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 PDF

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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
reactor
vessel
containment vessel
gaps
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森重 晴雄
Haruo Morishige
晴雄 森重
晴貴 森重
Haruki Morishige
晴貴 森重
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    • YGENERAL 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
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    • Y02E30/30Nuclear fission reactors

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Abstract

PROBLEM TO BE SOLVED: To stop leaking from all of cracks that are presumed to be formed at a tremendous number of portions of a reactor containment vessel due to explosion in an accident, so as to stop leaking of a cooling water from a reactor vessel, to stop outflow of radioactivity in gas, liquid, and solid states which are emitted from fuel debris to prevent it from releasing into the atmosphere, and to secure safety of workers physically as well as with respect to radiation.SOLUTION: Ice particles, liquid nitrogen, dry ice, cooling air, or the like is put or circulated in a reactor vessel, a reactor containment vessel, and a pressure suppression chamber, and air is exhausted from the vessels and the chamber. The exhausted air is discharged in the atmosphere after passing a filter such that radioactivity is removed therefrom, which causes inside of the reactor containment vessel to be under negative pressure, thereby allowing air to flow into the reactor containment vessel through cracks 7 and gaps. Water vapor 8 contained in the air is cooled and dew-condensed on outer wall surfaces of the vessels and the chamber, and dew-condensed water 9 of the water vapor 8 is vacuumed through the cracks 7 and gaps and further cooled to freeze such that the cracks, the gaps, and portions therearound are blocked with ice 10 to seal the vessels and the chamber and stop leakage.SELECTED DRAWING: Figure 2

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 Unit 3 melted due to the Great East Japan Earthquake.
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は損傷した原子炉容器、格納容器及び圧力抑制室を密封するイメージ図である。  FIG. 1 is an image of sealing a damaged reactor vessel, containment vessel, and pressure suppression chamber.

図2はキレツや隙間内を通過する空気内の水蒸気が氷結するイメージ図である。  FIG. 2 is an image diagram in which water vapor in the air passing through the cracks and gaps freezes.

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 containment vessel 2, and a pressure suppression chamber 3 damaged by fuel debris 4 dropped from the reactor vessel 1. The reactor vessel 1, the containment vessel 2, and the pressure suppression chamber 3 are filled or circulated with liquid nitrogen 5 through the cooling pipe 6. The exhausted air passes through a filter, removes radioactivity and releases it to the atmosphere. The inside of the reactor vessel, the containment vessel, and the pressure suppression chamber has a negative pressure, and air flows from outside air through a crack or a gap.
FIG. 2 shows that water vapor 8 contained in the air is cooled on the outer surface of the container and on the outer surface of the container and the chamber to form condensed water 9, and the condensed water is sucked into the container through the crystal 7 and further cooled by the crystal 7. It shows a state where the ice 10 is formed and the crack 7 is blocked.

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. Reactor vessel 2. 2. containment vessel 3. Pressure suppression chamber 4. Fuel debris Liquid nitrogen 6. Cooling pipe Kiretsu 8 Water vapor 9. Water 10 ice

Claims (1)

事故で損傷しキレツや隙間が発生した原子炉容器、格納容器及び圧力抑制室に液体窒素、ドライアイス、又は冷却空気などを充填または循環させ、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及びその付近を塞ぎ、原子炉容器、格納容器及び圧力抑制室からの漏れを食い止めることを特徴とする工法。    Fill or circulate liquid nitrogen, dry ice, or cooling air in reactor vessels, containment vessels, and pressure suppression chambers that have been damaged due to accidents and have gaps or gaps, and cool those containers and chambers. The air in the container or the 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 crystal and the gap, and the crystal and the gap and the A construction method characterized in that it is further cooled in the vicinity to become ice and closes the cracks and gaps and the vicinity thereof to prevent leakage from the reactor vessel, containment vessel, and pressure suppression chamber.
JP2015205907A 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 Expired - Fee Related JP6655224B2 (en)

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Cited By (1)

* Cited by examiner, † Cited by third party
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)

* Cited by examiner, † Cited by third party
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

Patent Citations (6)

* Cited by examiner, † Cited by third party
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)

* Cited by examiner, † Cited by third party
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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