FR1386117A - Procédé et dispositif pour supprimer certains effets de perte de charge dans des canaux de réacteur nucléaire parcourus par un liquide - Google Patents
Procédé et dispositif pour supprimer certains effets de perte de charge dans des canaux de réacteur nucléaire parcourus par un liquideInfo
- Publication number
- FR1386117A FR1386117A FR968284A FR968284A FR1386117A FR 1386117 A FR1386117 A FR 1386117A FR 968284 A FR968284 A FR 968284A FR 968284 A FR968284 A FR 968284A FR 1386117 A FR1386117 A FR 1386117A
- Authority
- FR
- France
- Prior art keywords
- liquid
- pressure drop
- nuclear reactor
- certain pressure
- suppressing certain
- 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.)
- Expired
Links
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/02—Details of handling arrangements
- G21C19/04—Means for controlling flow of coolant over objects being handled; Means for controlling flow of coolant through channel being serviced, e.g. for preventing "blow-out"
-
- B—PERFORMING OPERATIONS; TRANSPORTING
- B30—PRESSES
- B30B—PRESSES IN GENERAL
- B30B1/00—Presses, using a press ram, characterised by the features of the drive therefor, pressure being transmitted directly, or through simple thrust or tension members only, to the press ram or platen
- B30B1/10—Presses, using a press ram, characterised by the features of the drive therefor, pressure being transmitted directly, or through simple thrust or tension members only, to the press ram or platen by toggle mechanism
-
- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F16—ENGINEERING ELEMENTS AND UNITS; GENERAL MEASURES FOR PRODUCING AND MAINTAINING EFFECTIVE FUNCTIONING OF MACHINES OR INSTALLATIONS; THERMAL INSULATION IN GENERAL
- F16H—GEARING
- F16H21/00—Gearings comprising primarily only links or levers, with or without slides
- F16H21/10—Gearings comprising primarily only links or levers, with or without slides all movement being in, or parallel to, a single plane
- F16H21/16—Gearings comprising primarily only links or levers, with or without slides all movement being in, or parallel to, a single plane for interconverting rotary motion and reciprocating motion
- F16H21/18—Crank gearings; Eccentric gearings
- F16H21/22—Crank gearings; Eccentric gearings with one connecting-rod and one guided slide to each crank or eccentric
- F16H21/26—Crank gearings; Eccentric gearings with one connecting-rod and one guided slide to each crank or eccentric with toggle action
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactor types
- G21C1/04—Thermal reactors ; Epithermal reactors
- G21C1/06—Heterogeneous reactors, i.e. in which fuel and moderator are separated
- G21C1/14—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor
- G21C1/16—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor moderator and coolant being different or separated, e.g. sodium-graphite reactor, sodium-heavy water reactor or organic coolant-heavy water reactor
- G21C1/18—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor moderator and coolant being different or separated, e.g. sodium-graphite reactor, sodium-heavy water reactor or organic coolant-heavy water reactor coolant being pressurised
- G21C1/20—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor moderator and coolant being different or separated, e.g. sodium-graphite reactor, sodium-heavy water reactor or organic coolant-heavy water reactor coolant being pressurised moderator being liquid, e.g. pressure-tube reactor
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/20—Partitions or thermal insulation between fuel channel and moderator
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/22—Structural association of coolant tubes with headers
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
-
- 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)
- General Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- High Energy & Nuclear Physics (AREA)
- Mechanical Engineering (AREA)
- Organic Low-Molecular-Weight Compounds And Preparation Thereof (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
- Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
BE505010 | 1963-04-11 |
Publications (1)
Publication Number | Publication Date |
---|---|
FR1386117A true FR1386117A (fr) | 1965-01-15 |
Family
ID=42827392
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
FR968284A Expired FR1386117A (fr) | 1963-04-11 | 1964-03-23 | Procédé et dispositif pour supprimer certains effets de perte de charge dans des canaux de réacteur nucléaire parcourus par un liquide |
Country Status (9)
Country | Link |
---|---|
US (1) | US3313708A (fr) |
BE (1) | BE630921A (fr) |
DE (1) | DE1256805B (fr) |
FR (1) | FR1386117A (fr) |
GB (1) | GB1047179A (fr) |
LU (1) | LU45101A1 (fr) |
NL (1) | NL302020A (fr) |
OA (1) | OA00363A (fr) |
SE (1) | SE304561B (fr) |
Family Cites Families (13)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
NL211989A (fr) * | 1955-11-08 | |||
GB796966A (en) * | 1956-01-02 | 1958-06-25 | Parsons C A & Co Ltd | Improvements in and relating to nuclear reactors |
GB858504A (en) * | 1956-05-16 | 1961-01-11 | Babcock & Wilcox Ltd | Improvements relating to nuclear reactors and in the operation thereof |
GB849225A (en) * | 1957-05-13 | 1960-09-21 | Atomic Energy Authority Uk | Improvements in or relating to nuclear reactors |
US3031388A (en) * | 1957-09-17 | 1962-04-24 | Martin Marietta Corp | Fuel element for nuclear reactors |
GB862389A (en) * | 1958-05-06 | 1961-03-08 | Thompson Nuclear Energy Co Ltd | Improvements relating to nuclear reactors |
BE581841A (fr) * | 1958-08-19 | 1900-01-01 | ||
US2977297A (en) * | 1958-09-02 | 1961-03-28 | Ersel A Evans | Reactor fuel assembly |
US2980667A (en) * | 1958-10-31 | 1961-04-18 | Allis Chalmers Mfg Co | Rotating fuel element reactor pump |
FR1212200A (fr) * | 1958-12-15 | 1960-03-22 | Canaux déflecteurs pour barres de combustible d'un réacteur nucléaire | |
US3060111A (en) * | 1959-08-14 | 1962-10-23 | Sherman Jerome | Nuclear reactor |
DE1197559B (fr) * | 1959-10-15 | |||
US3235465A (en) * | 1961-05-16 | 1966-02-15 | Atomic Power Dev Ass Inc | Fuel element hold-down arrangement for nuclear reactors |
-
0
- BE BE630921D patent/BE630921A/xx unknown
- NL NL302020D patent/NL302020A/xx unknown
-
1963
- 1963-12-23 LU LU45101D patent/LU45101A1/xx unknown
-
1964
- 1964-01-20 SE SE674/64A patent/SE304561B/xx unknown
- 1964-03-03 DE DEE26527A patent/DE1256805B/de active Pending
- 1964-03-23 FR FR968284A patent/FR1386117A/fr not_active Expired
- 1964-03-25 US US354710A patent/US3313708A/en not_active Expired - Lifetime
- 1964-04-10 GB GB14971/64A patent/GB1047179A/en not_active Expired
- 1964-10-06 OA OA50428A patent/OA00363A/fr unknown
Also Published As
Publication number | Publication date |
---|---|
DE1256805B (de) | 1967-12-21 |
US3313708A (en) | 1967-04-11 |
NL302020A (fr) | 1900-01-01 |
LU45101A1 (fr) | 1964-02-24 |
GB1047179A (en) | 1966-11-02 |
OA00363A (fr) | 1966-05-15 |
BE630921A (fr) | 1900-01-01 |
SE304561B (fr) | 1968-09-30 |
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