FR1222856A - Réacteur nucléaire à eau lourde et à liquide organique comme liquide de refroidissement - Google Patents
Réacteur nucléaire à eau lourde et à liquide organique comme liquide de refroidissementInfo
- Publication number
- FR1222856A FR1222856A FR785728A FR785728A FR1222856A FR 1222856 A FR1222856 A FR 1222856A FR 785728 A FR785728 A FR 785728A FR 785728 A FR785728 A FR 785728A FR 1222856 A FR1222856 A FR 1222856A
- Authority
- FR
- France
- Prior art keywords
- coolant
- nuclear reactor
- organic liquid
- heavy water
- heavy
- 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
- 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
- G21C15/04—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from fissile or breeder material
- G21C15/06—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from fissile or breeder material in fuel elements
-
- 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
-
- 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
- G21C15/20—Partitions or thermal insulation between fuel channel and moderator
-
- 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
- G21C3/08—Casings; Jackets provided with external means to promote heat-transfer, e.g. fins, baffles
-
- 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
- G21C3/38—Fuel units consisting of a single fuel element in a supporting sleeve or in another supporting element
-
- 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
- G21C1/08—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling water reactor, integral super-heat reactor, pressurised water reactor
- G21C1/10—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling water reactor, integral super-heat reactor, pressurised water reactor moderator and coolant being different or separated
- G21C1/12—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling water reactor, integral super-heat reactor, pressurised water reactor moderator and coolant being different or separated moderator being solid, e.g. Magnox reactor or gas-graphite reactor
-
- 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)
- Production Of Liquid Hydrocarbon Mixture For Refining Petroleum (AREA)
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
US71301458A | 1958-02-03 | 1958-02-03 |
Publications (1)
Publication Number | Publication Date |
---|---|
FR1222856A true FR1222856A (fr) | 1960-06-14 |
Family
ID=24864428
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
FR785728A Expired FR1222856A (fr) | 1958-02-03 | 1959-02-02 | Réacteur nucléaire à eau lourde et à liquide organique comme liquide de refroidissement |
Country Status (4)
Country | Link |
---|---|
BE (1) | BE600097A (fr) |
CH (1) | CH380252A (fr) |
ES (1) | ES246790A1 (fr) |
FR (1) | FR1222856A (fr) |
Cited By (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US3309280A (en) * | 1964-12-24 | 1967-03-14 | Leonard J Balog | Pressure-tube nuclear reactor including fuel assembly with thermal baffle |
DE1237232B (de) * | 1961-06-26 | 1967-03-23 | Sulzer Ag | Atomkernreaktor mit von Reaktorkuehlmittel durchstroemten Druckrohren |
US3311540A (en) * | 1964-05-28 | 1967-03-28 | Westinghouse Electric Corp | Integral boiling and superheating nuclear reactor and pressure tube assembly therefor |
FR2652190A1 (fr) * | 1989-09-15 | 1991-03-22 | Babcock & Wilcox Co | Perfectionnements apportes aux reacteurs nucleaires. |
-
1959
- 1959-01-27 ES ES0246790A patent/ES246790A1/es not_active Expired
- 1959-02-02 FR FR785728A patent/FR1222856A/fr not_active Expired
- 1959-02-03 CH CH6906559A patent/CH380252A/de unknown
-
1961
- 1961-02-10 BE BE600097A patent/BE600097A/fr unknown
Cited By (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE1237232B (de) * | 1961-06-26 | 1967-03-23 | Sulzer Ag | Atomkernreaktor mit von Reaktorkuehlmittel durchstroemten Druckrohren |
US3311540A (en) * | 1964-05-28 | 1967-03-28 | Westinghouse Electric Corp | Integral boiling and superheating nuclear reactor and pressure tube assembly therefor |
US3309280A (en) * | 1964-12-24 | 1967-03-14 | Leonard J Balog | Pressure-tube nuclear reactor including fuel assembly with thermal baffle |
FR2652190A1 (fr) * | 1989-09-15 | 1991-03-22 | Babcock & Wilcox Co | Perfectionnements apportes aux reacteurs nucleaires. |
Also Published As
Publication number | Publication date |
---|---|
BE600097A (fr) | 1961-08-10 |
ES246790A1 (es) | 1959-06-01 |
CH380252A (de) | 1964-07-31 |
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