zirkoniumet i skyddsskiktet 0,1-2 viktprocent beryllium.What characterizes the present invention is that the protective layer on the inner surface of the enclosure tube consists of zirconium containing 0.1-5 percent beryllium and that the rest of the zirconium in the protective layer is included substances are normally found in zirconium fungi of principal quality pollutants. Normal levels of zirconium impurities of such quality for oxygen is 200-1200 ppm, for aluminum 75 ppm or less, for boron 0.4 ppm or less, for cadmium 0.4 ppm or less, for carbon 270 ppm or less, for chromium 200 ppm or less, for cobalt 20 ppm or less, for copper 50 ppm or less, for hafnium 100 ppm or less, for hydrogen 25 ppm or less, for iron 1500 ppm or less, for magnesium ppm or less, for manganese 50 ppm or less, for molybdenum 50 ppm or less, for nickel 70 ppm or less, for niobium 100 ppm or less, for nitrogen 80 ppm or less, for silicon 120 ppm or less, for tin 50 ppm or less, for tungsten 100 ppm or less, for titanium 50 ppm or less and for uranium 3.5 ppm or less. Preferably the zirconium in the protective layer contains 0.1-2% by weight of beryllium.
Tjockleken hos skyddsskiktet uppgår lämpligen till 0,0Ä-0,32 mm och före- trädesvis till 0,05-0,1 mm. Skiktets tjocklek utgör lämpligen 5-40 % och företrädesvis 5-15 % av kapslingsrörets väggtjocklek. 3 469 997 Materialet i kapslingsröret har beskrivits inledningsvis. Till detta kan läggas att för Zircaloy 2 är sammansättningen 1,2-1,7 viktprocent tenn, 0,07-0,20 viktprocent järn, 0,05-0,15 viktprocent krom, 0,03-0,08 vikt- procent nickel och 0,09-0,16 viktprocent syre och för Zircaloy 4 1,2-1,7 viktprocent tenn, 0,18-0,24 viktprocent järn, 0,07-0,13 viktprocent krom och 0,09-0,16 viktprocent syre. Resten av legeringen i kapslingsröret utgöres av zirkonium och i zirkonium av reaktorkvalitet normalt före- kommande föroreningar, vilka redan beskrivits närmare. Kärnbränslet i bränslestaven utgöres företrädesvis av urandioxid.The thickness of the protective layer is suitably 0.0Ä-0.32 mm and gradually to 0.05-0.1 mm. The thickness of the layer is suitably 5-40% and preferably 5-15% of the wall thickness of the enclosure tube. 3 469 997 The material of the encapsulation tube has been described initially. To this can it is added that for Zircaloy 2 the composition is 1.2-1.7% by weight of tin, 0.07-0.20 weight percent iron, 0.05-0.15 weight percent chromium, 0.03-0.08 weight percent percent nickel and 0.09-0.16 weight percent oxygen and for Zircaloy 4 1.2-1.7 weight percent tin, 0.18-0.24 weight percent iron, 0.07-0.13 weight percent chromium and 0.09-0.16% by weight oxygen. The rest of the alloy in the housing tube consists of zirconium and in reactor grade zirconium normally present future pollutants, which have already been described in more detail. Nuclear fuel in the fuel rod is preferably uranium dioxide.
Uppfinningen skall förklaras närmare genom beskrivning av utföringsexempel under hänvisning till bifogade ritning, som visar ett tvärsnitt av en bränslestav enligt den föreliggande uppfinningen för en lättvattenreaktor.The invention will be explained in more detail by describing exemplary embodiments with reference to the accompanying drawing, which shows a cross section of a fuel rod according to the present invention for a light water reactor.
Ett rör av en legering av zirkonium innehållande 1,0 viktprocent beryllium med en väggtjocklek av 1,25 mm och en ytterdiameter av 44 mm anordnas i ett rör av Zircaloy 2 med en väggtjocklek av 10 mm och en innerdiameter av 45 mm. De båda rören svetsas ihop vid rörens båda ändytor. Det så erhållna sammansatta röret strängpressas utan att underkastas någon uppvärmning. Den strängpressade produkten kallvalsas därefter i flera steg med mellanligg- ande rekristallisationsglödgningar vid omkring 650 OC och en slutglödgning efter sista valsningen vid omkring 525 OC, varvid en i figuren visad rörformad slutprodukt erhålles, bestående av ett skikt 1 av Zircaloy 2 med en tjocklek av 0,73 mm och en innerdiameter av 10,65 mm och av ett skikt 2 av en legering av zirkonium innehållande 1,0 viktprocent beryllium med en tjocklek av 0,07 mm. I figuren är även kärnbränslet inritat, vilket består av cirkulärcylindriska kutsar 3 av urandioxid staplade på varandra i kaps- lingsrörets axelriktning.A tube of an alloy of zirconium containing 1.0% by weight of beryllium with a wall thickness of 1.25 mm and an outer diameter of 44 mm are arranged in one pipes of Zircaloy 2 with a wall thickness of 10 mm and an inner diameter of 45 mm. The two pipes are welded together at both end surfaces of the pipes. That so obtained the composite pipe is extruded without being subjected to any heating. The the extruded product is then cold rolled in several steps with intermediate recrystallization annealing at about 650 ° C and a final annealing after the last rolling at about 525 ° C, one of which is shown in the figure tubular end product is obtained, consisting of a layer 1 of Zircaloy 2 with a thickness of 0.73 mm and an inner diameter of 10.65 mm and of a layer 2 of an alloy of zirconium containing 1.0% by weight of beryllium with a thickness of 0.07 mm. The figure also shows the nuclear fuel, which remains of circular cylindrical urns 3 of uranium dioxide stacked on top of each other in capsules axial direction of the pipe.
Bränslestaven enligt uppfinningen är i första hand avsedd att användas i en reaktor med vatten som kylmedel.The fuel rod according to the invention is primarily intended for use in a reactor with water as coolant.
Claims (2)
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| SE9200584A SE469997B (en) | 1992-02-27 | 1992-02-27 | Fuel rod for nuclear reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| SE9200584A SE469997B (en) | 1992-02-27 | 1992-02-27 | Fuel rod for nuclear reactor |
Publications (3)
| Publication Number | Publication Date |
|---|---|
| SE9200584D0 SE9200584D0 (en) | 1992-02-27 |
| SE9200584L SE9200584L (en) | 1993-08-28 |
| SE469997B true SE469997B (en) | 1993-10-18 |
Family
ID=20385442
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| SE9200584A SE469997B (en) | 1992-02-27 | 1992-02-27 | Fuel rod for nuclear reactor |
Country Status (1)
| Country | Link |
|---|---|
| SE (1) | SE469997B (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US8320515B2 (en) | 2006-08-24 | 2012-11-27 | Westinghouse Electric Sweden Ab | Water reactor fuel cladding tube |
-
1992
- 1992-02-27 SE SE9200584A patent/SE469997B/en not_active IP Right Cessation
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US8320515B2 (en) | 2006-08-24 | 2012-11-27 | Westinghouse Electric Sweden Ab | Water reactor fuel cladding tube |
Also Published As
| Publication number | Publication date |
|---|---|
| SE9200584D0 (en) | 1992-02-27 |
| SE9200584L (en) | 1993-08-28 |
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