JP2017067744A - Method for sealing cracks of reactor vessel and reactor containment vessel by using water vapor in air - Google Patents
Method for sealing cracks of reactor vessel and reactor containment vessel by using water vapor in air Download PDFInfo
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- JP2017067744A JP2017067744A JP2015205907A JP2015205907A JP2017067744A JP 2017067744 A JP2017067744 A JP 2017067744A JP 2015205907 A JP2015205907 A JP 2015205907A JP 2015205907 A JP2015205907 A JP 2015205907A JP 2017067744 A JP2017067744 A JP 2017067744A
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- air
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- containment vessel
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- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Chemical compound O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 title claims abstract description 25
- 238000007789 sealing Methods 0.000 title description 4
- 238000000034 method Methods 0.000 title description 3
- IJGRMHOSHXDMSA-UHFFFAOYSA-N Atomic nitrogen Chemical compound N#N IJGRMHOSHXDMSA-UHFFFAOYSA-N 0.000 claims abstract description 12
- 230000001629 suppression Effects 0.000 claims abstract description 12
- 239000007788 liquid Substances 0.000 claims abstract description 8
- 238000001816 cooling Methods 0.000 claims abstract description 6
- 229910052757 nitrogen Inorganic materials 0.000 claims abstract description 6
- CURLTUGMZLYLDI-UHFFFAOYSA-N Carbon dioxide Chemical compound O=C=O CURLTUGMZLYLDI-UHFFFAOYSA-N 0.000 claims abstract description 4
- 235000011089 carbon dioxide Nutrition 0.000 claims abstract description 4
- 239000013078 crystal Substances 0.000 claims description 4
- 238000010276 construction Methods 0.000 claims description 2
- 239000000446 fuel Substances 0.000 abstract description 6
- 239000002245 particle Substances 0.000 abstract description 3
- 239000000498 cooling water Substances 0.000 abstract description 2
- 238000004880 explosion Methods 0.000 abstract description 2
- 239000007789 gas Substances 0.000 abstract description 2
- 230000005855 radiation Effects 0.000 abstract description 2
- 239000007787 solid Substances 0.000 abstract description 2
- 238000003466 welding Methods 0.000 description 2
- 239000000356 contaminant Substances 0.000 description 1
- 238000011109 contamination Methods 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 239000003673 groundwater Substances 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
- 230000008439 repair process Effects 0.000 description 1
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- 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
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- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
Description
本発明は、事故で原子炉容器や格納容器に生じたキレツを封鎖する工法に関する。 The present invention relates to a method of sealing off cracks generated in a nuclear reactor vessel or containment vessel in an accident.
2011年3月11日東日本大震災により福島第一原発1号機から3号機まで炉心溶融した。
廃炉措置の第一段として格納容器及び原子炉容器を密封することが急務となっている。現在、抜本的な工法が見いだされていない。On March 11, 2011, the Fukushima Daiichi nuclear power plant from Unit 1 to
There is an urgent need to seal the containment vessel and reactor vessel as the first step in decommissioning measures. At present, no drastic construction method has been found.
従来から、格納容器のキレツは溶接で補修されており、現在、高放射線下の補修となる福島では人が作業せずに遠隔ロボットで溶接することが研究されている。
Conventionally, the cracks in the containment vessel have been repaired by welding. Currently, in Fukushima, where repairs are performed under high radiation, welding by a remote robot without human work is being studied.
損傷した原子炉容器及び格納容器を安全に安価に密閉する工法は見当たらない。 There is no method to safely and inexpensively seal damaged reactor vessels and containment vessels.
本発明は炉心溶融した原子炉容器,格納容器及び圧力抑制室に氷粒、液体窒素、ドライアイス、又は冷却空気などを循環または充填し、それらの容器と室を冷やした上で、それらの容器内または室内の空気を排気し、それに伴い空気に含まれる水蒸気が容器及び室の外側表面で冷やされ結露し、その結露水がキレツや隙間部を通じて内側に吸引されそのキレツや隙間部及びその付近でさらに冷やされ氷となりキレツや隙間部を塞ぎ、原子炉容器及び格納容器からの漏れを食い止める。 The present invention circulates or fills ice particles, liquid nitrogen, dry ice, cooling air, or the like in a reactor vessel, containment vessel, and pressure suppression chamber melted in the core, and cools the vessel and the chamber. The air in the room or room is exhausted, and the water vapor contained in the air is cooled and condensed on the outer surface of the container and the room, and the condensed water is sucked inward through the crevices and the gaps. It is further cooled to become ice and closes the cracks and gaps to prevent leakage from the reactor vessel and containment vessel.
事故時の爆発により格納容器は膨大な箇所においてキレツと隙間があると想定されそのすべての漏れを食い止める必要があること。 It is assumed that the containment vessel has gaps and gaps at enormous locations due to explosions at the time of the accident, and it is necessary to stop all leaks.
燃料デブリを冷やしている冷却水が放射化しキレツから建屋外の漏れ大量に地中に浸みこみ汚染が拡大していることに抜本的な対策が必要であること。 It is necessary to take drastic measures against the fact that the cooling water that cools fuel debris is activated and leaks from Kiretsu into the ground in large quantities and the pollution is spreading.
格納容器下部コンクリート内に周囲の地下水が侵入し放射能汚染が拡大していることに対し抜本的な対策が必要なこと。 It is necessary to take drastic measures against the surrounding groundwater invading into the concrete in the lower part of the PCV and increasing radioactive contamination.
燃料デブリを保管中であっても、回収作業中であっても燃料デブリから放出されている気体、液体、及び固体の放射能の流出を食い止め、環境中に放出しないこと。容器内が負圧管理され損傷しているキレツや隙間部を外から空気を流入させていても、内部の汚染物がキレツや隙間部から逆流し環境中に放出されることが多い。それに対する対策が急務である。 Regardless of whether fuel debris is being stored or being recovered, the release of gas, liquid, and solid radioactivity released from fuel debris must be prevented and not released into the environment. Even if the inside of the container is negative pressure controlled and air is introduced from the outside through damaged crevices and gaps, internal contaminants often flow backward from the crevices and gaps and are released into the environment. There is an urgent need for countermeasures.
原子炉容器、格納容器及び圧力抑制室内に氷粒、液体窒素、ドライアイス、又は冷却空気などを充填または循環させる。 Fill or circulate ice particles, liquid nitrogen, dry ice, or cooling air in the reactor vessel, containment vessel, and pressure suppression chamber.
原子炉容器、格納容器及び圧力抑制室から空気を排気する。 Air is exhausted from the reactor vessel, containment vessel, and pressure suppression chamber.
排気した空気はフィルターを通し放射能を除去し大気に放出する。 The exhausted air passes through a filter, removes radioactivity and releases it to the atmosphere.
排気した空気はフィルターを通し放射能を除去し大気に放出する。 The exhausted air passes through a filter, removes radioactivity and releases it to the atmosphere.
前項に誘発されて、原子炉容器、格納容器及び圧力抑制室の内側は負圧となりキレツや隙間から空気が外気から流入する。 Induced by the previous section, the inside of the reactor vessel, containment vessel, and pressure suppression chamber becomes negative pressure, and air flows from outside air through a crack or a gap.
容器及び室の外側の空気に含まれる水蒸気が容器及び室の外側表面で冷やされ結露し、その結露水がキレツや隙間部に吸引されさらに冷やされ氷となりキレツや隙間部を塞ぎ、その容器及び室を密閉させ、漏えいを安価に食い止め、漏えいがある限りこの現象は続き、場所を特定せずとも安定的に封鎖でき、たとえキレツや隙間がその後発生しても容器内を負圧にしている限り自動的に即座に修復される。 Water vapor contained in the air outside the container and the room is cooled and condensed on the outer surface of the container and the room, and the condensed water is sucked into the crevices and gaps and further cooled to form ice, closing the crevices and the gaps. The chamber is sealed, leaks are prevented at low cost, this phenomenon continues as long as there is a leak, and it can be stably sealed without specifying the location, and even if a crack or a gap occurs afterwards, the inside of the container is under negative pressure As soon as it is automatically repaired.
図1は原子炉容器1から落下した燃料デブリ4により損傷した原子炉容器1、格納容器2及び圧力抑制室3を密封するイメージ図である。原子炉容器1、格納容器2及び圧力抑制室3に冷却管6を通じて液体窒素5を充填または循環させる。排気した空気はフィルターを通し放射能を除去し大気に放出する。原子炉容器、格納容器及び圧力抑制室の内側は負圧となりキレツや隙間から空気が外気から流入する。
図2は 容器の外側表面で空気に含まれる水蒸気8がそれら容器及び室の外側表面で冷やされ結露し水9となり、その結露水がキレツ7を通じて容器内に吸引されそのキレツ7でさらに冷やされ氷10となりキレツ7を塞ぐ様子を示している。FIG. 1 is an image view of sealing a reactor vessel 1, a
FIG. 2 shows that
損傷した容器内の危険物を封じる必要がある事象に対して利用可能である。 It can be used for events that require the containment of dangerous goods in damaged containers.
1.原子炉容器
2.格納容器
3.圧力抑制室
4.燃料デブリ
5.液体窒素
6.冷却管
7.キレツ
8.水蒸気
9.水
10.氷1.
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JP2015205907A JP6655224B2 (en) | 2015-09-30 | 2015-09-30 | A method to seal off the cracks in the reactor vessel and containment vessel using water vapor in the air |
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JP2015205907A JP6655224B2 (en) | 2015-09-30 | 2015-09-30 | A method to seal off the cracks in the reactor vessel and containment vessel using water vapor in the air |
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JP2017067744A true JP2017067744A (en) | 2017-04-06 |
JP6655224B2 JP6655224B2 (en) | 2020-02-26 |
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Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN109344428A (en) * | 2018-08-23 | 2019-02-15 | 中电投电力工程有限公司 | A kind of advanced small-sized nuclear reactor power plant siting source term Model Calculating Method |
Citations (6)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPH06109885A (en) * | 1991-11-06 | 1994-04-22 | Commiss Energ Atom | Nuclear reactor having device for recovering reactor core after accidental melt-down of nuclear reactor |
JPH09209577A (en) * | 1996-02-01 | 1997-08-12 | Rinotetsuku:Kk | Repairing method for concrete crack and its device |
JP2002357000A (en) * | 2001-05-31 | 2002-12-13 | Taiyo Gijutsu Kaihatsu Kk | Method and tool for repairing concrete structure |
JP2013002869A (en) * | 2011-06-14 | 2013-01-07 | Yoshiaki Nagaura | Method and apparatus for repairing water leak damaged portion in reactor container of nuclear power plant |
US20130052367A1 (en) * | 2010-02-01 | 2013-02-28 | Pmd-Ateav Systems Sprl | Method and system for injecting liquid in a porous material |
JP2015141197A (en) * | 2014-01-30 | 2015-08-03 | 森重 晴雄 | Method for recovering molten fuel in nuclear reactor |
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- 2015-09-30 JP JP2015205907A patent/JP6655224B2/en not_active Expired - Fee Related
Patent Citations (6)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPH06109885A (en) * | 1991-11-06 | 1994-04-22 | Commiss Energ Atom | Nuclear reactor having device for recovering reactor core after accidental melt-down of nuclear reactor |
JPH09209577A (en) * | 1996-02-01 | 1997-08-12 | Rinotetsuku:Kk | Repairing method for concrete crack and its device |
JP2002357000A (en) * | 2001-05-31 | 2002-12-13 | Taiyo Gijutsu Kaihatsu Kk | Method and tool for repairing concrete structure |
US20130052367A1 (en) * | 2010-02-01 | 2013-02-28 | Pmd-Ateav Systems Sprl | Method and system for injecting liquid in a porous material |
JP2013002869A (en) * | 2011-06-14 | 2013-01-07 | Yoshiaki Nagaura | Method and apparatus for repairing water leak damaged portion in reactor container of nuclear power plant |
JP2015141197A (en) * | 2014-01-30 | 2015-08-03 | 森重 晴雄 | Method for recovering molten fuel in nuclear reactor |
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN109344428A (en) * | 2018-08-23 | 2019-02-15 | 中电投电力工程有限公司 | A kind of advanced small-sized nuclear reactor power plant siting source term Model Calculating Method |
CN109344428B (en) * | 2018-08-23 | 2023-08-15 | 上海能源科技发展有限公司 | Site selection source model calculation method for advanced small nuclear reactor power plant |
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