JPH07209478A - Reactor internal equipment temporary setting pool - Google Patents

Reactor internal equipment temporary setting pool

Info

Publication number
JPH07209478A
JPH07209478A JP6005306A JP530694A JPH07209478A JP H07209478 A JPH07209478 A JP H07209478A JP 6005306 A JP6005306 A JP 6005306A JP 530694 A JP530694 A JP 530694A JP H07209478 A JPH07209478 A JP H07209478A
Authority
JP
Japan
Prior art keywords
reactor
pool
steam
equipment
well
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Pending
Application number
JP6005306A
Other languages
Japanese (ja)
Inventor
Tsuneo Kuroda
恒雄 黒田
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Toshiba Corp
Original Assignee
Toshiba Corp
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by Toshiba Corp filed Critical Toshiba Corp
Priority to JP6005306A priority Critical patent/JPH07209478A/en
Publication of JPH07209478A publication Critical patent/JPH07209478A/en
Pending legal-status Critical Current

Links

Classifications

    • 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

PURPOSE:To provide a reactor internal equipment temporary setting pool in which exposure to worker can be reduced, and working efficiency can be improved by arranging an equipment temporary setting pool in T-shape to a reactor well, and also providing a shielding door in the equipment temporary setting pool. CONSTITUTION:In a reactor internal equipment temporary setting pool 7 for temporarily setting reactor internal equipments such as a steam dryer 4 and steam separator 5 provided to communicate with a reactor well 3 in a boiling water type nuclear power plant, the steam dryer 4 and steam separator 5 temporarily set in T-shape through the passage with the reactor well 3 are never linearly arranged with the reactor well 3. The inner part of the reactor internal equipment temporary setting pool 7 is partitioned by a watertight shielding door 8, so that each of the steam dryer 4 and steam separator 5 can be temporarily arranged in water independently.

Description

【発明の詳細な説明】Detailed Description of the Invention

【0001】[0001]

【産業上の利用分野】本発明は、沸騰水型原子力プラン
トにおける定期検査工事等に際して蒸気乾燥器等の炉内
機器を一時収容する炉内機器仮置プールに関する。
BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a temporary equipment pool for temporarily storing in-reactor equipment such as a steam dryer at the time of periodic inspection work in a boiling water nuclear power plant.

【0002】[0002]

【従来の技術】沸騰水型原子力プラントで原子炉の開放
とその復旧作業は、定期点検工事におけるクリティカル
パスと呼ばれる主要作業の一つであり、この作業のため
に従来の原子炉建屋には図3の平面図に示すように、一
方に炉内機器仮置プール1と他方に燃料プール2を備え
た内部に図示しない原子炉を設置した原子炉ウェル3
が、互いに連通してI字型状に構築されている。
2. Description of the Related Art In a boiling water nuclear power plant, the operation of opening and restoring a nuclear reactor is one of the main operations called critical path in the periodic inspection work. As shown in the plan view of FIG. 3, a reactor well 3 in which an unillustrated nuclear reactor is installed inside is provided with an in-reactor temporary storage pool 1 on one side and a fuel pool 2 on the other side.
Are communicated with each other and are constructed in an I-shape.

【0003】原子炉の開放と復旧作業は、原子炉ウェル
3から図示しないカバーの取外し及び取付けに始まり、
同じく図示しない原子炉格納容器の上蓋、と原子炉であ
る原子炉圧力容器の上蓋の夫々取外し及び取付け、原子
炉圧力容器内の蒸気乾燥器4及び気水分離器5の取外し
及び取付け、移動等の一連の作業が原子炉建屋の5階あ
るいは6階の位置にて実施される。また、この原子炉の
開放と復旧作業に携わる放射線作業従事者の被曝線量当
量は、原子力プラントの定期点検工事期間全体を通して
見ても常に上位にランクされる。
The opening and restoration work of the reactor begins with the removal and installation of the cover (not shown) from the reactor well 3.
Similarly, the upper lid of the reactor containment vessel (not shown) and the upper lid of the reactor pressure vessel, which is a reactor, are removed and attached, and the steam dryer 4 and the steam separator 5 in the reactor pressure vessel are removed, attached, and moved. Will be carried out on the 5th or 6th floor of the reactor building. Also, the radiation dose equivalent of radiation workers involved in the opening and restoration work of this nuclear reactor is always ranked high even during the entire periodic inspection work period of the nuclear power plant.

【0004】特に原子炉の開放作業においては、原子炉
圧力容器の上蓋取外し後に主蒸気系ラインへ水張りを行
い、さらに原子炉圧力容器への水張り等、炉水位を徐々
に上昇させながら、これと並行して原子炉圧力容器内か
ら蒸気乾燥器4及び気水分離器5の取外しを行う。
Particularly in the operation of opening the reactor, the main steam system line is filled with water after the upper lid of the reactor pressure vessel is removed, and further water filling of the reactor pressure vessel is performed while gradually raising the reactor water level. In parallel, the steam dryer 4 and the steam separator 5 are removed from the reactor pressure vessel.

【0005】この時の気水分離器5の取外しと移動につ
いては、予め図示しないシュラウドヘッドボルトの緩め
作業を、原子炉ウェル3における燃料交換機の床上にて
行わなければならないが、この際に、すでに機器仮置プ
ール1に移動して、裸のまま仮置きされている蒸気乾燥
器4からの高放射線量当量率の影響を強く受け易いた
め、この作業に従事する作業者が受ける被曝線量当量が
高くなる要因にもなっている。なお、蒸気乾燥器4を仮
置きしている機器仮置プール1内への水張りは、気水分
離器5の移動時に実施される。
Regarding the removal and movement of the steam separator 5 at this time, the work of loosening the shroud head bolt (not shown) must be performed in advance on the floor of the fuel exchanger in the reactor well 3, but at this time, The radiation dose equivalent received by the workers engaged in this work is strongly affected by the high radiation dose equivalent rate from the steam dryer 4 which has already been moved to the temporary storage pool 1 for equipment and is temporarily placed naked. Is also a factor that increases. The water filling into the equipment temporary storage pool 1 in which the steam dryer 4 is temporarily placed is performed when the steam separator 5 is moved.

【0006】さらに、原子炉の復旧作業に際して、原子
炉ウェル3内の水抜き後における原子炉ウェル3内の除
染、及びシュラウドヘッドボルトの締付け作業等に際し
ても、機器仮置プール1が原子炉ウェル3とI字型状の
直線的に配置されているので、蒸気乾燥器4からの放射
線量寄与が極めて大きい作業環境下となっている。
[0006] Further, when the reactor is restored, dewatering the reactor well 3 after dewatering the well 3, tightening the shroud head bolts, etc., the temporary equipment pool 1 Since the well 3 and the I-shape are arranged linearly, the working environment is such that the radiation dose contribution from the steam dryer 4 is extremely large.

【0007】したがって、これらの作業に際しては蒸気
乾燥器4からの高放射線量当量率を極力遮蔽する必要が
あり、従来は原子炉ウェル3内の作業が行われる場合に
は、機器仮置プール1で気中に仮置きした蒸気乾燥器4
からの放射線を遮蔽するために、遮蔽材である鉛シール
ドを原子炉ウェル3と機器仮置プール1間の連通部であ
るひな段6に仮積みしていた。
Therefore, in these operations, it is necessary to shield the high radiation dose equivalent rate from the steam dryer 4 as much as possible. Conventionally, when the operation in the reactor well 3 is performed, the temporary equipment pool 1 is used. Steam dryer 4 temporarily placed in the air
In order to shield the radiation from the equipment, a lead shield, which is a shielding material, was provisionally stacked on the tier 6 which is a communication portion between the reactor well 3 and the temporary equipment pool 1.

【0008】さらに、他の工法としては、この鉛シール
ドを図示しない天井クレーンで宙吊り状態にして遮蔽す
ることで対処したり、または、炉内機器の点検のために
一旦除去した図示しないコンクリートプラグを再びひな
段6に積み上げる工法が試みられていた。
Further, as another construction method, the lead shield is suspended by an overhead crane (not shown) and shielded, or a concrete plug (not shown) that has been removed for inspection of the equipment in the furnace is used. The method of stacking again on the tier 6 was being tried.

【0009】[0009]

【発明が解決しようとする課題】機器仮置プール1に蒸
気乾燥器4を気中で仮置きしている時に、原子炉ウェル
3における作業を実施する際に、放射線遮蔽のために原
子炉ウェル3と機器仮置プール1の間のひな段6に、鉛
シールドの仮積みや、天井クレーンによる鉛シールドの
宙吊り配設、及びコンクリートプラグを積み上げること
は、高放射線源である仮置きされた蒸気乾燥器4が作業
者がいる原子炉ウェル3と直線上に位置しているため、
これらの遮蔽体による被曝低減の効果は必ずしも十分で
はない。
When the steam dryer 4 is temporarily placed in the equipment temporary storage pool 1 in the air, when the work in the reactor well 3 is performed, the reactor well is shielded for radiation. Temporary stacking of lead shields, suspension of lead shields suspended by an overhead crane, and stacking of concrete plugs on the tier 6 between the equipment 3 and the temporary equipment pool 1 are temporary vapors that are high radiation sources. Since the dryer 4 is located on a straight line with the reactor well 3 in which the worker is located,
The effect of reducing the radiation exposure by these shields is not always sufficient.

【0010】また、炉内機器を機器仮置プール1に移動
するたびや、原子炉ウェル3に係る作業の都度にひな段
6に、遮蔽体の撤去及び配置を行うことは、定期点検作
業が繁雑で、その工程が増加することから定期点検期間
が長くなり、作業者の被曝が増すという不具合があっ
た。
Further, it is not necessary to perform the periodic inspection work every time the in-reactor equipment is moved to the temporary equipment pool 1 or when the shield 6 is removed and arranged in the tier 6 every time the work related to the reactor well 3 is performed. Since the process is complicated and the number of processes is increased, the periodic inspection period is extended and the worker is exposed to radiation.

【0011】本発明の目的とするところは、原子炉ウェ
ルに対して機器仮置プールをT字型状に配置すること
と、これに併せて機器仮置プール内に遮蔽扉を設けて作
業者の被曝低減と作業効率が向上する炉内機器仮置プー
ルを提供することにある。
An object of the present invention is to arrange a temporary equipment pool in a T-shape with respect to a reactor well, and to provide a shield door in the temporary equipment pool for the operator. It is to provide a temporary storage pool for in-core equipment that reduces the radiation exposure and improves work efficiency.

【0012】[0012]

【課題を解決するための手段】上記目的を達成するため
請求項1記載の発明に係る炉内機器仮置プールは、沸騰
水型原子力プラントで原子炉ウェルと連通して設けた蒸
気乾燥器及び気水分離器等の炉内機器を仮置するプール
において、原子炉ウェルとの通路を介してT字型状に配
置して仮置きした蒸気乾燥器及び気水分離器と前記原子
炉ウェルが直線的に並ばないことを特徴とする。
In order to achieve the above object, a temporary pool for in-reactor equipment according to the invention of claim 1 is a steam dryer provided in communication with a reactor well in a boiling water nuclear power plant, In a pool in which internal equipment such as a steam separator is temporarily placed, a steam dryer and a steam separator and the reactor well which are temporarily placed in a T-shape through a passage with the reactor well are placed. Characterized by not lining up in a straight line.

【0013】請求項2記載の発明に係る炉内機器仮置プ
ールは、沸騰水型原子力プラントで原子炉ウェルと連通
して設けた蒸気乾燥器及び気水分離器等の炉内機器を仮
置するプールにおいて、原子炉ウェルとの通路を介して
T字型状に配置して仮置きした蒸気乾燥器及び気水分離
器と前記原子炉ウェルが直線的に並ばないと共に、この
炉内機器の仮置プール内に開閉自在で水密に仕切る遮蔽
扉を設けたことを特徴とする。
According to a second aspect of the present invention, there is provided a temporary equipment pool for temporarily storing in-reactor equipment such as a steam dryer and a steam separator provided in communication with a reactor well in a boiling water nuclear plant. In the pool, the steam dryer and the steam separator temporarily arranged by being arranged in a T shape through the passage to the reactor well are not aligned linearly with the reactor well, and It is characterized by a watertight partition door that can be opened and closed in the temporary pool.

【0014】[0014]

【作用】請求項1記載の発明は、原子炉が開放されて原
子炉ウェル満水に至らない状態での原子炉ウェル内の関
連作業にに対して、炉内機器仮置プール内に着座、仮置
されている蒸気乾燥器からの放射線が原子炉ウェルに対
してT字型状に配置されている炉内機器仮置プールの壁
で遮断されるために、その高放射線量当量率は原子炉ウ
ェル付近にいる作業者へは影響が及ばない。
According to the invention described in claim 1, for the related work in the reactor well in a state where the reactor is opened and the reactor well is not filled with water, the reactor is temporarily seated in the temporary equipment pool and temporarily placed. Since the radiation from the installed steam dryer is blocked by the wall of the temporary storage pool for in-core equipment, which is arranged in a T shape with respect to the reactor well, the high radiation dose equivalent rate is high. Workers near the well are not affected.

【0015】請求項2記載の発明は、炉内機器仮置プー
ル内に着座、仮置されている蒸気乾燥器からの放射線が
原子炉ウェルに対してT字型状に配置されている炉内機
器仮置プールの壁で遮断する。さらに、炉内機器仮置プ
ールに仮置きした蒸気乾燥器及び気水分離器を遮蔽扉に
より、放射線を遮断すると共に、水没状態にすることに
より、遮蔽扉外の炉内機器仮置プール及び原子炉ウェル
における炉内機器仮置プール内に仮置きした炉内機器か
らの高放射線量当量率の影響を遮断する。
According to a second aspect of the present invention, the radiation from the steam dryer, which is seated and temporarily placed in the temporary equipment pool in the reactor, is arranged in a T-shape with respect to the reactor well. Shut off at the wall of the temporary equipment pool. In addition, the steam dryer and steam separator temporarily placed in the temporary equipment pool inside the reactor are shielded from radiation by being shielded from radiation and submerged so that the temporary equipment pool inside the reactor and the atomizer The influence of high radiation dose equivalent rate from the in-core equipment temporarily placed in the in-core equipment temporary pool in the reactor well is blocked.

【0016】[0016]

【実施例】本発明の一実施例を図面を参照して説明す
る。なお、上記した従来技術と同じ構成部分については
同一符号を付して詳細な説明を省略する。第1実施例
は、図1の平面図に示すように原子炉ウェル3と連通し
て一方に燃料プール2を、他方に連通部であるひな段6
を介してT字型に炉内機器仮置プール7を配置すると共
に、この炉内機器仮置プール7は、蒸気乾燥器4及び気
水分離器5を夫々左右に単独で搬入、仮置きして容易に
点検することのできる容積を確保して構成する。
DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS An embodiment of the present invention will be described with reference to the drawings. It should be noted that the same components as those in the above-described conventional technique are designated by the same reference numerals, and detailed description thereof will be omitted. In the first embodiment, as shown in the plan view of FIG. 1, the fuel well 2 is communicated with the reactor well 3 on one side, and the stage 6 which is a communication part on the other side.
The in-furnace equipment temporary storage pool 7 is arranged in a T-shape through the, and the steam drying equipment 4 and the steam separator 5 are individually loaded and temporarily placed in the left and right sides of the in-reactor equipment temporary storage pool 7. Secure a volume that can be easily inspected.

【0017】次ぎに上記構成による作用について、原子
炉の復旧作業時を例に説明する。機器仮置プール7には
夫々点検が終了した蒸気乾燥器4及び気水分離器5が左
右に離して仮置きしてあるが、原子炉ウェル3は、この
蒸気乾燥器4及び気水分離器5のいずれからも直線的な
配置ではないので、放射線は機器仮置プール7に遮られ
て直接的な高放射線量当量率の影響は受けない。
Next, the operation of the above configuration will be described by way of an example when the reactor is being restored. The steam dryer 4 and the steam separator 5, which have been inspected respectively, are temporarily placed in the temporary equipment pool 7 so as to be separated left and right, and the reactor well 3 has the steam dryer 4 and the steam separator 5. Since the radiation is not linearly arranged from any of No. 5, the radiation is blocked by the temporary equipment pool 7 and is not directly affected by the high radiation dose equivalent rate.

【0018】したがって、先ず満水状態の原子炉ウェル
3に、機器仮置プール7から気水分離器5を天井クレー
ンを用いて原子炉ウェル3内の図示しない原子炉圧力容
器位置へ水中移動した後に、原子炉水位を原子炉圧力容
器のフランジ面下約1mまで、時間をかけながら徐々に
下げる水抜き操作を行う。
Therefore, first, after moving the steam / water separator 5 from the temporary equipment pool 7 to the reactor well 3 in a full water state by using an overhead crane to a reactor pressure vessel position (not shown) in the reactor well 3, , The reactor water level is gradually lowered to about 1 m below the flange surface of the reactor pressure vessel over time.

【0019】その間に、炉水位の低下に追従して前記気
水分離器5も徐々に原子炉圧力容器内へ吊り降して行
き、シュラウドヘッドに着座させた後に、原子炉ウェル
3内の除染、及び燃料交換機の床上よりシュラウドヘッ
ドボルトの締付け作業を実施する。
In the meantime, the steam-water separator 5 is gradually suspended in the reactor pressure vessel in accordance with the decrease in the reactor water level, and after being seated on the shroud head, it is removed in the reactor well 3. Dyed and tighten the shroud head bolts from the floor of the refueling machine.

【0020】この時に原子炉ウェル3内と、機器仮置プ
ール7内に仮置きしてある蒸気乾燥器4との間は、その
距離が遠く、かつ、機器仮置プール7が原子炉ウェル3
とT字型状に配置されていることから、たとえ蒸気乾燥
器4が水抜き操作による機器仮置プール7内の水位が低
下して、気中に露出して着座した仮置き状態となって
も、この蒸気乾燥器4からの放射線は機器仮置プール7
の壁に遮断され、原子炉ウェル3においては高放射線量
当量率の影響は直接受けないために作業者の高放射線量
当量が増加することはなく被曝が低減される。
At this time, the distance between the reactor well 3 and the steam dryer 4 temporarily placed in the temporary equipment pool 7 is long, and the temporary equipment pool 7 is located in the reactor well 3
Since the steam dryer 4 is arranged in a T-shape, the water level in the equipment temporary storage pool 7 is lowered due to the draining operation, and the steam dryer 4 is exposed to the air and seated. Also, the radiation from this steam dryer 4 is stored in the temporary equipment pool 7.
Since the reactor well 3 is not directly affected by the high radiation dose equivalent rate, the high radiation dose equivalent of the worker is not increased and the exposure is reduced.

【0021】すなわち、本第1実施例によれば、定期検
査工事において、蒸気乾燥器4及び気水分離器5が夫々
左右単独で機器仮置プール7に着座、仮置きされるの
で、原子炉ウェル3内での各種作業に際して、作業者が
とりわけ蒸気乾燥器4からの高放射線量当量率の影響を
受けないので、作業者の作業効率と被曝低減が向上する
効果がある。
That is, according to the first embodiment, in the periodic inspection work, the steam dryer 4 and the steam separator 5 are individually seated in the temporary equipment pool 7 on the left and right sides, respectively. Since the worker is not particularly affected by the high radiation dose equivalent rate from the steam dryer 4 during various operations in the well 3, there is an effect that the worker's work efficiency and radiation exposure are improved.

【0022】第2実施例は、図1の平面図及び図2の要
部拡大図に示すように、原子炉ウェル3と連通して一方
に燃料プール2を、他方に連通部であるひな段6を介し
てT字型に炉内機器仮置プール7を配置すると共に、こ
の炉内機器仮置プール7は、蒸気乾燥器4及び気水分離
器5を夫々左右に単独で搬入、仮置きして容易に点検す
ることのできる容積を確保して構築する。
In the second embodiment, as shown in the plan view of FIG. 1 and the enlarged view of the essential portion of FIG. 2, the fuel pool 2 is connected to the reactor well 3 and the fuel pool 2 is connected to the reactor well 3 and the other is a communication part. The in-core device temporary storage pool 7 is arranged in a T-shape via 6 and the steam in-core device temporary storage pool 7 is independently loaded and temporarily installed on the left and right sides of the steam dryer 4 and the steam separator 5, respectively. And secure a volume that can be easily inspected.

【0023】さらに、炉内機器仮置プール7の一方の壁
面に、溝7aを、他方の壁面にピット7bを形成し、こ
のピット7b内に内遮蔽板8aと外遮蔽板8bを繰出し
て放射線を遮断すると共に、炉内機器仮置プール7内を
水密に仕切る遮蔽扉8を2箇所に設置して構成する。な
お、この内遮蔽板8aと外遮蔽板8bとからなる遮蔽扉
8は、内部が鉛板で外装を機器仮置プール7と同じステ
ンレス板による合板構造とし、図示しない油圧、電動駆
動装置によりスライドし、内遮蔽板8aと外遮蔽板8b
とが多段伸縮して開閉操作される。
Furthermore, a groove 7a is formed on one wall surface of the temporary equipment pool 7 and a pit 7b is formed on the other wall surface, and an inner shield plate 8a and an outer shield plate 8b are fed into the pit 7b to emit radiation. And a shielding door 8 for partitioning the inside of the furnace temporary storage pool 7 in a watertight manner is installed at two locations. The shield door 8 consisting of the inner shield plate 8a and the outer shield plate 8b has a lead plate inside and a plywood structure made of the same stainless steel plate as the temporary equipment pool 7 for the exterior, and is slid by an unillustrated hydraulic or electric drive device. The inner shield plate 8a and the outer shield plate 8b.
And are expanded and contracted in multiple stages to open and close.

【0024】また、前記遮蔽扉8については、その遮蔽
効果を考慮して内遮蔽板8aと外遮蔽板8b内の鉛板の
厚さを選定すれば、よりガンマ線の透過率は小さくな
り、不均一な放射線作業環境下での作業者の被曝低減が
図れて長時間の作業が可能になる。
Regarding the shielding door 8, if the thickness of the lead plates in the inner shielding plate 8a and the outer shielding plate 8b is selected in consideration of the shielding effect, the transmittance of gamma rays becomes smaller, and In a uniform radiation work environment, the worker's radiation exposure can be reduced and long-term work can be performed.

【0025】次に上記構成による作用について説明す
る。原子炉開放作業に際しては、予め原子炉ウェル3と
機器仮置プール7の連通部であるひな段6に積み上げら
れている図示しないコンクリートプラグを除去してか
ら、原子炉ウェル3内に設置した図示しない原子炉であ
る原子炉圧力容器の上蓋を取外した後に、主蒸気系ライ
ンの水張りと原子炉圧力容器の水張り等により、炉水位
を徐々に上昇させながら、これと並行して炉内機器の取
外しを行う。
Next, the operation of the above configuration will be described. During the reactor opening work, the concrete plugs (not shown) stacked in the tier 6 which is a communication portion between the reactor well 3 and the temporary equipment pool 7 are removed in advance, and then the reactor well 3 is installed in the illustrated state. After removing the upper lid of the reactor pressure vessel, which is a nuclear reactor, gradually increase the reactor water level by water filling the main steam system line and water filling the reactor pressure vessel, etc. Remove it.

【0026】初めに蒸気乾燥器4を取外して、機器仮置
プール7における蒸気乾燥器ピット7cに気中移動し、
着座仮置きしたら蒸気乾燥器ピット7c側の遮蔽扉8を
閉じて、機器仮置プール7内で蒸気乾燥器4と原子炉ウ
ェル3とを水密で、かつ放射線と隔離した状態にした後
に、蒸気乾燥器ピット7c内へ単独注水を行って、蒸気
乾燥器4を水没させることにより、蒸気乾燥器4から蒸
気乾燥器ピット7c外へ与える高放射線量当量率の影響
が遮断される。
First, the steam dryer 4 is detached and moved to the steam dryer pit 7c in the temporary equipment pool 7 in the air,
After the seat is temporarily placed, the shielding door 8 on the side of the steam dryer pit 7c is closed to make the steam dryer 4 and the reactor well 3 in the temporary equipment pool 7 watertight and isolated from radiation, and then steam. By independently pouring water into the dryer pit 7c and submerging the steam dryer 4 in the water, the influence of the high radiation dose equivalent rate from the steam dryer 4 to the outside of the steam dryer pit 7c is blocked.

【0027】これにより、原子炉水位を原子炉ウェル3
内に満水状態とする過程で、燃料交換機の床上にて行う
気水分離器5のシュラウドヘッドボルトの緩め作業と、
原子炉圧力容器内から水中移動、取外しを低放射線量当
量率下で実施することができる。
As a result, the reactor water level is adjusted to the reactor well 3
Loosening the shroud head bolts of the steam separator 5 on the floor of the fuel exchanger in the process of filling the inside with water,
It is possible to move and remove water from the reactor pressure vessel at a low radiation dose equivalent rate.

【0028】この取外した気水分離器5は機器仮置プー
ル7における気水分離器ピット7dに気中移動し、着座
仮置きしたら気水分離器ピット7d側の遮蔽扉8を閉じ
て、機器仮置プール7内で気水分離器5と原子炉ウェル
3とを水密で、かつ放射線と隔離した状態にした後に、
気水分離器ピット7d内へ単独注水を行って、気水分離
器5を水没させることにより、気水分離器5から気水分
離器ピット7d外へ与える高放射線量の影響を遮断す
る。
The removed water / water separator 5 moves to the air / water separator pit 7d in the equipment temporary storage pool 7 in the air, and when it is temporarily seated, the shielding door 8 on the side of the water / water separator pit 7d is closed to remove the equipment. After making the steam separator 5 and the reactor well 3 watertight in the temporary pool 7 and isolated from radiation,
By independently injecting water into the steam separator pit 7d and submerging the steam separator 5, the influence of the high radiation dose from the steam separator 5 to the outside of the steam separator pit 7d is blocked.

【0029】なお、この気水分離器5及び前記蒸気乾燥
器4は、夫々の気水分離器ピット7d及び蒸気乾燥器ピ
ット7cにおいて、単独で水抜きをしてから点検作業を
行うが、いずれも気水分離器ピット7d及び蒸気乾燥器
ピット7c外に高放射線量当量率の影響を与えずに作業
ができるので、機器仮置プール7内の高放射線量当量率
が低減される。また、点検済みの蒸気乾燥器4及び気水
分離器5は、夫々蒸気乾燥器ピット7c及び気水分離器
ピット7d内に、再び注水して復旧作業まで仮置きする
ことにより機器仮置プール7を含む周囲への高放射線量
の影響が遮断される。
The steam separator 5 and the steam dryer 4 are individually drained in the steam separator pit 7d and the steam dryer pit 7c, respectively, and then checked. Since the work can be performed outside the steam separator pit 7d and the steam dryer pit 7c without being affected by the high radiation dose equivalent rate, the high radiation dose equivalent rate in the temporary equipment pool 7 is reduced. In addition, the steam dryer 4 and the steam separator 5 which have been inspected are again poured into the steam dryer pit 7c and the steam separator pit 7d, respectively, and are temporarily placed until the restoration work so that the equipment temporary storage pool 7 The influence of high radiation dose on the surroundings including is blocked.

【0030】また、原子炉の復旧作業時には、気水分離
器ピット7d側の遮蔽扉8を開いて、気水分離器5を機
器仮置プール7より天井クレーンを用いて原子炉ウェル
3内の図示しない原子炉圧力容器位置へ水中移動した後
に、原子炉水位を原子炉ウェル3内の満水状態から原子
炉圧力容器のフランジ面下約1mまで、時間をかけなが
ら徐々に下げる水抜き操作を行う。
When the reactor is restored, the shield door 8 on the steam / water separator pit 7d side is opened, and the steam / water separator 5 is moved from the temporary equipment pool 7 into the reactor well 3 using an overhead crane. After the water is moved to the position of the reactor pressure vessel (not shown), the water level of the reactor is gradually lowered from the full state in the reactor well 3 to about 1 m below the flange surface of the reactor pressure vessel over time. .

【0031】その間に、炉水位の低下に追従して前記気
水分離器5も徐々に原子炉圧力容器内へ吊り降して行
き、シュラウドヘッドに着座させた後に、原子炉ウェル
3内の除染、及び燃料交換機の床上よりシュラウドヘッ
ドボルトの締付け作業を蒸気乾燥器4の移動、取付けの
前に実施する。
In the meantime, the steam-water separator 5 is gradually suspended in the reactor pressure vessel in accordance with the decrease in the reactor water level, and after being seated on the shroud head, it is removed in the reactor well 3. Dyeing and tightening work of the shroud head bolt from the floor of the refueling machine are carried out before moving and attaching the steam dryer 4.

【0032】この原子炉の復旧作業の場合も、前記原子
炉開放作業時と同様に原子炉ウェル3における燃料交換
機の床上での作業は、蒸気乾燥器4が機器仮置プール7
の蒸気乾燥器ピット7c内で水中に仮置きされているた
め、その高放射線量当量率の影響は受けないことから作
業者の被曝が低減される。
Also in the case of this reactor restoration work, as in the case of the reactor opening work, the work on the floor of the fuel exchanger in the reactor well 3 is performed by the steam dryer 4 in the temporary equipment pool 7.
Since it is temporarily placed in water in the steam dryer pit 7c, it is not affected by the high radiation dose equivalent rate, so that the worker's exposure is reduced.

【0033】また、本第2実施例においても、原子炉ウ
ェル3と機器仮置プール7の配置が上記第1実施例と同
じT字型状であることから、これによる作用と効果は同
様で、蒸気乾燥器4及び気水分離器5を夫々機器仮置プ
ール7の蒸気乾燥器ピット7c及び気水分離器ピット7
d内に収容した際に、原子炉ウェル3においては蒸気乾
燥器4及び気水分離器5のいずれからも直線的な位置で
はないので、直接的な高放射線量当量率の影響は受けな
い。
Also in the second embodiment, since the arrangement of the reactor well 3 and the temporary equipment pool 7 is the same T-shape as in the first embodiment, the operation and effect by this are the same. The steam dryer 4 and the steam separator 5 are respectively connected to the steam dryer pit 7c and the steam separator pit 7 of the equipment temporary storage pool 7.
When it is housed in d, it is not in a linear position in the reactor well 3 from either the steam dryer 4 or the steam separator 5, so that it is not directly affected by the high radiation dose equivalent rate.

【0034】なお、機器仮置プール7の蒸気乾燥器ピッ
ト7c及び気水分離器ピット7d内に着座、仮置して、
夫々の遮蔽扉8を閉じることで相互と機器仮置プール7
及び原子炉ウェル3とが、高放射線量当量から遮断さ
れ、さらに、夫々の蒸気乾燥器ピット7c及び気水分離
器ピット7d内に注水することにより、一層原子炉ウェ
ル3内の各種作業時における作業者に対する被曝が低減
できる。
It is to be noted that the equipment temporary storage pool 7 is seated and temporarily placed in the steam dryer pit 7c and the steam separator pit 7d,
By closing the respective shielding doors 8, the mutual equipment temporary storage pool 7
And the reactor well 3 are shielded from the high radiation dose equivalent, and water is further injected into the steam dryer pit 7c and the steam separator pit 7d, respectively, so that various operations in the reactor well 3 can be further performed. The exposure to workers can be reduced.

【0035】[0035]

【発明の効果】以上本発明によれば、原子力プラントの
定期点検工事期間全体を通して作業者の被曝線量当量が
上位にランクされている原子炉の開放、及び復旧作業に
際して、炉内機器仮置プール内での炉内機器の点検作業
と、原子炉ウェル内の各種作業が炉内機器からの高放射
線量当量率の影響を受けず、さらに作業者の被曝低減に
よる安全性向上と、定期点検工事期間が短縮される効果
がある。
As described above, according to the present invention, during the opening and restoration work of the reactor whose exposure dose equivalent of the worker is ranked higher throughout the periodic inspection construction period of the nuclear power plant, the temporary storage pool for the reactor equipment is provided. The inspection work of the equipment inside the reactor and the various work inside the reactor well are not affected by the high radiation dose equivalent rate from the equipment inside the reactor, and the safety is improved by reducing the exposure of workers and the periodic inspection work is performed. This has the effect of shortening the period.

【図面の簡単な説明】[Brief description of drawings]

【図1】本発明に係る第1実施例の炉内機器仮置プール
等の平面図。
FIG. 1 is a plan view of an in-core device temporary storage pool and the like according to a first embodiment of the present invention.

【図2】本発明に係る第2実施例の遮蔽扉の要部拡大斜
視図。
FIG. 2 is an enlarged perspective view of a main part of a shielding door according to a second embodiment of the present invention.

【図3】従来の炉内機器仮置プール等の平面図。FIG. 3 is a plan view of a conventional in-core device temporary storage pool and the like.

【符号の説明】[Explanation of symbols]

1,7…炉内機器仮置プール、2…燃料プール、3…原
子炉ウェル、4…蒸気乾燥器、5…気水分離器、6…ひ
な段、7a…仮置プール壁の溝、7b…仮置プール壁の
ピット、7c…蒸気乾燥器ピット、7d…気水分離器ピ
ット、8…遮蔽扉、8a…内遮蔽板、8b…外遮蔽板。
1, 7 ... Temporary equipment pool, 2 ... Fuel pool, 3 ... Reactor well, 4 ... Steam dryer, 5 ... Steam separator, 6 ... Stage, 7a ... Groove of temporary pool wall, 7b ... pit of temporary pool wall, 7c ... steam dryer pit, 7d ... steam separator pit, 8 ... shielding door, 8a ... inner shielding plate, 8b ... outer shielding plate.

Claims (2)

【特許請求の範囲】[Claims] 【請求項1】 沸騰水型原子力プラントで原子炉ウェル
と連通して設けた蒸気乾燥器及び気水分離器等の炉内機
器を仮置するプールにおいて、原子炉ウェルとの通路を
介してT字型状に配置して仮置きした蒸気乾燥器及び気
水分離器と前記原子炉ウェルが直線的に並ばないことを
特徴とする炉内機器仮置プール。
1. A pool in which in-reactor equipment such as a steam dryer and a steam separator provided in communication with a reactor well in a boiling water nuclear power plant is temporarily placed, through a passage to the reactor well. A temporary equipment pool for in-reactor equipment, wherein the steam dryer and steam separator, which are arranged in a V shape and temporarily placed, and the reactor well are not aligned in a straight line.
【請求項2】 沸騰水型原子力プラントで原子炉ウェル
と連通して設けた蒸気乾燥器及び気水分離器等の炉内機
器を仮置するプールにおいて、原子炉ウェルとの通路を
介してT字型状に配置して仮置きした蒸気乾燥器及び気
水分離器と前記原子炉ウェルが直線的に並ばないと共
に、この炉内機器の仮置プール内に開閉自在で水密に仕
切る遮蔽扉を設けたことを特徴とする炉内機器仮置プー
ル。
2. In a pool in which internal equipment such as a steam dryer and a steam separator provided in communication with a reactor well in a boiling water nuclear power plant is temporarily placed, a T is provided through a passage to the reactor well. The steam dryer and steam separator that are temporarily placed in a V-shape and the reactor well are not aligned in a straight line, and a shield door that can be opened and closed freely and watertightly partitions in the temporary pool of the in-reactor equipment. A temporary storage pool for in-core equipment, which is characterized by being provided.
JP6005306A 1994-01-21 1994-01-21 Reactor internal equipment temporary setting pool Pending JPH07209478A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP6005306A JPH07209478A (en) 1994-01-21 1994-01-21 Reactor internal equipment temporary setting pool

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP6005306A JPH07209478A (en) 1994-01-21 1994-01-21 Reactor internal equipment temporary setting pool

Publications (1)

Publication Number Publication Date
JPH07209478A true JPH07209478A (en) 1995-08-11

Family

ID=11607598

Family Applications (1)

Application Number Title Priority Date Filing Date
JP6005306A Pending JPH07209478A (en) 1994-01-21 1994-01-21 Reactor internal equipment temporary setting pool

Country Status (1)

Country Link
JP (1) JPH07209478A (en)

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