GB1404282A - Method of removing fission products from a nuclear reactor coolant - Google Patents
Method of removing fission products from a nuclear reactor coolantInfo
- Publication number
- GB1404282A GB1404282A GB4406573A GB4406573A GB1404282A GB 1404282 A GB1404282 A GB 1404282A GB 4406573 A GB4406573 A GB 4406573A GB 4406573 A GB4406573 A GB 4406573A GB 1404282 A GB1404282 A GB 1404282A
- Authority
- GB
- United Kingdom
- Prior art keywords
- vessel
- coolant
- reactants
- fission products
- monitor
- 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
- G21C19/28—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
- G21C19/31—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 for molten metals
- G21C19/313—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 for molten metals using cold traps
-
- 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
- G21C19/31—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 for molten metals
-
- 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)
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Manufacture And Refinement Of Metals (AREA)
- Measurement Of Radiation (AREA)
- Medicines Containing Antibodies Or Antigens For Use As Internal Diagnostic Agents (AREA)
Abstract
1404282 Nuclear reactors WESTINGHOUSE ELECTRIC CORP 20 Sept 1973 [28 Sept 1972] 44065/73 Heading G6C Fission products are removed from the coolant of a nuclear reactor by passing the coolant in a flow loop connected to the reactor primary circuit 12, the coolant being conducted through a first vessel 22 at a relatively high temperature, where it picks up precipitation-facilitating reactants, and then through a second vessel 24 at a relatively low temperature, where reactants and fission products are precipitated, and, when the reactants in the first vessel are substantially exhausted, the flow direction is reversed so that coolant passes first through the second vessel 24 at a relatively high temperature, where reactants and fission products become re-dissolved in the coolant, and then through the first vessel 22 at a relatively low temperature, where reactants and fission products are precipitated. The direction of flow is determined by the settings of various valves 18-20 which are switched automatically by means of a monitor 25 which senses the radio-active impurity concentration in the loop between the two vessels 22, 24 and hence assesses when the reactant contents of the appropriate vessel 22 or 24 has fallen to a level requiring flow reversal. Automatic switching is also effected by the monitor 25 to change the mode of operation of the appropriate vessel 22 or 24 from hot to cold and vice versa. Wire mesh within the vessels, and on which the deposits collect, are replaced as necessary when indicated by a monitor 26 on the output side of the loop. Where the reactor is a fast breeder employing liquid sodium as coolant, the reactants comprise NaH, Na 2 O, and NaI for removal of tritium, Ba-140, Cs-134, Cs-137; Cs-141, Zr-95, I-125 and I-131.
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| US29323872A | 1972-09-28 | 1972-09-28 |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| GB1404282A true GB1404282A (en) | 1975-08-28 |
Family
ID=23128278
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| GB4406573A Expired GB1404282A (en) | 1972-09-28 | 1973-09-20 | Method of removing fission products from a nuclear reactor coolant |
Country Status (5)
| Country | Link |
|---|---|
| US (1) | UST921016I4 (en) |
| JP (1) | JPS5231516B2 (en) |
| DE (1) | DE2348804A1 (en) |
| FR (1) | FR2209176B1 (en) |
| GB (1) | GB1404282A (en) |
Families Citing this family (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CA1071415A (en) * | 1975-09-18 | 1980-02-12 | The Government Of The United States As Represented By The United States Department Of Energy | Method for the recovery of halogens from sodium |
| JPS5450800A (en) * | 1977-09-30 | 1979-04-20 | Toshiba Corp | Removing device of radioactive substance |
| JPS5480216A (en) * | 1977-12-09 | 1979-06-26 | Hitachi Ltd | Operation method for liquid metal cooled reactor |
| CN106898406B (en) * | 2017-02-28 | 2019-01-29 | 中国核动力研究设计院 | A kind of preparation method of radioactivity iodine-125 and continuous circulation loop device |
| CN114167171A (en) * | 2021-11-22 | 2022-03-11 | 中国原子能科学研究院 | High-temperature fission chamber detection device and high-temperature fission chamber detection system |
-
1972
- 1972-09-28 US US921016D patent/UST921016I4/en active Pending
-
1973
- 1973-09-18 JP JP48104643A patent/JPS5231516B2/ja not_active Expired
- 1973-09-20 GB GB4406573A patent/GB1404282A/en not_active Expired
- 1973-09-27 FR FR7334636A patent/FR2209176B1/fr not_active Expired
- 1973-09-28 DE DE19732348804 patent/DE2348804A1/en active Pending
Also Published As
| Publication number | Publication date |
|---|---|
| DE2348804A1 (en) | 1974-04-04 |
| UST921016I4 (en) | 1974-04-16 |
| FR2209176B1 (en) | 1977-05-27 |
| FR2209176A1 (en) | 1974-06-28 |
| JPS4971400A (en) | 1974-07-10 |
| JPS5231516B2 (en) | 1977-08-15 |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PS | Patent sealed [section 19, patents act 1949] | ||
| PCNP | Patent ceased through non-payment of renewal fee |