CA2352141A1 - Method for nuclear power plant decontamination - Google Patents
Method for nuclear power plant decontamination Download PDFInfo
- Publication number
- CA2352141A1 CA2352141A1 CA002352141A CA2352141A CA2352141A1 CA 2352141 A1 CA2352141 A1 CA 2352141A1 CA 002352141 A CA002352141 A CA 002352141A CA 2352141 A CA2352141 A CA 2352141A CA 2352141 A1 CA2352141 A1 CA 2352141A1
- Authority
- CA
- Canada
- Prior art keywords
- zinc
- water
- oxide
- oxide layer
- metal surface
- 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.)
- Abandoned
Links
- 238000000034 method Methods 0.000 title claims abstract description 25
- 238000005202 decontamination Methods 0.000 title claims abstract description 8
- 230000003588 decontaminative effect Effects 0.000 title claims abstract description 8
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 28
- 229910052751 metal Inorganic materials 0.000 claims abstract description 18
- 239000002184 metal Substances 0.000 claims abstract description 18
- 239000011701 zinc Substances 0.000 claims description 26
- HCHKCACWOHOZIP-UHFFFAOYSA-N Zinc Chemical compound [Zn] HCHKCACWOHOZIP-UHFFFAOYSA-N 0.000 claims description 23
- 229910052725 zinc Inorganic materials 0.000 claims description 23
- XLOMVQKBTHCTTD-UHFFFAOYSA-N Zinc monoxide Chemical compound [Zn]=O XLOMVQKBTHCTTD-UHFFFAOYSA-N 0.000 claims description 18
- PTFCDOFLOPIGGS-UHFFFAOYSA-N Zinc dication Chemical compound [Zn+2] PTFCDOFLOPIGGS-UHFFFAOYSA-N 0.000 claims description 12
- 239000010410 layer Substances 0.000 claims description 10
- 239000011787 zinc oxide Substances 0.000 claims description 9
- 239000002002 slurry Substances 0.000 claims description 5
- 239000007864 aqueous solution Substances 0.000 claims description 4
- 238000002161 passivation Methods 0.000 claims description 2
- 239000000243 solution Substances 0.000 claims description 2
- 239000002344 surface layer Substances 0.000 claims description 2
- 150000002500 ions Chemical class 0.000 abstract 1
- 229910001220 stainless steel Inorganic materials 0.000 description 6
- 239000010935 stainless steel Substances 0.000 description 6
- 230000001464 adherent effect Effects 0.000 description 5
- 239000012857 radioactive material Substances 0.000 description 5
- 230000015572 biosynthetic process Effects 0.000 description 3
- 238000009835 boiling Methods 0.000 description 3
- 229910017052 cobalt Inorganic materials 0.000 description 3
- 239000010941 cobalt Substances 0.000 description 3
- GUTLYIVDDKVIGB-UHFFFAOYSA-N cobalt atom Chemical compound [Co] GUTLYIVDDKVIGB-UHFFFAOYSA-N 0.000 description 3
- 238000005260 corrosion Methods 0.000 description 3
- 230000007797 corrosion Effects 0.000 description 3
- 229940112824 paste Drugs 0.000 description 3
- 239000006072 paste Substances 0.000 description 3
- 230000002285 radioactive effect Effects 0.000 description 3
- 239000000941 radioactive substance Substances 0.000 description 3
- 238000012360 testing method Methods 0.000 description 3
- 238000009825 accumulation Methods 0.000 description 2
- 230000008021 deposition Effects 0.000 description 2
- 238000010348 incorporation Methods 0.000 description 2
- 238000010521 absorption reaction Methods 0.000 description 1
- 230000004913 activation Effects 0.000 description 1
- 239000010953 base metal Substances 0.000 description 1
- 230000008901 benefit Effects 0.000 description 1
- 230000008859 change Effects 0.000 description 1
- 239000011248 coating agent Substances 0.000 description 1
- 238000000576 coating method Methods 0.000 description 1
- 239000000470 constituent Substances 0.000 description 1
- 238000005336 cracking Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 230000005764 inhibitory process Effects 0.000 description 1
- 238000002347 injection Methods 0.000 description 1
- 239000007924 injection Substances 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 230000008569 process Effects 0.000 description 1
- 230000005855 radiation Effects 0.000 description 1
- 230000000717 retained effect Effects 0.000 description 1
- 150000003839 salts Chemical class 0.000 description 1
- 239000012498 ultrapure water Substances 0.000 description 1
- 150000003751 zinc Chemical class 0.000 description 1
- 229940052228 zinc oxide paste Drugs 0.000 description 1
- NDKWCCLKSWNDBG-UHFFFAOYSA-N zinc;dioxido(dioxo)chromium Chemical compound [Zn+2].[O-][Cr]([O-])(=O)=O NDKWCCLKSWNDBG-UHFFFAOYSA-N 0.000 description 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/28—Treating solids
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/02—Devices or arrangements for monitoring coolant or moderator
- G21C17/022—Devices or arrangements for monitoring coolant or moderator for monitoring liquid coolants or moderators
-
- 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
-
- 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)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Plasma & Fusion (AREA)
- Preventing Corrosion Or Incrustation Of Metals (AREA)
- Chemical Treatment Of Metals (AREA)
- Cleaning And De-Greasing Of Metallic Materials By Chemical Methods (AREA)
Abstract
Method effecting decontamination of metal components carrying an oxide layer in a nuclear powered water cooled reactor wherein a low concentration of zin c ions is introduced into the water to cause loosening and removal of the oxid e layer from the metal surface.
Description
N~EETHOD FOR NUCLEAR POWER PLANT
DECQNTAMINATION
The present application relates to a method for decontamination of nuclear power plant systems. More particularly, the invention relates to the use of small amounts of zinc to change the properties of the oxide film present on internal walls and tubing surfaces of nuclear reactors to facilitate removal of radioactive substances such as ~°Co therefrom.
BA~;KGROUND OF THE INVENTION
A major problem in water-cooled nuclear reactors is the accumulation of radioactive substances in the structural portions of the reactor system. For example, during reactor shut-down, workers are exposed to radiation emanating from internal walls and tubing surfaces, and radioactive materials retained in oxide films which have accumulated on these surfaces are a ma,~or source of radiation exposure.
The build-up of radioactive cobalt (~°Co) in recirculation piping of nuclear power reactors, including boiling water reactors, is a major source of radiation exposure, especially during reactor shutdown. Efforts have been made during recent years to identify parameters which affect the rate and magnitude of ~°Co buildup, with a view to developing methods for limiting the buildup. It has been shown in prior work that the msjority of ~°Co buildup in recirculation piping occurs by incorporation into the oxide film during formation of the oxide film on stainless steel surfaces.
U.S. Patent No. 4,950,449 describes the use of zinc ions to remove or lessen deposition of radioactive substances and reduce intergranular stress corrosion cracking in water-cooled nuclear reactors. The zinc may be added in the form of zinc oxide paste, slurry or aqueous solution.
U.S. Patent No. 4,756,874 describes the use of zinc having a Iower content of the ~Zn isotope in order to reduce accumulation of radioactive cobalt without increasing the presence of the 65Zn activation product of ~Zn. The zinc in this form may be added to the reactor water in the form of a zinc salt or zinc oxide.
U.S. Patent No. 4,759,900 relates to the inhibition of deposition of radioactive cobalt by continuous injection of zinc oxide into the reactor water. The zinc oxide may be prepared in the form of a paste, slurry or aqueous solution.
A need exists for reducing the buildup of radioactive materials in nuclear power systems. The present invention seeks to satisfy that need.
DECQNTAMINATION
The present application relates to a method for decontamination of nuclear power plant systems. More particularly, the invention relates to the use of small amounts of zinc to change the properties of the oxide film present on internal walls and tubing surfaces of nuclear reactors to facilitate removal of radioactive substances such as ~°Co therefrom.
BA~;KGROUND OF THE INVENTION
A major problem in water-cooled nuclear reactors is the accumulation of radioactive substances in the structural portions of the reactor system. For example, during reactor shut-down, workers are exposed to radiation emanating from internal walls and tubing surfaces, and radioactive materials retained in oxide films which have accumulated on these surfaces are a ma,~or source of radiation exposure.
The build-up of radioactive cobalt (~°Co) in recirculation piping of nuclear power reactors, including boiling water reactors, is a major source of radiation exposure, especially during reactor shutdown. Efforts have been made during recent years to identify parameters which affect the rate and magnitude of ~°Co buildup, with a view to developing methods for limiting the buildup. It has been shown in prior work that the msjority of ~°Co buildup in recirculation piping occurs by incorporation into the oxide film during formation of the oxide film on stainless steel surfaces.
U.S. Patent No. 4,950,449 describes the use of zinc ions to remove or lessen deposition of radioactive substances and reduce intergranular stress corrosion cracking in water-cooled nuclear reactors. The zinc may be added in the form of zinc oxide paste, slurry or aqueous solution.
U.S. Patent No. 4,756,874 describes the use of zinc having a Iower content of the ~Zn isotope in order to reduce accumulation of radioactive cobalt without increasing the presence of the 65Zn activation product of ~Zn. The zinc in this form may be added to the reactor water in the form of a zinc salt or zinc oxide.
U.S. Patent No. 4,759,900 relates to the inhibition of deposition of radioactive cobalt by continuous injection of zinc oxide into the reactor water. The zinc oxide may be prepared in the form of a paste, slurry or aqueous solution.
A need exists for reducing the buildup of radioactive materials in nuclear power systems. The present invention seeks to satisfy that need.
SUMMLARY OF THE INVENTION
It has been discovered, according to the present invention, that it is possible to introduce changes in the structure of an oxide film present on a metal surface by exposure of the oxide bearing surface to zinc ions at a low concentration, typically 1-3000 part per billion (ppb), more usually 10-100 ppb, over a period of at least 100 hours, typically in the region of 300 hours or more, and at a temperature of at least 450, for example 45~ to 550°F. Such exposure results in the oxide film changing from a tightly adherent l0 structure to a loosely adherent structure that can be removed by the circulating water of the system, thereby facilitating removal of at least a portion of the film, including radioactive materials contained therein. In this way, through changing the structure of the oxide film, the invention provides a way of effecting decontamination of the reactor to reduce the buildup of radioactive materials, including ~°Co buildup, on the inner wall surfaces and recirculation piping of nuclear power boiling water reactors.
It is also possible according to the present invention to incorporate zinc into a passivating oxide film wherein stainless steel, initially free of oxide film, is subjected to high temperature, typically greater than 300°F, high purity water (i.e. water having a quality consistent with that typically found in operating nuclear reactors) used under conditions where the zinc concentration is no higher than 500 ppb for an exposure time greater than or equal to about 100 hours. A passivating film covers the surface of the base metal (e.g. stainless steel) and inhibits subsequent corrosion/oxide formation Under these conditions, an oxide film is produced which is substantially thinner, i.e. usually less than 0.5 microns, more usually less than 0.2 microns, than non-oxide-bearing oxide films formed under similar conditions in the absence of zinc.
Typically, film thicknesses in absence of zinc range from about 1 to 3 microns.
With the thinner films present on a stainless steel surface, it is observed the at Co~° buildup is less than when the oxide film is formed in the absence of zinc. When zinc is present, 6°Co levels are typically less than l OpCi/cm2, while without zinc, the ~°Co levels are typically between about l OpCi/cm2 and SOOpCi/cm2.
Moreover, removal of the loosened oxide layer can be effected by the circulating water in the pipe.
In accordance with one aspect of the present invention, there is provided a method for effecting decontamination of metal components carrying an oxide layer comprising exposing the component to an aqueous solution of zinc ions to cause loosening of the oxide layer from the metal surface.
In accordance with another aspect there is provided a method for effecting decontaminat;en of metal components carrying an oxide layer in a nuclrsr Fowered water cooled reactor comprising introducing a low concentration of zinc ions into the reactor water to cause loosening of the oxide layer from the metal surface.
In accordance with yet another aspect, there is provided a method of passivation of a metal surface comprising immersing 5 the metal surface initially free of oxide surface layer in water at elevated temperature, typically in the region of 230 to 300°C in the presence of zinc at a low concentration for example 1-300 ppb for a time of at east 300 hours. It has been found according to the invention that incorporation of low amounts of zinc in the passivated film limits the buildup of radioactive materials therein, including 6°Co.
The zinc may be added in the form of a salt, for example zinc chromate or zinc oxide. It is also possible to use zinc which has been treated to eliminate or reduce its ~Zn content, such as described in U.S. patent 4,756,874 (herein incorporated by reference). The zinc oxide may be added in any form which permit it to be dissolved in the reactor water, such as by way of a slurry, paste or preformed solution. A paste will typically have a concentration of zinc oxide of about 25% to about 95% by weight, whereas a slurry will have a zinc oxide content in the region of about 0.1% to 20% by weight. Examples of ways in which the zinc oxide is introduced are set forth in U.S. patent 4,756,874, referred to above.
It has been discovered, according to the present invention, that it is possible to introduce changes in the structure of an oxide film present on a metal surface by exposure of the oxide bearing surface to zinc ions at a low concentration, typically 1-3000 part per billion (ppb), more usually 10-100 ppb, over a period of at least 100 hours, typically in the region of 300 hours or more, and at a temperature of at least 450, for example 45~ to 550°F. Such exposure results in the oxide film changing from a tightly adherent l0 structure to a loosely adherent structure that can be removed by the circulating water of the system, thereby facilitating removal of at least a portion of the film, including radioactive materials contained therein. In this way, through changing the structure of the oxide film, the invention provides a way of effecting decontamination of the reactor to reduce the buildup of radioactive materials, including ~°Co buildup, on the inner wall surfaces and recirculation piping of nuclear power boiling water reactors.
It is also possible according to the present invention to incorporate zinc into a passivating oxide film wherein stainless steel, initially free of oxide film, is subjected to high temperature, typically greater than 300°F, high purity water (i.e. water having a quality consistent with that typically found in operating nuclear reactors) used under conditions where the zinc concentration is no higher than 500 ppb for an exposure time greater than or equal to about 100 hours. A passivating film covers the surface of the base metal (e.g. stainless steel) and inhibits subsequent corrosion/oxide formation Under these conditions, an oxide film is produced which is substantially thinner, i.e. usually less than 0.5 microns, more usually less than 0.2 microns, than non-oxide-bearing oxide films formed under similar conditions in the absence of zinc.
Typically, film thicknesses in absence of zinc range from about 1 to 3 microns.
With the thinner films present on a stainless steel surface, it is observed the at Co~° buildup is less than when the oxide film is formed in the absence of zinc. When zinc is present, 6°Co levels are typically less than l OpCi/cm2, while without zinc, the ~°Co levels are typically between about l OpCi/cm2 and SOOpCi/cm2.
Moreover, removal of the loosened oxide layer can be effected by the circulating water in the pipe.
In accordance with one aspect of the present invention, there is provided a method for effecting decontamination of metal components carrying an oxide layer comprising exposing the component to an aqueous solution of zinc ions to cause loosening of the oxide layer from the metal surface.
In accordance with another aspect there is provided a method for effecting decontaminat;en of metal components carrying an oxide layer in a nuclrsr Fowered water cooled reactor comprising introducing a low concentration of zinc ions into the reactor water to cause loosening of the oxide layer from the metal surface.
In accordance with yet another aspect, there is provided a method of passivation of a metal surface comprising immersing 5 the metal surface initially free of oxide surface layer in water at elevated temperature, typically in the region of 230 to 300°C in the presence of zinc at a low concentration for example 1-300 ppb for a time of at east 300 hours. It has been found according to the invention that incorporation of low amounts of zinc in the passivated film limits the buildup of radioactive materials therein, including 6°Co.
The zinc may be added in the form of a salt, for example zinc chromate or zinc oxide. It is also possible to use zinc which has been treated to eliminate or reduce its ~Zn content, such as described in U.S. patent 4,756,874 (herein incorporated by reference). The zinc oxide may be added in any form which permit it to be dissolved in the reactor water, such as by way of a slurry, paste or preformed solution. A paste will typically have a concentration of zinc oxide of about 25% to about 95% by weight, whereas a slurry will have a zinc oxide content in the region of about 0.1% to 20% by weight. Examples of ways in which the zinc oxide is introduced are set forth in U.S. patent 4,756,874, referred to above.
An advantage associated with the method of the present invention is that it may be applied directly to existing boiling water reactor recirculation piping and other components without prior oxide film removal. It may also be applied to oxide-free metal components before their introduction into the reactor. The inventors have found that the properties of the oxide film are changed when subjected to the conditions of the present method.
At least part of the film is changed from a tightly adherent structure to a loosely adherent structure, with simultaneous release . of constituents. Thus, according to the invention, the application of the process not only inhibits further Co~° buildup but also effects a decontamination, including a decrease in Co6° levels.
E~,'.AMPLE
The following example illustrates the present invention.
Small stainless steel autoclaves were used to contain test specimens fvr the formation of the oxide films in high temperature water. The autoclaves used in these tests were previously employed for corrosion specimen testing under similar conditions without zinc present in the water. Under these conditions, after long exposure (many thousands o f hours) the inner surfaces had attained a heavy black oxide coating which was tightly adherent and could not be removed by w i p i n ~.
WO 01!27932 PCT/US99/23795 During a shut-down period for specimen removal, it was noted that the inner autoclave surfaces which had been treated according to the method of the present invention appeared lighter in color. Wiping of the surfaces resulted in removal of some of the dark outer surface oxide, leaving a dark bronze-colored oxide inner film. The autoclaves have been operated with high temperature water containing zinc for approximately 2,000 hours.
During the initial exposure, with the zinc containing water, a zinc depletion was also noted. The zinc concentration in the water l0 from the autoclaves was significantly lower than the inlet concentration, indicating absorption on the stainless steel surfaces.
Zinc can thus be incorporated into an oxide film even in the presence of an already existing oxide film. This results in release of material from the previously existing film and also gives rise to reduced Co~° buildup on the metal surfaces.
While the invention has been described in connection with what is presently considered to be the most practical and preferred embodiment, it is to be understood that the invention is not to be limited to the disclosed embodiment, but on the contrary, is intended to cover various modifications and equivalent arrangements included within the spirit and scope of the appended claims.
At least part of the film is changed from a tightly adherent structure to a loosely adherent structure, with simultaneous release . of constituents. Thus, according to the invention, the application of the process not only inhibits further Co~° buildup but also effects a decontamination, including a decrease in Co6° levels.
E~,'.AMPLE
The following example illustrates the present invention.
Small stainless steel autoclaves were used to contain test specimens fvr the formation of the oxide films in high temperature water. The autoclaves used in these tests were previously employed for corrosion specimen testing under similar conditions without zinc present in the water. Under these conditions, after long exposure (many thousands o f hours) the inner surfaces had attained a heavy black oxide coating which was tightly adherent and could not be removed by w i p i n ~.
WO 01!27932 PCT/US99/23795 During a shut-down period for specimen removal, it was noted that the inner autoclave surfaces which had been treated according to the method of the present invention appeared lighter in color. Wiping of the surfaces resulted in removal of some of the dark outer surface oxide, leaving a dark bronze-colored oxide inner film. The autoclaves have been operated with high temperature water containing zinc for approximately 2,000 hours.
During the initial exposure, with the zinc containing water, a zinc depletion was also noted. The zinc concentration in the water l0 from the autoclaves was significantly lower than the inlet concentration, indicating absorption on the stainless steel surfaces.
Zinc can thus be incorporated into an oxide film even in the presence of an already existing oxide film. This results in release of material from the previously existing film and also gives rise to reduced Co~° buildup on the metal surfaces.
While the invention has been described in connection with what is presently considered to be the most practical and preferred embodiment, it is to be understood that the invention is not to be limited to the disclosed embodiment, but on the contrary, is intended to cover various modifications and equivalent arrangements included within the spirit and scope of the appended claims.
Claims (14)
1. A method for effecting decontamination of metal components carrying an oxide layer in a nuclear powered water cooled reactor comprising introducing a low concentration of zinc ions into the water to cause loosening of the oxide layer from the metal surface.
2. A method according to claim 1, wherein said zinc ions are introduced in a concentration of at least 30 ppb.
3. A method according to claim 2, wherein said zinc ion concentration is 1-500 ppb.
4. A method according to claim 1, wherein said water is at a temperature of at least about 450°F.
5. A method according to claim 4, wherein said temperature is about 455 to 550°F.
6. A method according to claim 1, wherein said metal surface carrying said oxide layer is exposed to said zinc ions for at least 100 hours.
7. A method according to claim 6, wherein said exposure time is about 2000 hours.
8. A method according to claim 1, where the zinc ion is substantially devoid of 64Zn.
9. A method according to claim 1 wherein the zinc ion is added by dissolving zinc oxide in water.
10. A method according to claim 1 wherein the zinc ion is added as a water-based paste, a water-based slurry or a water-based solution.
11. A method of passivation of a metal surface comprising immersing the metal surface initially free of oxide surface layer in water at elevated temperature in the presence of zinc at a low concentration for a time of at least 100 hours.
12. A method according to claim 11, wherein said water is at a temperature of at least about 450°F.
13. A method according to claim 11, wherein said zinc is at a concentration of 1-300 ppb.
14. A method for effecting decontamination of metal components carrying an oxide layer comprising exposing the component to an aqueous solution of zinc ions to cause loosening of the oxide layer from the metal surface.
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| PCT/US1999/023795 WO2001027932A1 (en) | 1999-10-12 | 1999-10-12 | Method for nuclear power plant decontamination |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CA2352141A1 true CA2352141A1 (en) | 2001-04-19 |
Family
ID=22273799
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CA002352141A Abandoned CA2352141A1 (en) | 1999-10-12 | 1999-10-12 | Method for nuclear power plant decontamination |
Country Status (10)
| Country | Link |
|---|---|
| EP (1) | EP1138046A1 (en) |
| JP (1) | JP2003511709A (en) |
| KR (1) | KR20010108013A (en) |
| CN (1) | CN1330794A (en) |
| BG (1) | BG105544A (en) |
| CA (1) | CA2352141A1 (en) |
| CZ (1) | CZ20012065A3 (en) |
| HU (1) | HUP0201234A3 (en) |
| RO (1) | RO119217B1 (en) |
| WO (1) | WO2001027932A1 (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US11469006B2 (en) | 2016-08-04 | 2022-10-11 | Dominion Engineering, Inc. | Suppression of radionuclide deposition on nuclear power plant components |
Families Citing this family (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN101189374B (en) * | 2005-05-30 | 2010-09-29 | 贝卡尔特股份有限公司 | Method for manufacturing card clothing wire |
| KR101523763B1 (en) | 2013-06-19 | 2015-06-01 | 한국원자력연구원 | Oxidation decontamination reagent for removal of the dense radioactive oxide layer on the metal surface and oxidation decontamination method using the same |
| CN105716919A (en) * | 2016-02-22 | 2016-06-29 | 苏州热工研究院有限公司 | Preparation method of stainless steel performed oxide film sample with radionuclide |
| CN105931686A (en) * | 2016-04-22 | 2016-09-07 | 中国原子能科学研究院 | Pressurized water reactor primary circuit coolant zinc-adding device capable of automatically controlling zinc concentration |
Family Cites Families (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4756874A (en) * | 1986-12-22 | 1988-07-12 | General Electric Company | Minimization of radioactive material deposition in water-cooled nuclear reactors |
| US5108697A (en) * | 1990-10-19 | 1992-04-28 | Westinghouse Electric Corp. | Inhibiting stress corrosion cracking in the primary coolant circuit of a nuclear reactor |
| US5608766A (en) * | 1993-10-29 | 1997-03-04 | General Electric Company | Co-deposition of palladium during oxide film growth in high-temperature water to mitigate stress corrosion cracking |
| DE19739361C1 (en) * | 1997-09-09 | 1998-10-15 | Siemens Ag | Zinc introduction into nuclear reactor primary water system |
-
1999
- 1999-10-12 EP EP99974114A patent/EP1138046A1/en not_active Withdrawn
- 1999-10-12 CA CA002352141A patent/CA2352141A1/en not_active Abandoned
- 1999-10-12 CZ CZ20012065A patent/CZ20012065A3/en unknown
- 1999-10-12 KR KR1020017007255A patent/KR20010108013A/en not_active Application Discontinuation
- 1999-10-12 HU HU0201234A patent/HUP0201234A3/en unknown
- 1999-10-12 WO PCT/US1999/023795 patent/WO2001027932A1/en not_active Application Discontinuation
- 1999-10-12 JP JP2001530864A patent/JP2003511709A/en not_active Withdrawn
- 1999-10-12 CN CN99814301A patent/CN1330794A/en active Pending
- 1999-10-12 RO ROA200100653A patent/RO119217B1/en unknown
-
2001
- 2001-05-29 BG BG105544A patent/BG105544A/en unknown
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US11469006B2 (en) | 2016-08-04 | 2022-10-11 | Dominion Engineering, Inc. | Suppression of radionuclide deposition on nuclear power plant components |
Also Published As
| Publication number | Publication date |
|---|---|
| JP2003511709A (en) | 2003-03-25 |
| BG105544A (en) | 2001-12-29 |
| KR20010108013A (en) | 2001-12-07 |
| CN1330794A (en) | 2002-01-09 |
| EP1138046A1 (en) | 2001-10-04 |
| HUP0201234A2 (en) | 2002-08-28 |
| RO119217B1 (en) | 2004-05-28 |
| WO2001027932A1 (en) | 2001-04-19 |
| HUP0201234A3 (en) | 2004-06-28 |
| CZ20012065A3 (en) | 2001-11-14 |
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