UST921014I4 - Colburn mbthod for removing fission products from a nuclear reactor coolant - Google Patents
Colburn mbthod for removing fission products from a nuclear reactor coolant Download PDFInfo
- Publication number
- UST921014I4 UST921014I4 US921014DH UST921014I4 US T921014 I4 UST921014 I4 US T921014I4 US 921014D H US921014D H US 921014DH US T921014 I4 UST921014 I4 US T921014I4
- Authority
- US
- United States
- Prior art keywords
- reactor coolant
- mbthod
- colburn
- nuclear reactor
- fission products
- 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.)
- Pending
Links
- 239000002826 coolant Substances 0.000 title abstract description 4
- 230000004992 fission Effects 0.000 title 1
- DGAQECJNVWCQMB-PUAWFVPOSA-M Ilexoside XXIX Chemical compound C[C@@H]1CC[C@@]2(CC[C@@]3(C(=CC[C@H]4[C@]3(CC[C@@H]5[C@@]4(CC[C@@H](C5(C)C)OS(=O)(=O)[O-])C)C)[C@@H]2[C@]1(C)O)C)C(=O)O[C@H]6[C@@H]([C@H]([C@@H]([C@H](O6)CO)O)O)O.[Na+] DGAQECJNVWCQMB-PUAWFVPOSA-M 0.000 abstract description 6
- 239000007788 liquid Substances 0.000 abstract description 6
- 229910052708 sodium Inorganic materials 0.000 abstract description 6
- 239000011734 sodium Substances 0.000 abstract description 6
- YZCKVEUIGOORGS-NJFSPNSNSA-N Tritium Chemical compound [3H] YZCKVEUIGOORGS-NJFSPNSNSA-N 0.000 abstract description 4
- 229910052722 tritium Inorganic materials 0.000 abstract description 4
- KEAYESYHFKHZAL-UHFFFAOYSA-N Sodium Chemical compound [Na] KEAYESYHFKHZAL-UHFFFAOYSA-N 0.000 abstract description 3
- 229910000104 sodium hydride Inorganic materials 0.000 abstract description 3
- 239000012312 sodium hydride Substances 0.000 abstract description 3
- PNDPGZBMCMUPRI-HVTJNCQCSA-N 10043-66-0 Chemical compound [131I][131I] PNDPGZBMCMUPRI-HVTJNCQCSA-N 0.000 abstract description 2
- UFHFLCQGNIYNRP-UHFFFAOYSA-N Hydrogen Chemical class [H][H] UFHFLCQGNIYNRP-UHFFFAOYSA-N 0.000 abstract description 2
- DNYQQHLXYPAEMP-UHFFFAOYSA-N [I].[Cs] Chemical compound [I].[Cs] DNYQQHLXYPAEMP-UHFFFAOYSA-N 0.000 abstract description 2
- TVFDJXOCXUVLDH-RNFDNDRNSA-N cesium-137 Chemical compound [137Cs] TVFDJXOCXUVLDH-RNFDNDRNSA-N 0.000 abstract description 2
- 229910052739 hydrogen Inorganic materials 0.000 abstract description 2
- 239000001257 hydrogen Substances 0.000 abstract description 2
- 239000012535 impurity Substances 0.000 abstract description 2
- 238000000034 method Methods 0.000 abstract description 2
- 150000004678 hydrides Chemical class 0.000 abstract 1
- 238000007689 inspection Methods 0.000 description 1
Images
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
-
- 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
Definitions
- PUBLISHED APRIL 16, 1974 coouNo svsym ems A method for removing cesium 137, iodine 131 and tritium from a liquid sodium reactor coolant. Hydrogen is introduced into the liquid sodium causing sodium hydride to precipitate in a cold trap. The cesium iodine and tritium isotopes are removed from the liquid sodium by coprecipitating as impurities in the sodium hydride.
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
- Treating Waste Gases (AREA)
Abstract
A METHOD FOR REMOVING CESIUM 137, IODINE 131 AND TRITIUM FROM A LIQUID SODIUM REACTOR COOLANT. HYDROGEN IS INTRODUCED INTO THE LIQUID SODIUM CAUSING SODIUM HYDRIDE TO PRECIPITATE IN A COLD TRAP. THE CESIUM IODINE AND TRITIUM ISOTOPES ARE REMOVED FROM THE LIQUID SODIUM BY COPRECIPITATING AS IMPURITIES IN THE SODIUMM HYDRIDE.
Description
DEFENSIVE PULICATION UNITED STATES PATENT OFFICE Published at the request of the applicant or owner in accordance with the Notice of Dec. 16, 1969, 869 0.G. 687. The abstracts of Defensive Publication applications are identified by distinctly numbered series and are arranged chronologically. The heading of each abstract indicates the number of pages of specification, including claims and sheets of drawings contained in the application as originally filed. The files of these applications are available to the public for inspection and reproduction may be purchased for 30 cents a sheet.
Defensive Publication applications have not been examined as to the merits of alleged invention. The Patent Oflice makes no assertion as to the novelty of the disclosed subject matter.
PUBLISHED APRIL 16, 1974 coouNo svsym ems A method for removing cesium 137, iodine 131 and tritium from a liquid sodium reactor coolant. Hydrogen is introduced into the liquid sodium causing sodium hydride to precipitate in a cold trap. The cesium iodine and tritium isotopes are removed from the liquid sodium by coprecipitating as impurities in the sodium hydride.
April 16, 1974 A NUCLEAR REACTOR COOLANT Filed June @551 1 M9365 I 53356 RE 562,206 Em 38 Em \m \v 360 360 2596 f @2308 ozjooo
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| US26147672A | 1972-06-09 | 1972-06-09 |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| UST921014I4 true UST921014I4 (en) | 1974-04-16 |
Family
ID=22993472
Family Applications (2)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| US921014D Pending UST921014I4 (en) | 1972-06-09 | 1972-06-09 | Colburn mbthod for removing fission products from a nuclear reactor coolant |
| US05/493,368 Expired - Lifetime US4075060A (en) | 1972-06-09 | 1974-07-31 | Method for removing fission products from a nuclear reactor coolant |
Family Applications After (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| US05/493,368 Expired - Lifetime US4075060A (en) | 1972-06-09 | 1974-07-31 | Method for removing fission products from a nuclear reactor coolant |
Country Status (6)
| Country | Link |
|---|---|
| US (2) | UST921014I4 (en) |
| JP (1) | JPS5232436B2 (en) |
| DE (1) | DE2328660A1 (en) |
| FR (1) | FR2188252B1 (en) |
| GB (1) | GB1393355A (en) |
| IT (1) | IT993570B (en) |
Families Citing this family (14)
| 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 |
| DE2746159A1 (en) * | 1977-10-14 | 1979-04-19 | Interatom | NUCLEAR ENERGY SYSTEM WITH EQUIPMENT FOR COOLANT CLEANING |
| JPS5480216A (en) * | 1977-12-09 | 1979-06-26 | Hitachi Ltd | Operation method for liquid metal cooled reactor |
| DE2828153C3 (en) * | 1978-06-27 | 1984-07-26 | Kraftwerk Union AG, 4330 Mülheim | Nuclear reactor with a liquid coolant |
| DE3017585C2 (en) * | 1980-05-08 | 1984-05-30 | Brown Boveri Reaktor GmbH, 6800 Mannheim | Process and arrangement for lowering the pressure in the containment of a nuclear reactor plant |
| JPS5845600A (en) * | 1981-09-11 | 1983-03-16 | 動力炉・核燃料開発事業団 | Method of removing hydrogen from fast breeder secondary system |
| US4587083A (en) * | 1983-08-10 | 1986-05-06 | The United States Of America As Represented By The United States Department Of Energy | Method for removing cesium from a nuclear reactor coolant |
| US6272226B1 (en) | 1997-04-02 | 2001-08-07 | Scientific-Atlanta, Inc. | Apparatus and method for masking audio signals in a signal distribution system |
| FR2859042B1 (en) * | 2003-08-19 | 2005-11-18 | Framatome Anp | PROCESS AND PLANT FOR PROCESSING ALKALINE METALS CHARGED WITH TRITIUM OR COMPONENTS SUBJECTED BY ALKALINE METALS CHARGED WITH TRITIUM |
| RU2614048C1 (en) * | 2016-03-18 | 2017-03-22 | Российская Федерация, от имени которой выступает Государственная корпорация по атомной энергии "Росатом" | Nuclear power plant with heat carrier cleaning system |
| US12431253B2 (en) | 2023-06-21 | 2025-09-30 | Abilene Christian University | Fission product extraction system and methods of use thereof |
| WO2025029454A2 (en) | 2023-07-31 | 2025-02-06 | Abilene Christian University | Methods for the purification of molybdenum-99 with phase transfer agents |
| WO2025072644A1 (en) * | 2023-09-29 | 2025-04-03 | Abilene Christian University | Separation of fission products in a molten salt reactor via adsorbent frameworks |
Family Cites Families (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US2745552A (en) * | 1953-09-02 | 1956-05-15 | Warren H Bruggeman | Filter with fractional crystallization means |
| GB1285088A (en) * | 1969-12-18 | 1972-08-09 | Atomic Energy Authority Uk | Cold traps for liquid metal |
-
1972
- 1972-06-09 US US921014D patent/UST921014I4/en active Pending
-
1973
- 1973-05-29 GB GB2547373A patent/GB1393355A/en not_active Expired
- 1973-06-06 DE DE2328660A patent/DE2328660A1/en active Pending
- 1973-06-07 FR FR7320720A patent/FR2188252B1/fr not_active Expired
- 1973-06-08 JP JP48064024A patent/JPS5232436B2/ja not_active Expired
- 1973-06-12 IT IT25211/73A patent/IT993570B/en active
-
1974
- 1974-07-31 US US05/493,368 patent/US4075060A/en not_active Expired - Lifetime
Also Published As
| Publication number | Publication date |
|---|---|
| DE2328660A1 (en) | 1974-01-10 |
| FR2188252B1 (en) | 1976-05-07 |
| JPS5232436B2 (en) | 1977-08-22 |
| US4075060A (en) | 1978-02-21 |
| IT993570B (en) | 1975-09-30 |
| JPS4962898A (en) | 1974-06-18 |
| FR2188252A1 (en) | 1974-01-18 |
| GB1393355A (en) | 1975-05-07 |
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