EP4465308A1 - Systemic decontamination method of heavy water reactor - Google Patents

Systemic decontamination method of heavy water reactor Download PDF

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Publication number
EP4465308A1
EP4465308A1 EP23740388.6A EP23740388A EP4465308A1 EP 4465308 A1 EP4465308 A1 EP 4465308A1 EP 23740388 A EP23740388 A EP 23740388A EP 4465308 A1 EP4465308 A1 EP 4465308A1
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EP
European Patent Office
Prior art keywords
decontamination
moderator
coolant
coolant system
reduction process
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.)
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Application number
EP23740388.6A
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German (de)
French (fr)
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EP4465308A4 (en
Inventor
Cho Rong Kim
Hak Soo Kim
Jeong Ju Kim
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Korea Hydro and Nuclear Power Co Ltd
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Korea Hydro and Nuclear Power Co Ltd
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Application filed by Korea Hydro and Nuclear Power Co Ltd filed Critical Korea Hydro and Nuclear Power Co Ltd
Publication of EP4465308A1 publication Critical patent/EP4465308A1/en
Publication of EP4465308A4 publication Critical patent/EP4465308A4/en
Pending legal-status Critical Current

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    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21FPROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/001Decontamination of contaminated objects, apparatus, clothes, food; Preventing contamination thereof
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C17/00Monitoring; Testing ; Maintaining
    • G21C17/02Devices or arrangements for monitoring coolant or moderator
    • G21C17/022Devices or arrangements for monitoring coolant or moderator for monitoring liquid coolants or moderators
    • G21C17/0225Chemical surface treatment, e.g. corrosion
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C19/00Arrangements 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
    • G21C19/28Arrangements for introducing fluent material into the reactor core; Arrangements for removing fluent material from the reactor core
    • G21C19/30Arrangements 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
    • G21C19/307Arrangements 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
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21FPROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/001Decontamination of contaminated objects, apparatus, clothes, food; Preventing contamination thereof
    • G21F9/002Decontamination of the surface of objects with chemical or electrochemical processes
    • G21F9/004Decontamination of the surface of objects with chemical or electrochemical processes of metallic surfaces
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21FPROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/04Treating liquids
    • G21F9/06Processing

Definitions

  • the present disclosure relates to a systematic decontamination method for a heavy water nuclear reactor.
  • heavy water is used as a moderator for slowing down neutrons and a coolant for absorbing heat energy.
  • an object of the present disclosure is to provide a systematic decontamination method for a heavy water nuclear reactor.
  • a system decontamination method for a heavy water nuclear reactor including: performing decontamination of a moderator system; and performing decontamination of a coolant system after the decontamination of the moderator system, wherein the decontamination of the moderator system is performed by adjusting a temperature of first system water of the moderator system to a first system water process temperature and sequentially performing a moderator system oxidation process and a moderator system reduction process.
  • the first system water process temperature may be 65°C to 95°C, and the adjustment of the first system water process temperature may be performed through at least one of a) heating of the first system water using an ultraviolet lamp, and b) use of a heat source of the coolant system.
  • the heat source of the coolant system may be provided by using a coolant pump and a heat exchanger of the coolant system.
  • a moderator system waste liquid treatment process may be performed after the moderator system reduction process, and an ultraviolet lamp may be used in the moderator system waste liquid treatment process.
  • the decontamination of the coolant system may be performed by adjusting a temperature of second system water of the coolant system to a second system water process temperature and then performing a coolant system reduction process.
  • At least one of permanganic acid and potassium permanganate may be used in the moderator system oxidation process
  • at least one of oxalic acid and citric acid may be used in the moderator system reduction process
  • a decontamination target in the moderator system oxidation process may include chromium oxide
  • a decontamination target in the moderator system reduction process may include at least one of iron oxide and nickel oxide.
  • the second system water process temperature may be 90°C to 100°C.
  • a coolant system oxidation process In the decontamination of the coolant system, a coolant system oxidation process, a coolant system additional reduction process, and a coolant system waste liquid treatment process may be sequentially performed after the coolant system reduction process.
  • the system decontamination method may include: measuring a surface dose rate of the coolant system to derive a decontamination factor value, after the coolant system reduction process, and the coolant system oxidation process and the coolant system additional reduction process may be performed when the derived decontamination factor value does not satisfy a target value.
  • At least one of citric acid and oxalic acid may be used in the coolant system reduction process, at least one of permanganic acid and potassium permanganate may be used in the coolant system oxidation process, at least one of citric acid and oxalic acid may be used in the coolant system additional reduction process, a decontamination target in the coolant system reduction process may include iron oxide, and a decontamination target in the coolant system oxidation process may include chromium oxide.
  • a moderator system and a coolant system are separated, unlike a light water nuclear reactor.
  • the present disclosure provides a decontamination method for each of the moderator system and the coolant system.
  • the present disclosure proposes a decontamination order and a system-specific decontamination method in which the moderator system is decontaminated first and the coolant system is decontaminated later.
  • FIG. 1 is a configuration diagram illustrating a configuration of a moderator decontamination facility that performs the decontamination method of the present disclosure
  • FIG. 2 is a configuration diagram illustrating a configuration of a coolant decontamination facility that performs the decontamination method of the present disclosure.
  • the moderator decontamination facility is connected to the moderator system, and first system water is circulated therein.
  • the moderator decontamination facility includes, for example, a filter, a demineralizer, a UV reaction tank, an oxidizing agent manufacturing device, and a chemical injection pump. Although not shown, the moderator decontamination facility may further include a configuration for supplying a reducing agent. Further, in the moderator system, chemicals can be supplied through a calandria.
  • an ultraviolet lamp particularly, a UVB lamp may be used.
  • the coolant decontamination facility is connected to the coolant system, and second system water is circulated therein.
  • the coolant decontamination facility includes, for example, a pressure reducing device, a filter, a demineralizer, a UV reaction tank, and an injection pump. Although not shown, the coolant decontamination facility may further include a configuration for supplying a reducing agent and an oxidizing agent.
  • an ultraviolet lamp particularly, a UVC lamp may be used.
  • a decontamination method according to an embodiment of the present disclosure will be described with reference to FIGS. 3 and 4 .
  • FIG. 3 is a flowchart of a decontamination method for a moderator system according to an embodiment of the present disclosure
  • FIG. 4 is a flowchart of a decontamination method for a coolant system according to an embodiment of the present disclosure.
  • a temperature of the first system water is first adjusted (S110).
  • a temperature of the first system water is increased and adjusted to a first system water process temperature.
  • the first system water process temperature may be 65°C to 95°C or 85°C to 95°C.
  • the moderator system operates at room temperature at the time of a normal operation.
  • the increase in the temperature of the first system water may be performed using the UV reaction tank or a heat source of the coolant system.
  • the ultraviolet lamp may include a UVB lamp.
  • a temperature of the second system water is increased to 100°C or higher in the coolant system using a coolant pump so that a heat source is generated, and then the generated heat source is transferred to the first system water.
  • the heat source of the coolant system is transferred to the inside of the calandria, and the temperature of the moderator system can be increased through the heat transfer.
  • the moderator system In the moderator system oxidation process, at least one of permanganic acid, permanganic acid + nitric acid, and potassium permanganate + pH adjuster (the pH adjuster is nitric acid or sodium hydroxide) is used.
  • the moderator system is usually made of stainless steel, and a decontamination target includes chromium oxide or a chromium oxide film.
  • organic acid is used, and the organic acid may include at least one of citric acid and oxalic acid.
  • the decontamination target is iron oxide and/or nickel oxide.
  • a moderator system waste liquid treatment process (S140) is performed, and waste liquid treatment may be performed using the UV reaction tank.
  • waste liquid treatment may be performed using the UV reaction tank.
  • the organic acid is removed by using the UV reaction tank, the remaining organic acid may be removed by using an ion exchange resin or an oxidizing agent.
  • a UV lamp of the UV reaction tank used at this time a UVC or UVB lamp may be used.
  • a surface dose rate of the moderator system is measured for derivation of a decontamination factor (DF), and when the derived DF value does not satisfy a target value, the moderator system oxidation process (S120), the moderator system reduction process (S130), and the moderator system waste liquid treatment process (S140) are repeatedly performed.
  • the decontamination factor is a value derived by using a surface dose rate measurement value of a pipe or the like, and a reference value of the decontamination factor is a specific value in a range of 20 to 40 and may be determined depending on an on-site situation.
  • the surface dose rate the surface dose rate of the pipe or the like within the system may be measured using a mobile or fixed radiation meter.
  • the decontamination of the coolant system is performed.
  • the temperature of the second system water is first adjusted (S210).
  • the temperature of the second system water is adjusted to a second system water process temperature.
  • the temperature adjustment is performed using a coolant pump and a shutdown cooling heat exchanger, and the second system water process temperature may be 90°C to 100°C.
  • the temperature of the second system water only needs to be slightly decreased after the use as the heat source, making the process simpler and efficient treatment possible.
  • the decontamination of the coolant system can be performed immediately by slightly reducing the temperature of the second system water to 95°C.
  • a coolant system reduction process (S220) is performed.
  • organic acid is supplied, and the organic acid includes at least one of citric acid and oxalic acid.
  • the coolant system is mainly made of carbon steel, and the decontamination target includes iron oxide or an iron oxide film.
  • a concentration of the organic acid may be 500 to 1,000 ppm or 500 to 2,000 ppm.
  • a surface dose rate of the coolant system is measured for derivation of a decontamination factor (DF), and when the derived DF value does not satisfy a target value, a coolant system oxidation process (S230) and a coolant system additional reduction process (S240) are performed.
  • the decontamination factor is a value derived by using a surface dose rate measurement value of a pipe or the like, and a target reference value of the decontamination factor may be determined as a specific value in a range of 20 to 40.
  • the surface dose rate the surface dose rate of the pipe or the like within the system may be measured using a mobile or fixed radiation meter.
  • the surface dose rate of the coolant system is measured, and when the decontamination factor satisfies the target reference value, the coolant system oxidation process (S230) and the coolant system additional reduction process (S240) are omitted, and a coolant system waste liquid treatment process (S250) is performed.
  • the coolant system oxidation process (S230) and the coolant system additional reduction process (S240) that are selectively performed may be performed when chromium oxide is generated due to a steam generator pipe made of Alloy 800 and it is difficult to remove all of the oxide film through the reduction process.
  • At least one of permanganic acid, permanganic acid + nitric acid, and potassium permanganate + pH adjuster (the pH adjuster is nitric acid or sodium hydroxide) is used.
  • a target of the decontamination is the chromium oxide (chromium oxide film).
  • a large amount of oxidizing agent may be used so that the decomposition of the organic acid remaining in the reduction process, and the oxidation process are simultaneously performed. This oxidation process is performed after the reduction process in consideration of a problem that the permanganic acid is self-decomposed by carbon steel and deposits are formed.
  • the permanganic acid remaining after the oxidation process is decomposed into organic acid. Further, in the present process, the iron oxide (iron oxide film) and/or nickel oxide (nickel oxide film) present under the chromium oxide film can be removed. A large amount of oxidizing agent may be used so that the decomposition of the remaining permanganic acid and the reduction process can be simultaneously performed.
  • the organic acid oxalic acid or citric acid may be used.
  • the coolant system waste liquid treatment process may be performed using the UV reaction tank.
  • the organic acid is removed by using the UV reaction tank, the remaining organic acid may be removed by using an ion exchange resin or an oxidizing agent.
  • a UVB lamp or a UVC lamp may be used for the ultraviolet lamp of the UV reaction tank used at this time.
  • FIG. 5 shows results of an experiment in which an oxide film removal rate of a coolant system depending on a temperature is simulated
  • FIG. 6 shows results of an experiment in which an oxide film removal rate of a moderator system depending on a temperature is simulated.
  • a simulated specimen was immersed in citric acid (1L) of 0.1% for 8 hours and then the experiment was performed at a temperature of 60 to 95°C. After the experiment was performed, weights of the simulated specimen before and after the decontamination were measured for derivation of the oxide film removal rate.
  • the oxidation process and the reduction process were performed for a total of eight hours, each four hours.
  • permanganic acid + nitric acid was used for the experiment
  • oxalic acid was used. After the experiment was performed, weights of the simulated specimen before and after the decontamination were measured for derivation of the oxide film removal rate.

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  • High Energy & Nuclear Physics (AREA)
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Abstract

The present invention relates to a systemic decontamination method of a heavy water reactor, the method comprising the steps of: performing decontamination of a moderator system; and performing decontamination of a coolant system after the decontamination of the moderator system, wherein the decontamination of the moderator system is performed by adjusting the temperature of a first system water of the moderator system to a first system water process temperature and sequentially conducting a moderator system oxidation process and a moderator system reduction process.

Description

    Technical Field
  • The present disclosure relates to a systematic decontamination method for a heavy water nuclear reactor.
  • Background Art
  • In a heavy water nuclear reactor, heavy water is used as a moderator for slowing down neutrons and a coolant for absorbing heat energy.
  • The development of decommissioning technology and decontamination technology for a heavy water nuclear reactor is required, as in a light water nuclear reactor.
  • However, there is no development of technology for systematic decontamination for a heavy water nuclear reactor.
  • Disclosure Technical Problem
  • Therefore, an object of the present disclosure is to provide a systematic decontamination method for a heavy water nuclear reactor.
  • Technical Solution
  • The object of the present disclosure is achieved by a system decontamination method for a heavy water nuclear reactor, the system decontamination method including: performing decontamination of a moderator system; and performing decontamination of a coolant system after the decontamination of the moderator system, wherein the decontamination of the moderator system is performed by adjusting a temperature of first system water of the moderator system to a first system water process temperature and sequentially performing a moderator system oxidation process and a moderator system reduction process.
  • The first system water process temperature may be 65°C to 95°C, and the adjustment of the first system water process temperature may be performed through at least one of a) heating of the first system water using an ultraviolet lamp, and b) use of a heat source of the coolant system.
  • The heat source of the coolant system may be provided by using a coolant pump and a heat exchanger of the coolant system.
  • In the decontamination of the moderator system, a moderator system waste liquid treatment process may be performed after the moderator system reduction process, and an ultraviolet lamp may be used in the moderator system waste liquid treatment process.
  • The decontamination of the coolant system may be performed by adjusting a temperature of second system water of the coolant system to a second system water process temperature and then performing a coolant system reduction process.
  • At least one of permanganic acid and potassium permanganate may be used in the moderator system oxidation process, at least one of oxalic acid and citric acid may be used in the moderator system reduction process, a decontamination target in the moderator system oxidation process may include chromium oxide, and a decontamination target in the moderator system reduction process may include at least one of iron oxide and nickel oxide.
  • The second system water process temperature may be 90°C to 100°C.
  • In the decontamination of the coolant system, a coolant system oxidation process, a coolant system additional reduction process, and a coolant system waste liquid treatment process may be sequentially performed after the coolant system reduction process.
  • The system decontamination method may include: measuring a surface dose rate of the coolant system to derive a decontamination factor value, after the coolant system reduction process, and the coolant system oxidation process and the coolant system additional reduction process may be performed when the derived decontamination factor value does not satisfy a target value.
  • At least one of citric acid and oxalic acid may be used in the coolant system reduction process, at least one of permanganic acid and potassium permanganate may be used in the coolant system oxidation process, at least one of citric acid and oxalic acid may be used in the coolant system additional reduction process, a decontamination target in the coolant system reduction process may include iron oxide, and a decontamination target in the coolant system oxidation process may include chromium oxide.
  • Advantageous Effects
  • According to the present disclosure, a systematic decontamination method for a heavy water nuclear reactor is provided.
  • Description of Drawings
    • FIG. 1 is a diagram illustrating a configuration of a moderator decontamination facility that performs a decontamination method of the present disclosure.
    • FIG. 2 is a diagram illustrating a configuration of a coolant decontamination facility that performs the decontamination method of the present disclosure.
    • FIG. 3 is a flowchart of a decontamination method for a moderator system according to an embodiment of the present disclosure.
    • FIG. 4 is a flowchart of a decontamination method for a coolant system according to an embodiment of the present disclosure.
    • FIG. 5 shows results of an experiment in which an oxide film removal rate of the coolant system depending on a temperature is simulated.
    • FIG. 6 shows results of an experiment in which an oxide film removal rate of the moderator system depending on a temperature is simulated.
    Mode for Disclosure
  • In a heavy water nuclear reactor, a moderator system and a coolant system are separated, unlike a light water nuclear reactor.
  • The present disclosure provides a decontamination method for each of the moderator system and the coolant system. In particular, the present disclosure proposes a decontamination order and a system-specific decontamination method in which the moderator system is decontaminated first and the coolant system is decontaminated later.
  • A decontamination process of the coolant system and the moderator system according to the present disclosure will be described with reference to FIGS. 1 and 2.
  • FIG. 1 is a configuration diagram illustrating a configuration of a moderator decontamination facility that performs the decontamination method of the present disclosure, and FIG. 2 is a configuration diagram illustrating a configuration of a coolant decontamination facility that performs the decontamination method of the present disclosure.
  • The moderator decontamination facility is connected to the moderator system, and first system water is circulated therein.
  • The moderator decontamination facility includes, for example, a filter, a demineralizer, a UV reaction tank, an oxidizing agent manufacturing device, and a chemical injection pump. Although not shown, the moderator decontamination facility may further include a configuration for supplying a reducing agent. Further, in the moderator system, chemicals can be supplied through a calandria.
  • For the UV reaction tank, an ultraviolet lamp, particularly, a UVB lamp may be used.
  • The coolant decontamination facility is connected to the coolant system, and second system water is circulated therein.
  • The coolant decontamination facility includes, for example, a pressure reducing device, a filter, a demineralizer, a UV reaction tank, and an injection pump. Although not shown, the coolant decontamination facility may further include a configuration for supplying a reducing agent and an oxidizing agent.
  • For the UV reaction tank, an ultraviolet lamp, particularly, a UVC lamp may be used.
  • A decontamination method according to an embodiment of the present disclosure will be described with reference to FIGS. 3 and 4.
  • FIG. 3 is a flowchart of a decontamination method for a moderator system according to an embodiment of the present disclosure, and FIG. 4 is a flowchart of a decontamination method for a coolant system according to an embodiment of the present disclosure.
  • In the moderator decontamination method, a temperature of the first system water is first adjusted (S110).
  • A temperature of the first system water is increased and adjusted to a first system water process temperature. The first system water process temperature may be 65°C to 95°C or 85°C to 95°C.
  • The moderator system operates at room temperature at the time of a normal operation. The increase in the temperature of the first system water may be performed using the UV reaction tank or a heat source of the coolant system.
  • When the UV reaction tank is used, the ultraviolet lamp may include a UVB lamp.
  • When the heat source of the coolant system is used, a temperature of the second system water is increased to 100°C or higher in the coolant system using a coolant pump so that a heat source is generated, and then the generated heat source is transferred to the first system water. Specifically, the heat source of the coolant system is transferred to the inside of the calandria, and the temperature of the moderator system can be increased through the heat transfer.
  • Next, a moderator system oxidation process (S120) is performed.
  • In the moderator system oxidation process, at least one of permanganic acid, permanganic acid + nitric acid, and potassium permanganate + pH adjuster (the pH adjuster is nitric acid or sodium hydroxide) is used. The moderator system is usually made of stainless steel, and a decontamination target includes chromium oxide or a chromium oxide film.
  • Thereafter, a moderator system reduction process (S130) is performed.
  • In the moderator system reduction process, organic acid is used, and the organic acid may include at least one of citric acid and oxalic acid. The decontamination target is iron oxide and/or nickel oxide.
  • After the decontamination is completed, a moderator system waste liquid treatment process (S140) is performed, and waste liquid treatment may be performed using the UV reaction tank. After the organic acid is removed by using the UV reaction tank, the remaining organic acid may be removed by using an ion exchange resin or an oxidizing agent. For a UV lamp of the UV reaction tank used at this time, a UVC or UVB lamp may be used.
  • Thereafter, a surface dose rate of the moderator system is measured for derivation of a decontamination factor (DF), and when the derived DF value does not satisfy a target value, the moderator system oxidation process (S120), the moderator system reduction process (S130), and the moderator system waste liquid treatment process (S140) are repeatedly performed. The decontamination factor is a value derived by using a surface dose rate measurement value of a pipe or the like, and a reference value of the decontamination factor is a specific value in a range of 20 to 40 and may be determined depending on an on-site situation. For the surface dose rate, the surface dose rate of the pipe or the like within the system may be measured using a mobile or fixed radiation meter.
  • After the decontamination of the moderator system is completed, the decontamination of the coolant system is performed.
  • In the coolant system decontamination, the temperature of the second system water is first adjusted (S210).
  • The temperature of the second system water is adjusted to a second system water process temperature. The temperature adjustment is performed using a coolant pump and a shutdown cooling heat exchanger, and the second system water process temperature may be 90°C to 100°C.
  • When the temperature of the first system water is adjusted by the heat source of the coolant system, the temperature of the second system water only needs to be slightly decreased after the use as the heat source, making the process simpler and efficient treatment possible. For example, when the temperature of the second system water is increased to 100°C for generation of a heat source for the adjustment of the temperature of the first system water, the decontamination of the coolant system can be performed immediately by slightly reducing the temperature of the second system water to 95°C.
  • Thereafter, a coolant system reduction process (S220) is performed. In the coolant system reduction process, organic acid is supplied, and the organic acid includes at least one of citric acid and oxalic acid. The coolant system is mainly made of carbon steel, and the decontamination target includes iron oxide or an iron oxide film. A concentration of the organic acid may be 500 to 1,000 ppm or 500 to 2,000 ppm.
  • Thereafter, a surface dose rate of the coolant system is measured for derivation of a decontamination factor (DF), and when the derived DF value does not satisfy a target value, a coolant system oxidation process (S230) and a coolant system additional reduction process (S240) are performed. The decontamination factor is a value derived by using a surface dose rate measurement value of a pipe or the like, and a target reference value of the decontamination factor may be determined as a specific value in a range of 20 to 40. For the surface dose rate, the surface dose rate of the pipe or the like within the system may be measured using a mobile or fixed radiation meter.
  • The surface dose rate of the coolant system is measured, and when the decontamination factor satisfies the target reference value, the coolant system oxidation process (S230) and the coolant system additional reduction process (S240) are omitted, and a coolant system waste liquid treatment process (S250) is performed.
  • The coolant system oxidation process (S230) and the coolant system additional reduction process (S240) that are selectively performed may be performed when chromium oxide is generated due to a steam generator pipe made of Alloy 800 and it is difficult to remove all of the oxide film through the reduction process.
  • In the coolant system oxidation process (S230), at least one of permanganic acid, permanganic acid + nitric acid, and potassium permanganate + pH adjuster (the pH adjuster is nitric acid or sodium hydroxide) is used. A target of the decontamination is the chromium oxide (chromium oxide film). A large amount of oxidizing agent may be used so that the decomposition of the organic acid remaining in the reduction process, and the oxidation process are simultaneously performed. This oxidation process is performed after the reduction process in consideration of a problem that the permanganic acid is self-decomposed by carbon steel and deposits are formed.
  • In the coolant system additional reduction process (S240), the permanganic acid remaining after the oxidation process is decomposed into organic acid. Further, in the present process, the iron oxide (iron oxide film) and/or nickel oxide (nickel oxide film) present under the chromium oxide film can be removed. A large amount of oxidizing agent may be used so that the decomposition of the remaining permanganic acid and the reduction process can be simultaneously performed. For the organic acid, oxalic acid or citric acid may be used.
  • Thereafter, the coolant system waste liquid treatment process (S250) is performed. The coolant system waste liquid treatment process may be performed using the UV reaction tank. After the organic acid is removed by using the UV reaction tank, the remaining organic acid may be removed by using an ion exchange resin or an oxidizing agent. For the ultraviolet lamp of the UV reaction tank used at this time, a UVB lamp or a UVC lamp may be used.
  • FIG. 5 shows results of an experiment in which an oxide film removal rate of a coolant system depending on a temperature is simulated, and FIG. 6 shows results of an experiment in which an oxide film removal rate of a moderator system depending on a temperature is simulated.
  • Experimental conditions and experiment method of the coolant system are as follows.
  • Using carbon steel, a simulated specimen was immersed in citric acid (1L) of 0.1% for 8 hours and then the experiment was performed at a temperature of 60 to 95°C. After the experiment was performed, weights of the simulated specimen before and after the decontamination were measured for derivation of the oxide film removal rate.
  • Experimental conditions and experiment method of the moderator system are as follows.
  • Using stainless steel, the oxidation process and the reduction process were performed for a total of eight hours, each four hours. In this case, in the oxidation process, permanganic acid + nitric acid was used for the experiment, and in the reduction process, oxalic acid was used. After the experiment was performed, weights of the simulated specimen before and after the decontamination were measured for derivation of the oxide film removal rate.
  • Experimental results showed that the oxide film removal rate of 100% or more was shown at 70°C or more in the case of the carbon steel as shown in FIG. 5, and the oxide film removal rate of 70% or more was shown at 80°C or more in one cycle, but the highest removal rate was shown at 95°C after two cycles in the case of stainless steel, as shown in FIG. 6. Therefore, it is necessary to perform systematic decontamination between 70°C and 95°C in the coolant system, and it is necessary to perform systematic decontamination at 80°C or more in the moderator system.
  • The above-described embodiments are examples for describing the present disclosure, and the present disclosure is not limited thereto. Since those skilled in the art to which the present disclosure pertains will be able to implement the present disclosure through various modifications of the embodiments, the technical protection scope of the present disclosure should be determined by the appended claims.

Claims (10)

  1. A system decontamination method for a heavy water nuclear reactor, the system decontamination method comprising:
    performing decontamination of a moderator system; and
    performing decontamination of a coolant system after the decontamination of the moderator system, wherein
    the decontamination of the moderator system is performed by adjusting a temperature of first system water of the moderator system to a first system water process temperature and sequentially performing a moderator system oxidation process and a moderator system reduction process.
  2. The system decontamination method of claim 1, wherein
    the first system water process temperature is 65°C to 95°C, and
    the adjustment of the first system water process temperature is performed through at least one of
    a) heating of the first system water using an ultraviolet lamp, and
    b) use of a heat source of the coolant system.
  3. The system decontamination method of claim 2, wherein the heat source of the coolant system is provided by using a coolant pump and a heat exchanger of the coolant system.
  4. The system decontamination method of claim 1, wherein
    in the decontamination of the moderator system,
    a moderator system waste liquid treatment process is performed after the moderator system reduction process, and
    an ultraviolet lamp is used in the moderator system waste liquid treatment process.
  5. The system decontamination method of claim 1, wherein the decontamination of the coolant system is performed by adjusting a temperature of second system water of the coolant system to a second system water process temperature and then performing a coolant system reduction process.
  6. The system decontamination method of claim 1, wherein
    at least one of permanganic acid and potassium permanganate is used in the moderator system oxidation process,
    at least one of oxalic acid and citric acid is used in the moderator system reduction process,
    a decontamination target in the moderator system oxidation process includes chromium oxide, and
    a decontamination target in the moderator system reduction process includes at least one of iron oxide and nickel oxide.
  7. The system decontamination method of claim 6, wherein the second system water process temperature is 90°C to 100°C.
  8. The system decontamination method of claim 1, wherein
    in decontamination of the coolant system, a coolant system oxidation process, a coolant system additional reduction process, and a coolant system waste liquid treatment process are sequentially performed after the coolant system reduction process.
  9. The system decontamination method of claim 8, comprising:
    measuring a surface dose rate of the coolant system to derive a decontamination factor value, after the coolant system reduction process, and
    the coolant system oxidation process and the coolant system additional reduction process are performed when the derived decontamination factor value does not satisfy a target value.
  10. The system decontamination method of claim 8, wherein
    at least one of citric acid and oxalic acid is used in the coolant system reduction process, at least one of permanganic acid and potassium permanganate is used in the coolant system oxidation process,
    at least one of citric acid and oxalic acid is used in the coolant system additional reduction process,
    a decontamination target in the coolant system reduction process includes iron oxide, and
    a decontamination target in the coolant system oxidation process includes chromium oxide.
EP23740388.6A 2022-01-14 2023-01-05 SYSTEMIC DECONTAMINATION PROCESS FOR A HEAVY WATER REACTOR Pending EP4465308A4 (en)

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PCT/KR2023/000203 WO2023136544A1 (en) 2022-01-14 2023-01-05 Systemic decontamination method of heavy water reactor

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WO2017076431A1 (en) * 2015-11-03 2017-05-11 Areva Gmbh Method of decontaminating metal surfaces in a heavy water cooled and moderated nuclear reactor
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KR102667516B1 (en) 2024-05-20

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