FR2344931A1 - Nuclear reactor with molten salt combustible - has vacuum chamber for safe extraction of gaseous fission prods. - Google Patents
Nuclear reactor with molten salt combustible - has vacuum chamber for safe extraction of gaseous fission prods.Info
- Publication number
- FR2344931A1 FR2344931A1 FR7607831A FR7607831A FR2344931A1 FR 2344931 A1 FR2344931 A1 FR 2344931A1 FR 7607831 A FR7607831 A FR 7607831A FR 7607831 A FR7607831 A FR 7607831A FR 2344931 A1 FR2344931 A1 FR 2344931A1
- Authority
- FR
- France
- Prior art keywords
- combustible
- salt
- circuit
- nuclear reactor
- molten salt
- 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
- 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
- G21C19/28—Arrangements for introducing fluent material into the reactor core; Arrangements for removing fluent material from the reactor core
- G21C19/30—Arrangements for introducing fluent material into the reactor core; Arrangements for removing fluent material from the reactor core with continuous purification of circulating fluent material, e.g. by extraction of fission products deterioration or corrosion products, impurities, e.g. by cold traps
- G21C19/307—Arrangements for introducing fluent material into the reactor core; Arrangements for removing fluent material from the reactor core with continuous purification of circulating fluent material, e.g. by extraction of fission products deterioration or corrosion products, impurities, e.g. by cold traps specially adapted for liquids
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- 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)
- Manufacture And Refinement Of Metals (AREA)
Abstract
Gaseous fission prods. are extracted from the combustible of a molten combustible salt nuclear reactor. In such a reactor, the combustible, generally Pu fluoride or U fluoride or a mixt. of fluorides of U or Th, dissolved in fluorides of Li-7 and of Be, is used also as heat transfer fluid in a prim. circuit. The circuit includes the reactor core, a pump and an exchanger in which heat is transferred to another molten salt, which exchanges its heat in turn, in a steam generator. Fission reactions produce radioactive gases, e.g. tritium and Xe 135, which must be removed. According to the invention, a reduced press. is established in the upper prt of a chamber fitted in the primary circuit so as to be partly filled with the combustible salt. The reduced press. causes degassing of the combustible. The process is more effective than existing processes, in which the gases are usually extracted by contacting the combustible with helium in the body of the pump, and the helium is purged. In those processes, the extn. is therefore carried out at a point in the prim. circuit where the salt is at the max. press, and the solubility of the gas is greater.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| FR7607831A FR2344931A1 (en) | 1976-03-18 | 1976-03-18 | Nuclear reactor with molten salt combustible - has vacuum chamber for safe extraction of gaseous fission prods. |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| FR7607831A FR2344931A1 (en) | 1976-03-18 | 1976-03-18 | Nuclear reactor with molten salt combustible - has vacuum chamber for safe extraction of gaseous fission prods. |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| FR2344931A1 true FR2344931A1 (en) | 1977-10-14 |
| FR2344931B1 FR2344931B1 (en) | 1978-08-25 |
Family
ID=9170624
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| FR7607831A Granted FR2344931A1 (en) | 1976-03-18 | 1976-03-18 | Nuclear reactor with molten salt combustible - has vacuum chamber for safe extraction of gaseous fission prods. |
Country Status (1)
| Country | Link |
|---|---|
| FR (1) | FR2344931A1 (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN106548811A (en) * | 2015-09-18 | 2017-03-29 | M·谢尔登·汉森 | System and method for providing fusedsalt reactor |
-
1976
- 1976-03-18 FR FR7607831A patent/FR2344931A1/en active Granted
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN106548811A (en) * | 2015-09-18 | 2017-03-29 | M·谢尔登·汉森 | System and method for providing fusedsalt reactor |
Also Published As
| Publication number | Publication date |
|---|---|
| FR2344931B1 (en) | 1978-08-25 |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| ST | Notification of lapse |