UST920001I4 - Cooper method and apparatus for removing iodine from a nuclear reactor coolant - Google Patents
Cooper method and apparatus for removing iodine from a nuclear reactor coolant Download PDFInfo
- Publication number
- UST920001I4 UST920001I4 US920001DH UST920001I4 US T920001 I4 UST920001 I4 US T920001I4 US 920001D H US920001D H US 920001DH US T920001 I4 UST920001 I4 US T920001I4
- Authority
- US
- United States
- Prior art keywords
- iodine
- reactor coolant
- nuclear reactor
- removing iodine
- cooper
- 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
- 229910052740 iodine Inorganic materials 0.000 title abstract description 13
- 239000011630 iodine Substances 0.000 title abstract description 13
- 239000002826 coolant Substances 0.000 title abstract description 5
- 238000000034 method Methods 0.000 title abstract description 5
- ZCYVEMRRCGMTRW-UHFFFAOYSA-N 7553-56-2 Chemical compound [I] ZCYVEMRRCGMTRW-UHFFFAOYSA-N 0.000 title description 6
- PNDPGZBMCMUPRI-UHFFFAOYSA-N iodine Chemical compound II PNDPGZBMCMUPRI-UHFFFAOYSA-N 0.000 abstract description 7
- 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 4
- 239000007788 liquid Substances 0.000 abstract description 4
- 229910052708 sodium Inorganic materials 0.000 abstract description 4
- 239000011734 sodium Substances 0.000 abstract description 4
- 230000002285 radioactive effect Effects 0.000 abstract description 3
- PNDPGZBMCMUPRI-HVTJNCQCSA-N 10043-66-0 Chemical compound [131I][131I] PNDPGZBMCMUPRI-HVTJNCQCSA-N 0.000 abstract description 2
- ZCYVEMRRCGMTRW-YPZZEJLDSA-N iodine-125 Chemical compound [125I] ZCYVEMRRCGMTRW-YPZZEJLDSA-N 0.000 abstract description 2
- 229940044173 iodine-125 Drugs 0.000 abstract description 2
- 238000001556 precipitation Methods 0.000 abstract description 2
- 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
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Measurement Of Radiation (AREA)
- Organic Low-Molecular-Weight Compounds And Preparation Thereof (AREA)
- Exposure Of Semiconductors, Excluding Electron Or Ion Beam Exposure (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
A METHOD AND APPARATUS FOR REMOVING IODINE-131 AND IODINE-125 FROM A LIQUID SODIUM REACTOR COOLANT. NONRADIOCATIVE IODINE IS DISSSOLVED IN HOT LIQUID SODIUM TO INCREASE THE TOTAL IODINE CONCENTRATION. SUBSEQUENT PRECIPITATION OF THE IODINE IN A COLD TRAP REMOVES BOTH THE RADIOACTIVE IODINE ISOTOPES AS WELL AS THE NON-RADIOACTIVE IODINE.
Description
DEFENSIVE PUBLICATION UNITED STATES PATENT OFFICE Published at the request of the applicant or owner in accordance with the Notice of Dec. 18, 1969, 869 0.8. 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 tor inspection and reproduction may be purchased for 30 cents a sheet.
Defensive Publication applications have not been examined as to the merits oi! alleged invention. The Patent Oflice makes no assertion as to the novelty of the disclosed subject matter.
PUBLISHED MARCH 5, 197i T920,001 METHOD AND APPARATUS FOR REMOVING IODINE FROM A NUCLEAR REACTOR COOLANT Martin H. Cooper, Monroeville, Pa., assignor to Westinghouse Elecn'ic Corporation, Pittsburgh, Pa. Filed June 15, 1972, Ser. No. 263,054 Int. Cl. C01b 7/14; G21c 19/30 US. Cl. 176-37 1 Sheet Drawing. 14 Pages Specification A method and apparatus for removing iodine-131 and iodine-125 from a liquid sodium reactor coolant. Nonradioactive iodine is dissolved in hot liquid sodium to increase the total iodine concentration. Subsequent precip itation of the iodine in a cold trap removes both the radioactive iodine isotopes as well as the non-radioactive iodine.
. M. H. COOPER METHOD AND APPARATUS FOR REMOVING IODINE March 5, 1974 FROM A NUCLEAR REACTOR COOLANT Filgd June 15, 1972 lllll mfloo. 023000 Ar 4wwww mm3mmmmm 1064mm 20mm
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| US26305472A | 1972-06-15 | 1972-06-15 |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| UST920001I4 true UST920001I4 (en) | 1974-03-05 |
Family
ID=23000186
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| US920001D Pending UST920001I4 (en) | 1972-06-15 | 1972-06-15 | Cooper method and apparatus for removing iodine from a nuclear reactor coolant |
Country Status (6)
| Country | Link |
|---|---|
| US (1) | UST920001I4 (en) |
| JP (1) | JPS4950398A (en) |
| DE (1) | DE2329899A1 (en) |
| FR (1) | FR2189820B1 (en) |
| GB (1) | GB1395431A (en) |
| IT (1) | IT993574B (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4088533A (en) | 1977-01-18 | 1978-05-09 | The United States Of America As Represented By The United States Department Of Energy | Radionuclide trap |
| US4202730A (en) | 1977-01-18 | 1980-05-13 | The United States Of America As Represented By The Department Of Energy | Radionuclide deposition control |
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 |
| JPS57116296A (en) * | 1981-01-13 | 1982-07-20 | Tokyo Shibaura Electric Co | Impurity removing device |
| JPS57117678U (en) * | 1981-01-14 | 1982-07-21 | ||
| USH262H (en) * | 1983-11-25 | 1987-05-05 | The United States Of America As Represented By The United States Department Of Energy | Method of and apparatus for removing silicon from a high temperature sodium coolant |
| DE19638659C1 (en) * | 1996-09-20 | 1998-02-12 | Siemens Ag | Process and system for reducing the risk of leakage of radioactive iodine when revising primary circuit components of a nuclear power plant |
Family Cites Families (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB985400A (en) * | 1960-12-30 | 1965-03-10 | Atomic Energy Authority Uk | Improvements in or relating to radioactive materials extraction processes |
| FR2184516B1 (en) * | 1972-05-19 | 1978-09-01 | Labo Electronique Physique |
-
1972
- 1972-06-15 US US920001D patent/UST920001I4/en active Pending
-
1973
- 1973-05-29 GB GB2547673A patent/GB1395431A/en not_active Expired
- 1973-06-12 DE DE2329899A patent/DE2329899A1/en active Pending
- 1973-06-15 FR FR7321911A patent/FR2189820B1/fr not_active Expired
- 1973-06-15 IT IT25395/73A patent/IT993574B/en active
- 1973-06-15 JP JP48067026A patent/JPS4950398A/ja active Pending
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4088533A (en) | 1977-01-18 | 1978-05-09 | The United States Of America As Represented By The United States Department Of Energy | Radionuclide trap |
| US4202730A (en) | 1977-01-18 | 1980-05-13 | The United States Of America As Represented By The Department Of Energy | Radionuclide deposition control |
Also Published As
| Publication number | Publication date |
|---|---|
| IT993574B (en) | 1975-09-30 |
| GB1395431A (en) | 1975-05-29 |
| JPS4950398A (en) | 1974-05-16 |
| FR2189820A1 (en) | 1974-01-25 |
| FR2189820B1 (en) | 1976-04-30 |
| DE2329899A1 (en) | 1974-01-03 |
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