CH320931A - Element with fissile material for nuclear reactors - Google Patents
Element with fissile material for nuclear reactorsInfo
- Publication number
- CH320931A CH320931A CH320931DA CH320931A CH 320931 A CH320931 A CH 320931A CH 320931D A CH320931D A CH 320931DA CH 320931 A CH320931 A CH 320931A
- Authority
- CH
- Switzerland
- Prior art keywords
- fissile material
- shell
- fissile
- nuclear reactors
- percent
- Prior art date
Links
- 239000000463 material Substances 0.000 title claims description 16
- 239000000956 alloy Substances 0.000 claims description 2
- 229910045601 alloy Inorganic materials 0.000 claims description 2
- 229910052797 bismuth Inorganic materials 0.000 claims description 2
- JCXGWMGPZLAOME-UHFFFAOYSA-N bismuth atom Chemical compound [Bi] JCXGWMGPZLAOME-UHFFFAOYSA-N 0.000 claims description 2
- 239000007788 liquid Substances 0.000 claims description 2
- XLYOFNOQVPJJNP-ZSJDYOACSA-N Heavy water Chemical compound [2H]O[2H] XLYOFNOQVPJJNP-ZSJDYOACSA-N 0.000 description 2
- 230000004992 fission Effects 0.000 description 2
- 230000008018 melting Effects 0.000 description 2
- 238000002844 melting Methods 0.000 description 2
- 229910052770 Uranium Inorganic materials 0.000 description 1
- 238000010521 absorption reaction Methods 0.000 description 1
- 229910052782 aluminium Inorganic materials 0.000 description 1
- XAGFODPZIPBFFR-UHFFFAOYSA-N aluminium Chemical compound [Al] XAGFODPZIPBFFR-UHFFFAOYSA-N 0.000 description 1
- QVGXLLKOCUKJST-UHFFFAOYSA-N atomic oxygen Chemical compound [O] QVGXLLKOCUKJST-UHFFFAOYSA-N 0.000 description 1
- 230000006866 deterioration Effects 0.000 description 1
- 230000003647 oxidation Effects 0.000 description 1
- 238000007254 oxidation reaction Methods 0.000 description 1
- 229910052760 oxygen Inorganic materials 0.000 description 1
- 239000001301 oxygen Substances 0.000 description 1
- 239000000941 radioactive substance Substances 0.000 description 1
- 239000007787 solid Substances 0.000 description 1
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-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
- G21C3/16—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
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Description
Element mit spaltbarem Material für Kernreaktoren Es ist eine Bauart für Kernreaktoren bekannt, in welcher Stäbe oder Rohre von spaltbarem Material (z. B. Uran) von einem Moderator (z. B. schweres Wasser) umgeben sind. Damit die bei den Kernspaltungen ent stehenden radioaktiven Substanzen nicht in den Moderator entweichen können, sind die Stäbe oder Rohre mit je einer Hülle aus ge eignetem Material (z. B. Aluminium) ver sehen.
Diese Stäbe oder Rohre zeigen nun beim Betrieb des Reaktors infolge der Temperatur einflüsse mehr oder weniger starke Formände rungen. Dadurch werden Hüllen, welche an fänglich das spaltbare Material fest umschlos sen, lose. Die Folge ist eine Verschlechterung des Wärmeüberganges vom spaltbaren Ma terial in die Hülle. Befinden sich innerhalb der Hülle Spuren von Sauerstoff, so tritt eine Oxydation des spaltbaren Materials auf, welche den Wärmeübergang noch weiter erschwert. Eine Folge von schlechtem Wärmeübergang sind unzulässig grosse Temperaturdifferenzen im spaltbaren Material, welche zu mechani schen Schäden führen können.
Dieser Nachteil wird erfindungsgemäss da durch vermieden, dass zwischen dem spaltbaren Material und der Hülle ein Zwischenmedium vorgesehen wird, welches bei der Betriebstem peratur des Kernreaktors flüssig ist und wel ches einen guten Wärmeübergang zwischen dem spaltbaren Material und der Hülle be wirkt. Ein für den vorgesehenen Zweck geeignetes Mediiun soll einen kleinen Absorptionsquer schnitt für Neutronen aufweisen, darf bei den in Frage kommenden Temperaturen weder mit dem spaltbaren Material noch mit dem Material der Hülle reagieren und soll auch durch die Spaltprodukte nicht angegriffen werden. Wird ein Medium gewählt, welches bei Zimmertemperatur fest ist, so soll die Volumenänderung beim Schmelzen möglichst gering sein.
Als geeignetes Zwischenmedium hat sich eine Legierung von 44,5 Gewichtsprozenten Blei und 55,5 Gewichtsprozenten Wismut er wiesen, deren Schmelzpunkt bei 125 C liegt.
Element with fissile material for nuclear reactors A design for nuclear reactors is known in which rods or tubes of fissile material (e.g. uranium) are surrounded by a moderator (e.g. heavy water). So that the radioactive substances produced during nuclear fission cannot escape into the moderator, the rods or tubes are each provided with a cover made of a suitable material (e.g. aluminum).
These rods or tubes now show more or less strong changes in shape during operation of the reactor as a result of the temperature influences. As a result, casings which initially firmly enclose the fissile material are loose. The result is a deterioration in the heat transfer from the fissile material into the shell. If there are traces of oxygen within the shell, oxidation of the fissile material occurs, which makes the heat transfer even more difficult. One consequence of poor heat transfer are inadmissibly large temperature differences in the fissile material, which can lead to mechanical damage.
According to the invention, this disadvantage is avoided by providing an intermediate medium between the fissile material and the shell, which is liquid at the operating temperature of the nuclear reactor and which ensures good heat transfer between the fissile material and the shell. A medium suitable for the intended purpose should have a small absorption cross-section for neutrons, must not react with the fissile material or the material of the shell at the temperatures in question and should not be attacked by the fission products. If a medium is chosen that is solid at room temperature, the change in volume during melting should be as small as possible.
An alloy of 44.5 percent by weight lead and 55.5 percent by weight bismuth, with a melting point of 125 ° C., has proven to be a suitable intermediate medium.
Claims (1)
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CH320931T | 1954-08-21 |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CH320931A true CH320931A (en) | 1957-04-15 |
Family
ID=4498190
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CH320931D CH320931A (en) | 1954-08-21 | 1954-08-21 | Element with fissile material for nuclear reactors |
Country Status (1)
| Country | Link |
|---|---|
| CH (1) | CH320931A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO2020185502A3 (en) * | 2019-03-07 | 2020-10-22 | Westinghouse Electric Company Llc | Self-healing liquid pellet-cladding gap heat transfer filler |
-
1954
- 1954-08-21 CH CH320931D patent/CH320931A/en unknown
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO2020185502A3 (en) * | 2019-03-07 | 2020-10-22 | Westinghouse Electric Company Llc | Self-healing liquid pellet-cladding gap heat transfer filler |
| JP2022523582A (en) * | 2019-03-07 | 2022-04-25 | ウェスティングハウス エレクトリック カンパニー エルエルシー | Self-healing liquid pellet-coating gap heat transfer filler |
| JP2025020202A (en) * | 2019-03-07 | 2025-02-12 | ウェスティングハウス エレクトリック カンパニー エルエルシー | Self-healing liquid pellet-coated gap heat transfer filler |
| US12412672B2 (en) | 2019-03-07 | 2025-09-09 | Westinghouse Electric Company Llc | Fuel rod having heat transfer liquid filling the gap between fuel pellets and cladding tube |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| DE1125087B (en) | Heavy water moderated nuclear reactor cooled with liquid metal | |
| DE2501505A1 (en) | IMPROVED CORE FUEL ELEMENT | |
| DE1037609B (en) | Fuel element for nuclear reactors | |
| DE2259569A1 (en) | NUCLEAR FUEL ELEMENT | |
| DE2220486C3 (en) | Pressurized water reactor | |
| DE1068821B (en) | ||
| DE1204345B (en) | Nuclear reactor fuel element | |
| DE2007833A1 (en) | Nuclear reactor fuel rod | |
| DE1003364B (en) | Nuclear reactor | |
| US3067116A (en) | Protected nuclear fuel element | |
| DE1514962C3 (en) | The breeder reactor works with fast neutrons | |
| DE2259570A1 (en) | NUCLEAR FUEL ELEMENT | |
| CH320931A (en) | Element with fissile material for nuclear reactors | |
| CH626739A5 (en) | Burnable neutron absorber rod | |
| DE1055141B (en) | Fuel element for a heterogeneous nuclear reactor | |
| DE2728748C2 (en) | ||
| CH370491A (en) | Thermal insulation for the moderator boiler and the components of liquid-moderated nuclear reactors passed through it | |
| DE1297775B (en) | Gas-cooled nuclear reactor | |
| AT206076B (en) | Atomic nuclear reactor with fissile elements | |
| DE1014240B (en) | Fuel element | |
| DE69606772T2 (en) | FUEL BAR TO BURN ACTINIDES | |
| DE1439843C3 (en) | Nuclear reactor | |
| DE1093495B (en) | Carrying and supporting device for nuclear reactor fuel elements | |
| DE1062834B (en) | Fuel elements with non-metallic cover for nuclear reactors | |
| DE1639070C (en) | Fissile material element for pressure nuclear reactors and process for its manufacture |