NO135805B - - Google Patents
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- Publication number
- NO135805B NO135805B NO723418A NO341872A NO135805B NO 135805 B NO135805 B NO 135805B NO 723418 A NO723418 A NO 723418A NO 341872 A NO341872 A NO 341872A NO 135805 B NO135805 B NO 135805B
- Authority
- NO
- Norway
- Prior art keywords
- fuel
- carbide
- oxygen
- zirconium
- titanium
- Prior art date
Links
- 239000000446 fuel Substances 0.000 claims description 14
- QVGXLLKOCUKJST-UHFFFAOYSA-N atomic oxygen Chemical compound [O] QVGXLLKOCUKJST-UHFFFAOYSA-N 0.000 claims description 12
- 229910052760 oxygen Inorganic materials 0.000 claims description 11
- 239000001301 oxygen Substances 0.000 claims description 11
- 239000003758 nuclear fuel Substances 0.000 claims description 7
- 230000001427 coherent effect Effects 0.000 claims description 6
- RTAQQCXQSZGOHL-UHFFFAOYSA-N Titanium Chemical compound [Ti] RTAQQCXQSZGOHL-UHFFFAOYSA-N 0.000 claims description 5
- QCWXUUIWCKQGHC-UHFFFAOYSA-N Zirconium Chemical compound [Zr] QCWXUUIWCKQGHC-UHFFFAOYSA-N 0.000 claims description 5
- 229910052719 titanium Inorganic materials 0.000 claims description 5
- 239000010936 titanium Substances 0.000 claims description 5
- 229910052726 zirconium Inorganic materials 0.000 claims description 5
- 238000002485 combustion reaction Methods 0.000 claims description 4
- 238000005245 sintering Methods 0.000 claims description 4
- 238000004519 manufacturing process Methods 0.000 claims description 3
- 238000000034 method Methods 0.000 claims description 3
- ZSLUVFAKFWKJRC-IGMARMGPSA-N 232Th Chemical compound [232Th] ZSLUVFAKFWKJRC-IGMARMGPSA-N 0.000 claims description 2
- 229910052778 Plutonium Inorganic materials 0.000 claims description 2
- 229910052776 Thorium Inorganic materials 0.000 claims description 2
- 229910052770 Uranium Inorganic materials 0.000 claims description 2
- 239000011230 binding agent Substances 0.000 claims description 2
- 150000001247 metal acetylides Chemical class 0.000 claims description 2
- OYEHPCDNVJXUIW-UHFFFAOYSA-N plutonium atom Chemical compound [Pu] OYEHPCDNVJXUIW-UHFFFAOYSA-N 0.000 claims description 2
- 239000000843 powder Substances 0.000 claims description 2
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 claims 1
- 229910026551 ZrC Inorganic materials 0.000 description 5
- OTCHGXYCWNXDOA-UHFFFAOYSA-N [C].[Zr] Chemical compound [C].[Zr] OTCHGXYCWNXDOA-UHFFFAOYSA-N 0.000 description 4
- 230000004992 fission Effects 0.000 description 4
- 238000000576 coating method Methods 0.000 description 3
- 239000000047 product Substances 0.000 description 3
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 description 2
- 229910052799 carbon Inorganic materials 0.000 description 2
- 238000006243 chemical reaction Methods 0.000 description 2
- 239000007795 chemical reaction product Substances 0.000 description 2
- 150000001875 compounds Chemical class 0.000 description 2
- 239000007789 gas Substances 0.000 description 2
- 235000021355 Stearic acid Nutrition 0.000 description 1
- 230000015572 biosynthetic process Effects 0.000 description 1
- 125000004432 carbon atom Chemical group C* 0.000 description 1
- 239000011248 coating agent Substances 0.000 description 1
- 230000000254 damaging effect Effects 0.000 description 1
- 238000005538 encapsulation Methods 0.000 description 1
- 239000011812 mixed powder Substances 0.000 description 1
- 239000000203 mixture Substances 0.000 description 1
- QIQXTHQIDYTFRH-UHFFFAOYSA-N octadecanoic acid Chemical compound CCCCCCCCCCCCCCCCCC(O)=O QIQXTHQIDYTFRH-UHFFFAOYSA-N 0.000 description 1
- OQCDKBAXFALNLD-UHFFFAOYSA-N octadecanoic acid Natural products CCCCCCCC(C)CCCCCCCCC(O)=O OQCDKBAXFALNLD-UHFFFAOYSA-N 0.000 description 1
- 125000004430 oxygen atom Chemical group O* 0.000 description 1
- 239000006104 solid solution Substances 0.000 description 1
- 239000008117 stearic acid Substances 0.000 description 1
- 239000000126 substance Substances 0.000 description 1
- MTPVUVINMAGMJL-UHFFFAOYSA-N trimethyl(1,1,2,2,2-pentafluoroethyl)silane Chemical compound C[Si](C)(C)C(F)(F)C(F)(F)F MTPVUVINMAGMJL-UHFFFAOYSA-N 0.000 description 1
- 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 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
- G21C3/42—Selection of substances for use as reactor fuel
- G21C3/58—Solid reactor fuel Pellets made of fissile material
- G21C3/62—Ceramic fuel
- G21C3/626—Coated fuel particles
-
- 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
- G21C3/42—Selection of substances for use as reactor fuel
- G21C3/58—Solid reactor fuel Pellets made of fissile material
- G21C3/62—Ceramic fuel
-
- 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)
- Ceramic Engineering (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Ceramic Products (AREA)
- Materials For Medical Uses (AREA)
- Manufacturing Of Micro-Capsules (AREA)
- Inorganic Compounds Of Heavy Metals (AREA)
Description
Foreliggende oppfinnelse angår kapslede eller bekledde nukleære brensellegemer som omfatter nukleært brensel i form av oksyd, samt en fremgangsmåte for fremstilling av et sådant legeme. En av de faktorer som antas å ha en odeleggende virkning på oksydbrensel, The present invention relates to encapsulated or coated nuclear fuel bodies which comprise nuclear fuel in the form of oxide, as well as a method for producing such a body. One of the factors believed to have a damaging effect on oxide fuel,
er at det oppstår gasser inne i brenselstrukturen og dens omslutning. Under forbrenningen av oksydbrensel.vil f.eks. de oksygen-atomer som ikke reagerer med fisjons-produktene bygge opp et gass-trykk som vil kunne bli meget kraftig og frembringe skadelige påkjenninger i brenselstrukturen eller dens omslutning. is that gases occur inside the fuel structure and its surroundings. During the combustion of oxide fuel, e.g. the oxygen atoms that do not react with the fission products build up a gas pressure that can become very strong and produce harmful stresses in the fuel structure or its enclosure.
Det er et formål for foreliggende oppfinnelse å overvinne denne ulempe, og da det f.eks. fra svensk patentskrift nr. 315.341 og US patentskrift nr. 3.472.734 er tidligere kjent kapslede nukleære brensellegemer som omfatter nukleært brensel i form av oksyd av minst ett av elementene i elementgruppen: uran, plutenium, og torium, kombinert med en tilleggskomponent som omfatter en karbid av zirkonium eller titan, foreslåes på denne bakgrunn og i henhold til oppfinnelsen et brensellegeme av ovenfor angitt art hvori, It is an object of the present invention to overcome this disadvantage, and when it e.g. from Swedish Patent No. 315,341 and US Patent No. 3,472,734 are previously known encapsulated nuclear fuel bodies which comprise nuclear fuel in the form of oxide of at least one of the elements in the element group: uranium, plutonium, and thorium, combined with an additional component comprising a carbide of zirconium or titanium, on this background and in accordance with the invention, a fuel element of the type indicated above is proposed in which,
nevnte kombinasjon utgjbres av en koherent sammensintring som omfatter minst en av nevnte oksyder og en av nevnte karbider i separate faser og innkapslet i fravær av oksygenholdig atmosfære. said combination is produced by a coherent sintering comprising at least one of said oxides and one of said carbides in separate phases and encapsulated in the absence of an oxygen-containing atmosphere.
Når et sådant brensellegeme plasseres i en nukleær reaktor hvori fisjons-reaksjoner opptrer og oksygen dannes, vil den andel av det dannede oksygen som ikke kombineres med fisjons-produktene, hvilket vil være fri oksygen, enten utfylle foreliggende mellomrom i karbiden, hvis struktur forblir uforandret, eller reagerer med karbonatomer for dannelse av CO. I sistnevnte tilfelle vil imidler-tid CO-trykket i brensellegemet eller dets innkapsling ikke over- - skride likevektstrykket av CO overfor det oksygenfrie oksy-karbid, fordi CO ettersom det dannes vil reagere med karbiden og ikke etter- When such a fuel body is placed in a nuclear reactor in which fission reactions occur and oxygen is formed, the proportion of the formed oxygen that does not combine with the fission products, which will be free oxygen, will either fill existing spaces in the carbide, whose structure remains unchanged , or reacts with carbon atoms to form CO. In the latter case, however, the CO pressure in the fuel body or its encapsulation will not exceed the equilibrium pressure of CO vis-à-vis the oxygen-free oxy-carbide, because CO, as it is formed, will react with the carbide and not
late noen reaksjonsprodukter i gassform. leaving some reaction products in gaseous form.
Oppfinnelsen omfatter også en fremgangsmåte for fremstilling av ovenfor angitte brensellegeme, og som går ut på at det dannes et koherent ferskt legeme som omfatter en eller flere av de nevnte oksyder samt en karbid av zirkonium eller titan, hvoretter nevnte ferske legeme sintres ved en temperatur som tillater vedkommende oksyd og karbid å forbli i separate faser, og det sintrede legeme tilslutt innkapsles uten at legemet utsettes for oksygenholdig atmosfære. The invention also includes a method for producing the above-mentioned fuel body, which involves the formation of a coherent fresh body comprising one or more of the aforementioned oxides as well as a carbide of zirconium or titanium, after which said fresh body is sintered at a temperature which allows the relevant oxide and carbide to remain in separate phases, and the sintered body is finally encapsulated without exposing the body to an oxygen-containing atmosphere.
Ved en praktisk utfdrelse av oppfinnelsens fremgangsmåte ble zirkoniumkarbid-pulver blandet med U02 og et bindemiddel som f.eks. stearinsyre. De blandede pulvere ble malt og utformet til sferoider ved hjelp av "langsom vekst"-metoden. Sferoidene ble så sintret under reduserende forhold for frembringelse av koherente sferoider av U02 og Zr C. Forutsatt at sintringstemperaturen holdes forholds-vis lav, f.eks. under omkring 1.500°C, vil U02 og Zr C ikke danne en fast opplbsning, men fortsatt foreligge som separate faser. In a practical implementation of the method of the invention, zirconium carbide powder was mixed with U02 and a binder such as e.g. stearic acid. The mixed powders were ground and shaped into spheroids using the "slow growth" method. The spheroids were then sintered under reducing conditions to produce coherent spheroids of UO 2 and Zr C. Provided that the sintering temperature is kept relatively low, e.g. below about 1,500°C, U02 and Zr C will not form a solid solution, but still exist as separate phases.
Etter sintringen holdes sferoidene adskilt fra oksygenholdige atmosfærer inntil de er klare for påfbring av de vanlige belegg for tilbakeholdelse av fisjonsprodukter. After sintering, the spheroids are kept separated from oxygen-containing atmospheres until they are ready for application of the usual coatings for containment of fission products.
Når disse belegg er påfbrt, vil det ikke lenger foreligge noen fare for at sferoidene kan oppta oksygen fra atmosfæren. Under for-brenning av U02, vil det frigjorte oksygen som ikke inngår i noen reaksjon oppta ledige atomplasser i zirkoniumkarbidet:, og opptil 60 % av disse indre gitterposisjoner kan være fylt med atomisk oksygen i stedet for karbon uten at det opptrer strukturelle forandringer i sferoiden. Karbon i belegget eller sferoiden kan reagere med oksygen for dannelse av CO, men i dette tilfelle vil CO reagere med Zr C for dannelse av en oksy-karbid, og man får When these coatings are applied, there will no longer be any danger that the spheroids can absorb oxygen from the atmosphere. During combustion of U02, the freed oxygen that does not take part in any reaction will occupy vacant atomic sites in the zirconium carbide:, and up to 60% of these internal lattice positions can be filled with atomic oxygen instead of carbon without structural changes occurring in the spheroid . Carbon in the coating or spheroid can react with oxygen to form CO, but in this case the CO will react with ZrC to form an oxy-carbide, and you get
således : thus:
Den kjemiske sammensetning av oksykarbidet er ikke veldefinert og alle slags mellom-forbindélser«er mulige. Forbindelsen kan således bedre beskrives ved formelen Zr 0x C^.. CO-trykket i sferoiden vil ikke overskride likevektstrykket for CO overfor det oksygenfattige oksy-karbid, fordi CO, etterhvert som det dannes, vil reagere med karbiden og ikke etterlate noen reaksjonsprodukter i gassform. The chemical composition of the oxycarbide is not well defined and all kinds of intermediate compounds are possible. The compound can thus be better described by the formula Zr 0x C^.. The CO pressure in the spheroid will not exceed the equilibrium pressure for CO against the oxygen-poor oxy-carbide, because CO, as it is formed, will react with the carbide and leave no reaction products in gaseous form .
Det kan vises at likevektstrykket for CO overfor både oksygenfattig oksy-zirkoniumkarbid og oksy-titankarbid er meget lavt. It can be shown that the equilibrium pressure for CO against both oxygen-poor oxy-zirconium carbide and oxy-titanium carbide is very low.
Den anvandte forholdsvise mengde av zirkoniumkarbid eller titankarbid avhenger av den forbrenningsgrad som brenselet skal utsettes for. Det antas at det for hver prosent nukleært spaltbart brensel {% FIMA) grovt regnet kan andvendes 25 mol-prosent karbid. The relative amount of zirconium carbide or titanium carbide used depends on the degree of combustion to which the fuel is to be subjected. It is assumed that for each percent nuclear fissionable fuel {% FIMA) roughly 25 mole percent carbide can be used.
Claims (4)
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB4675871A GB1375575A (en) | 1971-10-07 | 1971-10-07 | Improvements in or relating to encapsulated or clad nuclear fuel bodies |
Publications (2)
Publication Number | Publication Date |
---|---|
NO135805B true NO135805B (en) | 1977-02-21 |
NO135805C NO135805C (en) | 1977-06-01 |
Family
ID=10442477
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
NO723418A NO135805C (en) | 1971-10-07 | 1972-09-25 |
Country Status (3)
Country | Link |
---|---|
JP (1) | JPS4845795A (en) |
GB (1) | GB1375575A (en) |
NO (1) | NO135805C (en) |
Families Citing this family (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
GB2330685A (en) * | 1997-10-25 | 1999-04-28 | British Nuclear Fuels Plc | Production of plutonium containing products |
CN108417279B (en) * | 2018-02-01 | 2020-05-01 | 中国工程物理研究院材料研究所 | ZrC and UO2Composite fuel pellet and preparation method and application thereof |
-
1971
- 1971-10-07 GB GB4675871A patent/GB1375575A/en not_active Expired
-
1972
- 1972-09-25 NO NO723418A patent/NO135805C/no unknown
- 1972-10-07 JP JP72101076A patent/JPS4845795A/ja active Pending
Also Published As
Publication number | Publication date |
---|---|
JPS4845795A (en) | 1973-06-29 |
NO135805C (en) | 1977-06-01 |
GB1375575A (en) | 1974-11-27 |
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