CA2307402A1 - Modular fuel element adaptable to different nuclear power plants with cooling channels - Google Patents
Modular fuel element adaptable to different nuclear power plants with cooling channels Download PDFInfo
- Publication number
- CA2307402A1 CA2307402A1 CA002307402A CA2307402A CA2307402A1 CA 2307402 A1 CA2307402 A1 CA 2307402A1 CA 002307402 A CA002307402 A CA 002307402A CA 2307402 A CA2307402 A CA 2307402A CA 2307402 A1 CA2307402 A1 CA 2307402A1
- Authority
- CA
- Canada
- Prior art keywords
- fuel
- fuel element
- modular
- nuclear
- power plants
- 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.)
- Granted
Links
Classifications
-
- 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
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
The present invention relates to a modular nuclear fuel element, which can be adapted by an assembly system allowing it to be used in different nuclear power plants with horizontal and vertical cooling channels. The module is a cluster of parallel fuel rods mounted as circular concentric crowns and supported by a structural system. It has a single diameter fuel rod array where the ratio of the heat transfer area to the transverse rod area is higher than 330. It also has self-supporting fuel element spacer grids, which are collapsible sheaths attached to them with fewer than 13 welded end stoppers, The number of these fuel rods is higher than 43. The length of the module is the largest compatible length with the refuelling machine, to reduce the hydraulic restrictions caused by structural endings, and to be able to balance this by providing a fuel element having a larger cooling area. This will maintain the hydraulic restriction and the current total fuel mass in the channel.
The modular fuel element may contain fuel material combinations with different uranium and/or plutonium isotopic concentrations, and/or any other nuclear fuel material (actinides, nuclear poisons, fission products or fuel material coming from other nuclear reactors.
The utilisation of the fuel modules individually in the pressurised heavy water reactors with horizontal fuel channels is an application of the present invention. Another application would involve the assembling of several fuel modules in nuclear reactors with vertical fuel channels.
The modular fuel element may contain fuel material combinations with different uranium and/or plutonium isotopic concentrations, and/or any other nuclear fuel material (actinides, nuclear poisons, fission products or fuel material coming from other nuclear reactors.
The utilisation of the fuel modules individually in the pressurised heavy water reactors with horizontal fuel channels is an application of the present invention. Another application would involve the assembling of several fuel modules in nuclear reactors with vertical fuel channels.
Claims (14)
1. A modular fuel element adaptable to different nuclear power plants with cooling channels comprising a cluster of parallel fuel rods mounted as circular concentric crowns and supported by structural systems, which can be used in said nuclear power plants with horizontal channels. It comprises a cylindrical bar or fuel rod array placed so that the ratio of the heat transfer area to the fuel rod transverse area (both defined per unit length) is higher that 330. These cylindrical fuel rods have a single diameter.
2. A modular fuel element as claimed in claim 1, wherein said ratio of the heat transfer area to the rod transverse area is higher than 360.
3. A nuclear modular fuel element as claimed in claim 1 or 2, wherein the length of the fuel element is the largest compatible length with the refuelling machine.
4. A modular fuel element as claimed in claim 3, wherein said length of the fuel element is higher than o.5 metre, and smaller or equal to approximately 1.0 metre.
5. A modular fuel element as claimed in claim 1, 2, 3, or 4, further comprising self-supporting fuel element spacer grids. These are collapsible sheaths attached to them by fewer than 20 welded end stoppers, whereas the intermediate longitudinal positions are not welded to the sheaths.
6. A modular fuel element as claimed in claim 1, 2, 3, 4, or 5 wherein said number of welded end stoppers is smaller than 13.
7. A modular fuel element adaptable to different nuclear power plants with channels as claimed in claim 1, 2, 3, 4, 5, or 6 claims, wherein said number of the fuel rods is higher than 43, and its single diameter is smaller than 11 mm.
8. A modular fuel element as claimed in claim 7, further comprising 52 parallel fuel rods, which are arranged in four concentric rings, said arrangement comprising three self-supporting spacer grids with rigid and flexible fuel rod pads fixing their relative position.
9. A modular fuel element as claimed in claim 1, 2, 3, 4, 5, 6, 7, or 8 wherein bearing pads are welded to said self-supporting spacer grids therein providing a supporting place on the fuel channels, when used in horizontal channel nuclear power plants.
10.A modular fuel element as claimed in claim 1 2, 3, 4, 5, or 6, wherein said modular fuel element can be adapted to nuclear power plants with heavy water vertical channels. Further comprising a dismountable coupling between modules adaptable to the total length of said fuel elements.
11.A modular fuel element as claimed in claim 10, wherein said coupling system provides a fitting media between the end plates, further enabling several fuel elements to be bound together to form a longer fuel element.
12.A modular fuel element as claimed in claim 10, wherein said coupling system is an outer body, forming a longer fuel element by attaching several said fuel modules
13.A modular fuel element as claimed in claim 10, wherein said coupling system has an inner-fitting element, adaptable to another said fuel module, therein forming a longer fuel element.
14.A modular fuel element as claimed in claim 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, or 13, containing fuel material combinations with different uranium and/or plutonium isotopic concentrations, and/or any other nuclear fuel material (actinides, nuclear poisons, fission products or fuel material coming from other nuclear reactors).
Applications Claiming Priority (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| ARP990102054A AR019129A1 (en) | 1999-05-03 | 1999-05-03 | ADAPTABLE MODULAR FUEL ELEMENT FOR DIFFERENT NUCLEAR CHANNEL CENTERS. |
| ARP99-01-02054 | 1999-05-03 |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CA2307402A1 true CA2307402A1 (en) | 2000-11-03 |
| CA2307402C CA2307402C (en) | 2012-03-20 |
Family
ID=45606592
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CA2307402A Expired - Fee Related CA2307402C (en) | 1999-05-03 | 2000-05-02 | Modular fuel element adaptable to different nuclear power plants with cooling channels |
Country Status (4)
| Country | Link |
|---|---|
| CN (1) | CN1272674A (en) |
| AR (1) | AR019129A1 (en) |
| CA (1) | CA2307402C (en) |
| RO (1) | RO120363B1 (en) |
Families Citing this family (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN106448749B (en) * | 2016-09-23 | 2018-01-05 | 中广核研究院有限公司 | fuel pellet and preparation method thereof |
| CN106695097B (en) * | 2016-12-28 | 2019-01-08 | 中核北方核燃料元件有限公司 | A kind of end plate welding equipment of nuclear fuel cluster |
| CN110534213B (en) * | 2019-09-04 | 2022-09-27 | 哈尔滨工程大学 | Heat pipe cooling mixed fuel reactor system |
| CN113118682B (en) * | 2019-12-30 | 2023-04-14 | 中核北方核燃料元件有限公司 | Split rod bundle clamp for automatic end plate welding |
-
1999
- 1999-05-03 AR ARP990102054A patent/AR019129A1/en active IP Right Grant
-
2000
- 2000-04-28 RO ROA200000457A patent/RO120363B1/en unknown
- 2000-04-30 CN CN00108235A patent/CN1272674A/en active Pending
- 2000-05-02 CA CA2307402A patent/CA2307402C/en not_active Expired - Fee Related
Also Published As
| Publication number | Publication date |
|---|---|
| AR019129A1 (en) | 2001-12-26 |
| CN1272674A (en) | 2000-11-08 |
| CA2307402C (en) | 2012-03-20 |
| RO120363B1 (en) | 2005-12-30 |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| EEER | Examination request | ||
| MKLA | Lapsed |
Effective date: 20140502 |