FR2111642A1 - Support and separation of nuclear fuel needles - in a heat exchanger,by system of plates - Google Patents
Support and separation of nuclear fuel needles - in a heat exchanger,by system of platesInfo
- Publication number
- FR2111642A1 FR2111642A1 FR7036995A FR7036995A FR2111642A1 FR 2111642 A1 FR2111642 A1 FR 2111642A1 FR 7036995 A FR7036995 A FR 7036995A FR 7036995 A FR7036995 A FR 7036995A FR 2111642 A1 FR2111642 A1 FR 2111642A1
- Authority
- FR
- France
- Prior art keywords
- plates
- needles
- casing
- separation
- support
- 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
-
- 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
- G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
- G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
- G21C3/322—Means to influence the coolant flow through or around the bundles
-
- 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
- G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
- G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
- G21C3/336—Spacer elements for fuel rods in the bundle
-
- 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)
- Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)
Abstract
Fuel needles in a fast reactor during the heat exchange process are supported and separated by sets of identical plates fixed at regular intervals onto a collar to just fit inside the regular n-sided casing of the system. The plates are both perpendicular to and inclined to the axis of the casing at different stages and the sets join each other and form a rigid structure. Holes in the plates are not the same shape as the needles section. This arrangement mixes the coolant effectively and allows for differential expansion between the needles and the casing.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
FR7036995A FR2111642A1 (en) | 1970-10-13 | 1970-10-13 | Support and separation of nuclear fuel needles - in a heat exchanger,by system of plates |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
FR7036995A FR2111642A1 (en) | 1970-10-13 | 1970-10-13 | Support and separation of nuclear fuel needles - in a heat exchanger,by system of plates |
Publications (2)
Publication Number | Publication Date |
---|---|
FR2111642A1 true FR2111642A1 (en) | 1972-06-09 |
FR2111642B1 FR2111642B1 (en) | 1974-04-26 |
Family
ID=9062675
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
FR7036995A Granted FR2111642A1 (en) | 1970-10-13 | 1970-10-13 | Support and separation of nuclear fuel needles - in a heat exchanger,by system of plates |
Country Status (1)
Country | Link |
---|---|
FR (1) | FR2111642A1 (en) |
Cited By (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR2349825A1 (en) * | 1976-04-30 | 1977-11-25 | Interatom | INSTALLATION INTENDED TO ACHIEVE, IN A FLOWING FLUID, IN PARTICULAR IN THE CASE OF A NUCLEAR REACTOR, CONDITIONS ALLOWING TO MEASURE A REPRESENTATIVE TEMPERATURE |
EP0036142A1 (en) * | 1980-03-17 | 1981-09-23 | Ab Asea-Atom | Bundle of fuel elements |
US4514358A (en) * | 1981-03-31 | 1985-04-30 | Ab Asea-Atom | Fuel assembly |
US4587093A (en) * | 1982-07-12 | 1986-05-06 | Ab Asea-Atom | Nuclear fuel assembly |
EP2842134B1 (en) * | 2012-04-26 | 2017-03-22 | Ge-Hitachi Nuclear Energy Americas LLC | Fuel bundle for a liquid metal cooled nuclear reactor |
-
1970
- 1970-10-13 FR FR7036995A patent/FR2111642A1/en active Granted
Cited By (6)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR2349825A1 (en) * | 1976-04-30 | 1977-11-25 | Interatom | INSTALLATION INTENDED TO ACHIEVE, IN A FLOWING FLUID, IN PARTICULAR IN THE CASE OF A NUCLEAR REACTOR, CONDITIONS ALLOWING TO MEASURE A REPRESENTATIVE TEMPERATURE |
EP0036142A1 (en) * | 1980-03-17 | 1981-09-23 | Ab Asea-Atom | Bundle of fuel elements |
US4478786A (en) * | 1980-03-17 | 1984-10-23 | Ab Asea-Atom | Fuel assembly |
US4514358A (en) * | 1981-03-31 | 1985-04-30 | Ab Asea-Atom | Fuel assembly |
US4587093A (en) * | 1982-07-12 | 1986-05-06 | Ab Asea-Atom | Nuclear fuel assembly |
EP2842134B1 (en) * | 2012-04-26 | 2017-03-22 | Ge-Hitachi Nuclear Energy Americas LLC | Fuel bundle for a liquid metal cooled nuclear reactor |
Also Published As
Publication number | Publication date |
---|---|
FR2111642B1 (en) | 1974-04-26 |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
GB1023969A (en) | Buckstay arrangement for furnace walls | |
FR2111642A1 (en) | Support and separation of nuclear fuel needles - in a heat exchanger,by system of plates | |
ES449006A1 (en) | Method of manufacturing a grill-type support comprising two different materials and capable of being initially rigid, while allowing differential thermal expansions after installation | |
ES453573A1 (en) | Nuclear reactor core flow baffling | |
JPS5543400A (en) | Tubeeinnshell type heat exchanger | |
IT961833B (en) | IMPROVEMENT IN THE MATRICES OF GLASS-CERAMIC TUBES FOR EXAMPLE FOR HEAT EXCHANGERS AND RELATED MANUFACTURING PROCESS | |
GB1454972A (en) | Nuclear power plant with closed gas coolant circuit for the production of process heat | |
GB1055325A (en) | Heat exchanger and method of its manufacture | |
ES386075A1 (en) | Corrugated dissipator for tube and dissipator radiator core and process for manufacturing the same | |
BE767288A (en) | PROCESS FOR MANUFACTURING A HEAT DUCT | |
ES195672U (en) | Disposition of heat exchanger module. (Machine-translation by Google Translate, not legally binding) | |
NL161603C (en) | METHOD FOR COOLING A GAS COOLED GRAPHITE MODERATED NUCLEAR REACTOR. | |
NL172494B (en) | PROCESS FOR SHUTDOWN A GAS COOLED HIGH TEMPERATURE NUCLEAR REACTOR. | |
ES411592A1 (en) | Procedure and exchanger to improve the thermal transition between two means separated by a surface of heat exchange. (Machine-translation by Google Translate, not legally binding) | |
FR1412607A (en) | Regenerative heat exchanger, especially for gas turbine units | |
TR17482A (en) | BED FOR SEATING CATI HEATING PLATES, AWAY FROM CATI CEILING | |
GB1513689A (en) | Dual-temperature deuterium exchange apparatus | |
SU515023A1 (en) | Distributor manifold tubular heat exchanger | |
GB1312457A (en) | Nuclear reactor power plant | |
GB992099A (en) | Self-cleaning heat transfer surface in a rotary regenerative heat exchanger | |
NO741725L (en) | Regenerative heat exchanger. | |
GB817963A (en) | Improvements in or relating to heat transfer systems | |
CA977167A (en) | Gas turbine heat exchanging system | |
FR2041724A1 (en) | Gas circuit for gas cooled nuclear reactor | |
FR2294417A1 (en) | Heating and support panel - has internal partitions formed by complementary components fixed to two wall panels |
Legal Events
Date | Code | Title | Description |
---|---|---|---|
ST | Notification of lapse |