DE1010660B - Protective sleeve for fissile material elements of nuclear reactors - Google Patents
Protective sleeve for fissile material elements of nuclear reactorsInfo
- Publication number
- DE1010660B DE1010660B DES48398A DES0048398A DE1010660B DE 1010660 B DE1010660 B DE 1010660B DE S48398 A DES48398 A DE S48398A DE S0048398 A DES0048398 A DE S0048398A DE 1010660 B DE1010660 B DE 1010660B
- Authority
- DE
- Germany
- Prior art keywords
- fissile material
- protective sleeve
- glass
- nuclear reactors
- material elements
- 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.)
- Pending
Links
- 239000000463 material Substances 0.000 title claims description 21
- 230000001681 protective effect Effects 0.000 title claims description 8
- 239000011521 glass Substances 0.000 claims description 16
- 238000000576 coating method Methods 0.000 claims description 8
- 239000011248 coating agent Substances 0.000 claims description 5
- 238000004519 manufacturing process Methods 0.000 claims description 4
- 238000000034 method Methods 0.000 claims description 4
- 229910052910 alkali metal silicate Inorganic materials 0.000 claims description 2
- 239000005397 alkali-lead silicate glass Substances 0.000 claims description 2
- 239000000156 glass melt Substances 0.000 claims description 2
- 239000000843 powder Substances 0.000 claims description 2
- 229910052782 aluminium Inorganic materials 0.000 description 7
- XAGFODPZIPBFFR-UHFFFAOYSA-N aluminium Chemical compound [Al] XAGFODPZIPBFFR-UHFFFAOYSA-N 0.000 description 7
- 239000000126 substance Substances 0.000 description 5
- 238000010521 absorption reaction Methods 0.000 description 4
- IJGRMHOSHXDMSA-UHFFFAOYSA-N Atomic nitrogen Chemical compound N#N IJGRMHOSHXDMSA-UHFFFAOYSA-N 0.000 description 2
- 239000000919 ceramic Substances 0.000 description 2
- 239000007789 gas Substances 0.000 description 2
- 239000000203 mixture Substances 0.000 description 2
- 239000002245 particle Substances 0.000 description 2
- 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
- 239000000654 additive Substances 0.000 description 1
- 230000002411 adverse Effects 0.000 description 1
- 229910052802 copper Inorganic materials 0.000 description 1
- 239000010949 copper Substances 0.000 description 1
- 238000005260 corrosion Methods 0.000 description 1
- 230000007797 corrosion Effects 0.000 description 1
- 239000013078 crystal Substances 0.000 description 1
- 230000002349 favourable effect Effects 0.000 description 1
- 230000004992 fission Effects 0.000 description 1
- 239000000446 fuel Substances 0.000 description 1
- 229910002804 graphite Inorganic materials 0.000 description 1
- 239000010439 graphite Substances 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
- 238000002844 melting Methods 0.000 description 1
- 230000008018 melting Effects 0.000 description 1
- 229910052751 metal Inorganic materials 0.000 description 1
- 239000002184 metal Substances 0.000 description 1
- 150000002739 metals Chemical class 0.000 description 1
- 229910052757 nitrogen Inorganic materials 0.000 description 1
- TWNQGVIAIRXVLR-UHFFFAOYSA-N oxo(oxoalumanyloxy)alumane Chemical compound O=[Al]O[Al]=O TWNQGVIAIRXVLR-UHFFFAOYSA-N 0.000 description 1
- 230000005855 radiation Effects 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
- 239000005368 silicate glass Substances 0.000 description 1
- 239000007787 solid Substances 0.000 description 1
- 229910001220 stainless steel Inorganic materials 0.000 description 1
- 239000010935 stainless steel Substances 0.000 description 1
- 210000002700 urine Anatomy 0.000 description 1
- 229910052845 zircon Inorganic materials 0.000 description 1
- GFQYVLUOOAAOGM-UHFFFAOYSA-N zirconium(iv) silicate Chemical compound [Zr+4].[O-][Si]([O-])([O-])[O-] GFQYVLUOOAAOGM-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
- G21C3/02—Fuel elements
- G21C3/04—Constructional details
- G21C3/06—Casings; Jackets
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C21/00—Apparatus or processes specially adapted to the manufacture of reactors or parts thereof
- G21C21/02—Manufacture of fuel elements or breeder elements contained in non-active casings
-
- 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)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Manufacturing & Machinery (AREA)
- Glass Compositions (AREA)
Description
Schutzhülse für Spaltstoffelemente von Kernreaktoren In heterogenen Reaktoren wird der Spaltstoff meist in Form von Stäben oder Blechen, den sogenannten Spaltstoffelementen, in die Moderatursubstanz, z. B. aus Graphit oder D.0, eingebettet. Um eine Korrosion derBrennstoffelementezuvermeiden und damit die bei der Kernspaltung entstehenden, zum Teil hochradioaktiven Spaltprodukte den Reaktor und seine Umgebung nicht zu verseuchen sowie auf Grund der sonstigen bei einem Reaktor gegebenen Verhältnisse und. Anforderungen werden die Spaltstoffelemente mit einer Hülse versehen.Protective sleeve for fissile material elements of nuclear reactors In heterogeneous reactors, the fissile material is usually in the form of rods or sheets, the so-called fissile material elements, in the moderating substance, e.g. B. made of graphite or D.0, embedded. In order to avoid corrosion of the fuel elements and thus not to contaminate the reactor and its surroundings due to the fission products, some of which are highly radioactive. If required, the fissile material elements are provided with a sleeve.
Der Hülsenwerkstoff muß gemäß den vorgenannten Bedingungen im Reaktor folgende Eigenschaften aufweisen 1. Geringer Absorptionsquerschnitt für Neutronen, 2. hohes Bremsvermögen für Kerntrümmer, ferner für a-, ß- und y-Strahlung, 3. geringe Beeinflußbarkeit der mechanischen und chemischen Eigenschaften durch Neutronenbeschuß, 4. möglichst hoherErweichungs- undSchmelzpunkt, 5. Gasdichtigkeit, 6. hinreichende chemische Widerstandsfähigkeit. Als Hülsenwerkstoff wurde bisher vorwiegend Aluminiam, insbesondere Sinteraluminium mit Aluminiumoxydzusätzen, verwendet. Bei Temperaturbeanspruchungen, die wesentlich über 400° C hinausgehen, wurde bisher auch gesintertes Zirkon verwendet. Dieses muß vorher extrem rein dargestellt, vor allem von Hafnium und Stickstoff befreit werden. Weiterhin sind auch Hülsen aus rostfreiem Stahl vorgeschlagen worden. Derartige Schutzhülsen sind verhältnismäßig sehr teuer. Neuerdings wurde ein keramischer Hülsenwerkstoff entwickelt, der Neutronen nur sehr schwach absorbiert und für Temperaturen bis zu etwa 1000° C brauchbar ist. Bei diesem Werkstoff dürfte die Erreichung einer genügenden Gasdichtigkeit Schwierigkeiten bereiten.The sleeve material must comply with the aforementioned conditions in the reactor have the following properties 1. Small absorption cross-section for neutrons, 2. high braking capacity for core debris, furthermore for a-, ß- and y-radiation, 3. low The mechanical and chemical properties can be influenced by neutron bombardment, 4. the highest possible softening and melting point, 5. gas tightness, 6. adequate chemical resistance. The sleeve material used so far has been mainly aluminum, in particular sintered aluminum with aluminum oxide additives is used. In case of temperature loads, which go well above 400 ° C, sintered zircon has also been used up to now. This must first be made extremely pure, especially of hafnium and nitrogen to be freed. Stainless steel sleeves have also been proposed. Such protective sleeves are relatively very expensive. Recently a ceramic one Sleeve material developed that absorbs neutrons only very weakly and is suitable for temperatures up to about 1000 ° C is useful. With this material, the achievement of a sufficient gas tightness cause difficulties.
Gemäß der Erfindung wird als Hülsenwerkstoff Glas verwendet. Es kommen z. B. Alkali-Silikat- oder .Alkali-Blei-Silikat-Gläser in Frage, die sich für andere Anwendungszwecke zur Herstellung von Glasüberzügen bereits bewährt haben. Die nachfolgende Gegenüberstellung der Eigenschaften des Schutzhülsenwerkstoffes nach der Erfindung und der bisher bekannten Schutzhülsen.werkstoffe zeigt,die günstigen Eigenschaften des ersteren: Absorptionsquerschnitt für thermische Neutronen Er beträgt bei Aluminium 0,22 harn. Bei einem Blei-Silikat-Glas, wie es bereits zur Herstellung von Glasüberzügen auf Kupfer in einer Zusammensetzung von 63 Molprozent Si 021 25 Molprozent Pb O, 10 Molprozent Nag O und 2 Molprozent Al. 03 verwendet wurde, beträgt der mittlere Absorptionsquerschnitt 0,084 barn und liegt somit unterhalb des Absorptionsquerschnittes des Aluminiums.According to the invention, glass is used as the sleeve material. There come z. B. alkali-silicate or .Alkali-lead-silicate glasses in question, which have already proven themselves for other applications for the production of glass coatings. The following comparison of the properties of the protective sleeve material according to the invention and the previously known Schutzhülsen.werkstoffe shows the favorable properties of the former: Absorption cross-section for thermal neutrons It is 0.22 urine for aluminum. In the case of a lead-silicate glass, as has already been used for the production of glass coatings on copper in a composition of 63 mol percent Si 021, 25 mol percent Pb O, 10 mol percent Nag O and 2 mol percent Al. 03 was used, the mean absorption cross-section is 0.084 barn and is thus below the absorption cross-section of aluminum.
Bremsvermögen für Kerntrümmer und für a-, ß- und y-Strahlung Die Reichweite von Kerntrümmern und von a- und ß-Teilchen hängt in erster Näherung nur von der Teilchenenergie und von der Dichte des betreffenden Stoffes ab. Gläser und Aluminium haben etwa die gleiche Dichte. Auch die Reichweite von y-Quanten liegt im Energiebereich zwischen 0,1 und 100 meV bei Gläsern der obeügenannten Zusammensetzung in der gleichen Größenordnung wie bei Aluminium.Braking power for core debris and for a, ß and y radiation. The range of nuclear debris and of a- and ß-particles depends in a first approximation only on the Particle energy and the density of the substance in question. Glasses and aluminum have about the same density. The range of y-quanta is also in the energy range between 0.1 and 100 meV for glasses of the above-mentioned composition in the same The same order of magnitude as with aluminum.
Der Erweichungswert der meisten Gläser liegt oberhalb 600° C. Sie sind in dieser Hinsicht als Hülsenwerkstoff zumindest dem Aluminium überlegen.The softening value of most glasses is above 600 ° C. They are at least superior to aluminum as a sleeve material in this regard.
Die mechanischen Eigenschaften kristalliner Festkörper, insbesondere von Metallen, werden durch Neutronenbeschuß ungünstig beeinflußt. Dies beruht darauf, daß die Neutronen Störungen im Kristallgitter verursachen und damit eine Herabsetzung der Festigkeit. Gläser sind dagegen, da sie keine ausgeprägte Gitterstruktur besitzen, gegen Neutronenbeschuß unempfindlicher.The mechanical properties of crystalline solids, in particular of metals are adversely affected by neutron bombardment. This is based on that the neutrons cause disturbances in the crystal lattice and thus a reduction of strength. Glasses are against it, because they do not have a distinctive lattice structure, less sensitive to neutron bombardment.
Die chemische Widerstandsfähigkeit der nach der Erfindung als Hülsenwerkstoff zu verwendenden Gläser ist zumindest ebenso groß, wie die der neuerdings vorgeschlagenen keramischen Hülsenwerkstoffe: Hinzu kommt, daß Glasüberzüge absolut gasdicht sind. Die Herstellung der Schutzhülse nach der Erfindung kann in der Weise erfolgen, daß auf das an sich fertige Spaltstoffelement ein Glasüberzug aufgebracht wird. Dieser kann z. B. durch Eintauchen des Spaltstoffelements in eine Glasschmelze gebildet werden. Ein anderes Verfahren besteht darin, daß der Glasüberzug auf elektrophoretischem oder elektrostatischem Wege hergestellt wird. Hierbei wird in an sich bekannter Weise der zu überziehende Gegenstand, in diesem Fall also das Spaltstoffelement, elektrophöretisch oder elektrostatisch mit Glaspulver überzogen und dieses anschließend eingebrannt.The chemical resistance of the sleeve material according to the invention to be used glasses is at least as large as that of the recently proposed Ceramic sleeve materials: In addition, glass coatings are absolutely gas-tight. the Production of the protective sleeve according to the invention can be done in such a way that on a glass coating is applied to the ready-made fissile material element. This can z. B. be formed by immersing the fissile material element in a glass melt. Another method is that the glass coating on electrophoretic or electrostatically. This is known per se The object to be coated, in this case the fissionable material element, Electrophoretic or electrostatic coated with glass powder and then this burned in.
Claims (5)
Priority Applications (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| DES48398A DE1010660B (en) | 1956-04-19 | 1956-04-19 | Protective sleeve for fissile material elements of nuclear reactors |
| CH347582D CH347582A (en) | 1956-04-19 | 1957-04-11 | Protective sleeve for fissile material elements of nuclear reactors |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| DES48398A DE1010660B (en) | 1956-04-19 | 1956-04-19 | Protective sleeve for fissile material elements of nuclear reactors |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| DE1010660B true DE1010660B (en) | 1957-06-19 |
Family
ID=7486832
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| DES48398A Pending DE1010660B (en) | 1956-04-19 | 1956-04-19 | Protective sleeve for fissile material elements of nuclear reactors |
Country Status (2)
| Country | Link |
|---|---|
| CH (1) | CH347582A (en) |
| DE (1) | DE1010660B (en) |
Cited By (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| DE1086817B (en) * | 1958-12-05 | 1960-08-11 | Babcock & Wilcox Dampfkessel | Tubular nuclear reactor fuel element and process for its manufacture |
| DE1205203B (en) * | 1959-07-07 | 1965-11-18 | Commissariat Energie Atomique | Method of applying reinforcement to the ends of a nuclear reactor fuel sleeve |
| DE1206098B (en) * | 1958-05-30 | 1965-12-02 | Atomic Energy Authority Uk | Nuclear fuel |
| DE1217514B (en) * | 1959-06-03 | 1966-05-26 | Philips Nv | Fuel element for nuclear reactors |
| DE1238113B (en) * | 1959-04-29 | 1967-04-06 | Commissariat Energie Atomique | Nuclear reactor duct |
| DE1294571B (en) * | 1960-05-16 | 1969-05-08 | Westinghouse Electric Corp | Nuclear fuel for suspension reactors |
| FR2410682A1 (en) * | 1977-11-30 | 1979-06-29 | Westinghouse Electric Corp | COATINGS RESISTANT TO THE PENETRATION OF HYDROGEN AND ITS ISOTOPES |
-
1956
- 1956-04-19 DE DES48398A patent/DE1010660B/en active Pending
-
1957
- 1957-04-11 CH CH347582D patent/CH347582A/en unknown
Cited By (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| DE1206098B (en) * | 1958-05-30 | 1965-12-02 | Atomic Energy Authority Uk | Nuclear fuel |
| DE1086817B (en) * | 1958-12-05 | 1960-08-11 | Babcock & Wilcox Dampfkessel | Tubular nuclear reactor fuel element and process for its manufacture |
| DE1238113B (en) * | 1959-04-29 | 1967-04-06 | Commissariat Energie Atomique | Nuclear reactor duct |
| DE1217514B (en) * | 1959-06-03 | 1966-05-26 | Philips Nv | Fuel element for nuclear reactors |
| DE1205203B (en) * | 1959-07-07 | 1965-11-18 | Commissariat Energie Atomique | Method of applying reinforcement to the ends of a nuclear reactor fuel sleeve |
| DE1294571B (en) * | 1960-05-16 | 1969-05-08 | Westinghouse Electric Corp | Nuclear fuel for suspension reactors |
| FR2410682A1 (en) * | 1977-11-30 | 1979-06-29 | Westinghouse Electric Corp | COATINGS RESISTANT TO THE PENETRATION OF HYDROGEN AND ITS ISOTOPES |
Also Published As
| Publication number | Publication date |
|---|---|
| CH347582A (en) | 1960-07-15 |
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