JP2965635B2 - Inspection method in fast breeder reactor - Google Patents
Inspection method in fast breeder reactorInfo
- Publication number
- JP2965635B2 JP2965635B2 JP2201151A JP20115190A JP2965635B2 JP 2965635 B2 JP2965635 B2 JP 2965635B2 JP 2201151 A JP2201151 A JP 2201151A JP 20115190 A JP20115190 A JP 20115190A JP 2965635 B2 JP2965635 B2 JP 2965635B2
- Authority
- JP
- Japan
- Prior art keywords
- inert gas
- core
- reactor
- primary pump
- reactor vessel
- 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.)
- Expired - Lifetime
Links
Classifications
-
- 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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- Monitoring And Testing Of Nuclear Reactors (AREA)
Description
【発明の詳細な説明】 [発明の目的] (産業上の利用分野) 本発明は液体金属冷却型高速増殖炉の原子炉容器内に
設置されている炉内構造物を供用期間中検査するための
高速増殖炉内の検査方法に関する。DETAILED DESCRIPTION OF THE INVENTION [Object of the Invention] (Industrial application field) The present invention is to inspect a reactor internal structure installed in a reactor vessel of a liquid metal cooled fast breeder reactor during a service period. The inspection method in the fast breeder reactor.
(従来の技術) 従来、この種の高速増殖炉は例えば第5図に示すよう
に原子炉容器1の内部に炉心2と、この炉心2お支持し
かつ炉心冷却材の流路を形成する炉心支持構造物3と、
この炉心支持構造物3の荷重を原子炉容器1に伝達する
炉心支持スカート4と、冷却材のホットプレナム5とコ
ールドプレナム6との境界を形成しかつ炉心の水平荷重
を原子炉容器1に伝する下部隔壁7と、一次ポンプ8
と、中間熱交換器9と、炉心上部機構10を収納してい
る。また、一次ポンプ8、中間熱交換器9および炉心上
部機構10は原子炉容器1の蓋を形成するルーフスラブ11
に支持されている。炉心支持構造物3はさらに炉心2の
重量を支持する2枚の炉心支持板3aと、炉心支持板3aの
剛性を補強する下部補強3bと、一次ポンプ8から吐出さ
れた高圧冷却材を炉心2に導く入口プレナム3cから構成
されている。2. Description of the Related Art Conventionally, a fast breeder reactor of this type has a core 2 inside a reactor vessel 1 and a core supporting the core 2 and forming a flow path for core coolant as shown in FIG. 5, for example. A support structure 3,
A core support skirt 4 for transmitting the load of the core support structure 3 to the reactor vessel 1, a boundary between the hot plenum 5 and the cold plenum 6 of the coolant, and a horizontal load of the core are transmitted to the reactor vessel 1. Lower partition 7 and primary pump 8
, An intermediate heat exchanger 9 and an upper core mechanism 10. The primary pump 8, the intermediate heat exchanger 9, and the core upper mechanism 10 are provided with a roof slab 11 for forming a lid of the reactor vessel 1.
It is supported by. The core support structure 3 further includes two core support plates 3a for supporting the weight of the core 2, a lower reinforcement 3b for reinforcing the rigidity of the core support plate 3a, and a high-pressure coolant discharged from the primary pump 8 for the core 2. It is composed of an inlet plenum 3c leading to the entrance.
このように構成された高速増殖炉において、原子炉容
器1内の構造物の溶接部のうち、バウンダリを形成する
か又は炉心2を支持する重要溶接部を第6図に示す。な
お、図中、重要溶接部のうち周方向継手を×印、長手方
向継手を で示している。In the fast breeder reactor thus configured, important welds that form a boundary or support the core 2 among the welds of the structures in the reactor vessel 1 are shown in FIG. In the figure, the crosswise joints of the important welds are marked with x and the longitudinal joints are marked. Indicated by.
これらの重要溶接部の供用期間中検査を実施するに
は、以下の3つの方法が考えられる。The following three methods are conceivable for performing the inspection during the service period of these important welds.
(1)検査対象機器を分解し、炉外に取出す方法。(1) A method of disassembling the inspection target equipment and taking it out of the furnace.
(2)原子炉容器内の冷却材を汲上げて液位を下げ、検
査対象機器をガス中に露出させる方法。(2) A method in which the coolant inside the reactor vessel is pumped down to lower the liquid level, and the inspection target equipment is exposed to the gas.
(3)超音波発信器を用いた冷却材透視装置により画像
を結んで観察する方法。(3) A method of connecting and observing images with a coolant see-through device using an ultrasonic transmitter.
(発明が解決しようとする課題) しかしながら、(1)の方法では検査対象が著しく限
定され、重要溶接部をカバーしきれない、(2)の方法
では事前に炉心を退避させる等の準備作業及び付帯設備
が膨大となる、(3)の方法では現状技術レベルの解像
能力の限界により微細な画像情報が得られない等の課題
があった。(Problems to be Solved by the Invention) However, in the method (1), the inspection target is extremely limited, and the important welded portion cannot be covered. In the method (2), preparation work such as evacuation of the core in advance and In the method (3), there is a problem that minute image information cannot be obtained due to the limitation of the resolution capability of the current technology level.
そこで本発明は上記課題を解決するためになされたも
ので、その目的は、原子炉容器内構造物の溶接部のうち
バウンダリを形成するか又は炉心を支持する重要溶接部
について詳細に観察可能でかつ検査後の原子炉運転に支
障を来すことがないように構成した高速増殖炉内の検査
方法を提供することにある。Therefore, the present invention has been made to solve the above-described problems, and an object of the present invention is to enable detailed observation of an important welded portion that forms a boundary or supports a core in a welded portion of a reactor vessel internal structure. Another object of the present invention is to provide an inspection method in a fast breeder reactor configured so as not to hinder the operation of the reactor after the inspection.
[発明の構成] (課題を解決するための手段) 本発明は原子炉容器と、原子炉容器と、この原子炉容
器内に配設された炉心を支持する炉心支持構造物と、前
記炉心内に制御棒を挿入する制御棒駆動機構と、前記原
子炉容器の上部を覆う蓋と、この蓋に支持されて前記制
御棒駆動機構を支持する炉心上部機構と、前記原子炉容
器内の冷却材を強制循環させる循環部が前記蓋内を貫通
し上部が前記蓋に固定して設置された一次ポンプとから
なる高速増殖炉内の検査方法において、前記一次ポンプ
を取り外してその一次ポンプの設置位置に炉内検査装置
を設置し、前記原子炉容器内に配設された原子炉内構造
物の溶接部近傍に不活性ガスを貯留しかつ上部に不活性
ガス空間消滅用小孔を有する仕切板を設置して不活性ガ
ス空間を形成し、この不活性ガス空間に前記炉内検査装
置に設けた監視カメラを挿入して前記溶接部近傍を監視
し健全性を検査するとともに、検査後に前記小孔から前
記不活性ガス空間内に充満した不活性ガスを外部に流出
して前記不活性ガス空間を消滅させた後、前記炉内検査
装置を引抜き、この引抜き個所に前記一次ポンプを戻す
ことを特徴とする。[Constitution of the Invention] (Means for Solving the Problems) The present invention relates to a nuclear reactor vessel, a nuclear reactor vessel, a core support structure for supporting a core provided in the nuclear reactor vessel, and A control rod drive mechanism for inserting a control rod into the reactor vessel, a lid covering the upper part of the reactor vessel, an upper core mechanism supported by the lid to support the control rod drive mechanism, and a coolant in the reactor vessel In a method for inspecting the inside of a fast breeder reactor, a circulating section for forcibly circulating the inside of the lid and an upper part being fixed to the lid and being installed on the upper part of the fast breeder reactor, the primary pump is removed and the installation position of the primary pump is removed. A partition plate having an in-reactor inspection device installed therein, storing an inert gas near a welded portion of a reactor internal structure disposed in the reactor vessel, and having an inert gas space extinguishing hole at an upper portion thereof. To create an inert gas space, A monitoring camera provided in the in-furnace inspection device is inserted into a gas space to monitor the vicinity of the weld and inspect the soundness.After the inspection, the inert gas filled in the inert gas space from the small hole is inspected. After flowing out to the outside to eliminate the inert gas space, the in-furnace inspection device is withdrawn, and the primary pump is returned to the withdrawal point.
(作用) 本発明では、原子炉容器内の冷却材浸漬部に仕切板を
設けることにより、仕切板に囲まれた領域に不活性ガス
を送り込んで不活性ガス空間を形成する。次にこの不活
性ガス空間に炉内検査装置の先端を投入し、先端に設置
されたファイバースコープ又はCCDカメラにより検査対
象箇所を観察する。一方、原子炉容器内構造物の溶接部
のうち、バウンダリを形成するか又は炉心を支持する重
要溶接部はすべてこの不活性ガス空間内に位置するよう
にあらかじめ板取り構成されているため、前記炉内検査
装置によりすべて検査可能となる。また、検査後に不活
性ガス空間内の不活性ガスを小孔を通して外部に流出
し、不活性ガス空間を消滅させることにより、その後の
原子炉運転に支障を来すことがないようにできる。(Operation) In the present invention, the partition plate is provided in the coolant immersion portion in the nuclear reactor vessel, so that an inert gas is fed into a region surrounded by the partition plate to form an inert gas space. Next, the tip of the in-furnace inspection apparatus is put into this inert gas space, and the inspection target is observed with a fiber scope or a CCD camera installed at the tip. On the other hand, among the welded portions of the internal structure of the reactor vessel, the important welded portions that form the boundary or support the core are all pre-boarded so as to be located in the inert gas space. All inspections can be performed by the furnace inspection device. Further, after the inspection, the inert gas in the inert gas space flows out through the small holes to the outside, and the inert gas space is extinguished, so that the subsequent operation of the reactor is not hindered.
(実施例) 第1図から第4図を参照して本発明に係る高速増殖炉
内の検査方法の一実施例を説明する。(Embodiment) An embodiment of an inspection method in a fast breeder reactor according to the present invention will be described with reference to FIGS.
第1図において、原子炉容器1の内部には炉心2と、
この炉心2を支持しかつ炉心冷却材の流路を形成する炉
心構造物3と、冷却材のホットプレナム5とコールドプ
レナム6との境界を形成しかつ炉心の水平荷重を原子炉
容器に伝達する下部隔壁7と、一次ポンプ8と、中間熱
交換器9と、炉心上部機構10を収納している。一次ポン
プ8、中間熱交換器9および炉心上部機構10は原子炉容
器1の蓋を形成するルーフスラブ11に支持されている。
炉心支持構造物3はさらに炉心2の重量を支持する2枚
の炉心支持板(うち1枚は極厚鍛造板)3aと、一次ポン
プ8から吐出された高圧冷却材を炉心に導く入口プレナ
ム3cとから構成されている。入口プレナム3cの外側には
第1の仕切板12、一次ポンプ8との取合部には一次ポン
プ用受台の機能も併せ持つ第2の仕切板13が設置されて
いる。下部隔壁7には、一次ポンプ8及び中間熱交換器
9を収納するスタンドパイプ7aが設置されており、一次
ポンプ用スタンドパイプ7aは下方に延長されて第3の仕
切板14を形成している。In FIG. 1, a reactor core 2 is provided inside a reactor vessel 1,
A core structure 3 that supports the core 2 and forms a flow path for the core coolant, forms a boundary between the hot plenum 5 and the cold plenum 6 of the coolant, and transmits the horizontal load of the core to the reactor vessel. The lower partition 7, the primary pump 8, the intermediate heat exchanger 9, and the core upper mechanism 10 are housed therein. The primary pump 8, the intermediate heat exchanger 9, and the core upper mechanism 10 are supported by a roof slab 11 that forms a lid of the reactor vessel 1.
The core support structure 3 further includes two core support plates 3a (one of which is an extremely thick forged plate) 3a for supporting the weight of the core 2, and an inlet plenum 3c for guiding the high-pressure coolant discharged from the primary pump 8 to the core. It is composed of A first partition plate 12 is provided outside the inlet plenum 3c, and a second partition plate 13 having a function of a pedestal for the primary pump is provided at a connection portion with the primary pump 8. A standpipe 7a for accommodating the primary pump 8 and the intermediate heat exchanger 9 is provided in the lower partition wall 7. The standpipe 7a for the primary pump is extended downward to form a third partition plate 14. .
このように構成された高速増殖炉において、原子炉容
器1内の構造物の溶接部のうち、バウンダリを形成する
か又は炉心2を支持する重要溶接部を第2図に示す。な
お、図中、重要溶接部のうち周方向継手を×印、長手方
向継手を で示している。In the fast breeder reactor configured as described above, important welds that form a boundary or support the core 2 among the welds of the structures in the reactor vessel 1 are shown in FIG. In the figure, the crosswise joints of the important welds are marked with x and the longitudinal joints are marked. Indicated by.
また、検査時においては一次ポンプを引抜き、ルーフ
スラブ上の一次ポンプ設置位置に炉内検査装置15(第3
図及び第4図参照)を設置する構造としており、本装置
は中間部に支持脚15aを有し、中間部から下方は多関節
構造15bとなっている。At the time of inspection, the primary pump was pulled out, and the furnace inspection device 15 (the third
(See FIG. 4 and FIG. 4). The apparatus has a support leg 15a at an intermediate portion, and an articulated structure 15b below the intermediate portion.
次に本実施例の作用を説明する。 Next, the operation of the present embodiment will be described.
検査時において、第1図および第2図に示したルーフ
スラブ11の一次ポンプ8を取り外し、この一次ポンプ8
の設置位置に第3図(a)に示すように炉内検査装置15
を設置し、原子炉容器1内に多関節構造15bを挿入す
る。この時、支持脚15aを左右に拡げて一次ポンプ用ス
タンドパイプ7aに接触させ中間部の位置を固定した後、
多関節構造15bを動かしてその先端を原子炉容器1内の
冷却材中の第3の仕切板14に囲まれた領域に下に差込
む。At the time of inspection, the primary pump 8 of the roof slab 11 shown in FIGS.
As shown in FIG. 3 (a), the furnace
Is installed, and the articulated structure 15b is inserted into the reactor vessel 1. At this time, after extending the support legs 15a to the left and right to contact the primary pump stand pipe 7a and fix the position of the intermediate portion,
By moving the articulated structure 15b, its tip is inserted downward into a region surrounded by the third partition plate 14 in the coolant in the reactor vessel 1.
この状態で上方から不活性ガスを供給すると、第3図
(b)に拡大して示したように多関節構造15bの先端か
ら気泡となって流出し、第3の仕切板14と下部隔壁7と
に囲まれた領域に不活性ガスが蓄積されて不活性ガス空
間16が形成される。When an inert gas is supplied from above in this state, as shown in an enlarged manner in FIG. 3 (b), the inert gas flows out as bubbles from the tip of the articulated structure 15b, and the third partition plate 14 and the lower partition 7 The inert gas is accumulated in a region surrounded by the above and the inert gas space 16 is formed.
なお、第3の仕切板14の上端部には第3の小孔14aが
設けられており、ここから不活性ガスは外部へ流出する
が、炉内検査装置から供給される不活性ガス流量の方が
大なので、第3の仕切板14と下部隔壁に囲まれた領域に
は不活性ガス空間16が形成されることになる。A third small hole 14a is provided at the upper end of the third partition plate 14, from which the inert gas flows to the outside. Therefore, an inert gas space 16 is formed in a region surrounded by the third partition plate 14 and the lower partition.
次に、第4図(a)および(b)に示すように多関節
構造15bの先端を不活性ガス空間16に挿入し、多関節構
造の先端から不活性ガスを供給しながら多関節構造の先
端に組込まれたファイバースコープ又はCCDカメラによ
り検査対象箇所を観察する。Next, as shown in FIGS. 4 (a) and 4 (b), the tip of the multi-joint structure 15b is inserted into the inert gas space 16, and the inert gas is supplied from the tip of the multi-joint structure. Observe the inspection target using a fiberscope or CCD camera installed at the tip.
第1の仕切板12または第2の仕切板13に囲まれた不活
性ガス空間16についても上記と同様の手順により観察可
能であり、結果的に第2図に示した重要溶接部はすべて
詳細に観察できることになる。The inert gas space 16 surrounded by the first partition plate 12 or the second partition plate 13 can also be observed by the same procedure as described above. As a result, all the important welds shown in FIG. Can be observed.
炉内検査終了後は不活性ガスの供給を停止すると、第
1の小孔12a、第2の小孔13a、第3の小孔14aから不活
性ガスは外部、つまり原子炉圧力容器内の冷却材上方の
不活性ガス溜りの上部プレナムに流出する。これによっ
て不活性ガス空間は消滅し、炉内検査装置15を引抜い
て、一次ポンプ8を挿入すれば、原子炉は再び運転可能
な状態に復帰する。When the supply of the inert gas is stopped after the completion of the in-reactor inspection, the inert gas is discharged from the first small hole 12a, the second small hole 13a, and the third small hole 14a to the outside, that is, the cooling inside the reactor pressure vessel. It flows into the upper plenum of the inert gas reservoir above the material. As a result, the inert gas space disappears, and the reactor is returned to an operable state again by pulling out the furnace inspection device 15 and inserting the primary pump 8.
上記実施例は、タンク型高速増殖炉の原子炉容器内の
重要溶接部を検査する場合を想定した適用例であるが、
冷却材中にガス空間を形成して炉内検査する方法は、他
の型の原子炉または他の検査対象に対しても適用可能で
ある。例えば機器表面の損傷状態、変形、振動の観察や
異物探索等への適用が考えられる。The above embodiment is an application example assuming a case where an important weld in a reactor vessel of a tank type fast breeder reactor is inspected.
The method of forming a gas space in the coolant and performing the in-core inspection is applicable to other types of nuclear reactors or other inspection targets. For example, application to observation of a damaged state, deformation, and vibration of the surface of the device, search for foreign matter, and the like can be considered.
なお、本発明の実施態様としてはつぎのとおりであ
る。The embodiments of the present invention are as follows.
(1)原子炉容器と、この原子炉容器内に設置された炉
心を支持する炉心支持構造物と、前記炉心内に制御棒を
挿入する制御棒駆動機構と、前記原子炉容器の上部を覆
う蓋と、この蓋に支持されて前記制御棒駆動機構を支持
する炉心上部機構と、前記原子炉容器内の冷却材を強制
循環させる循環部が前記蓋内を貫通し上部が前記蓋に固
定して設置された一次ポンプとからなる高速増殖炉内の
検査方法において、前記一次ポンプを取り外してその一
次ポンプの設置位置に炉内検査装置を設置し、前記原子
炉容器内に配設された原子炉内構造物の溶接部近傍に不
活性ガスを貯留しかつ上部に不活性ガス空間消滅用小孔
を有する仕切板を設置して不活性ガス空間を形成し、こ
の不活性ガス空間に前記炉内検査装置に設けた監視カメ
ラを挿入して前記溶接部近傍を監視し健全性を検査する
とともに、検査後に前記小孔から前記不活性ガス空間内
に充満した不活性ガスを外部に流出して前記不活性ガス
空間を消滅させた後、前記炉内検査装置を引抜き、この
引抜き個所に前記一次ポンプを戻す。(1) A reactor vessel, a core support structure for supporting a reactor core installed in the reactor vessel, a control rod drive mechanism for inserting a control rod into the reactor core, and covering an upper part of the reactor vessel A lid, a core upper mechanism supported by the lid and supporting the control rod drive mechanism, and a circulating unit for forcibly circulating a coolant in the reactor vessel penetrates through the lid and the upper part is fixed to the lid. In the inspection method in the fast breeder reactor comprising a primary pump installed in the reactor, the primary pump is removed, an in-core inspection device is installed at a position where the primary pump is installed, and the nuclear reactor installed in the reactor vessel is installed. An inert gas space is formed by storing an inert gas near the welded portion of the furnace internals and installing a partition plate having an inert gas space extinguishing hole at the top to form an inert gas space. Insert the surveillance camera provided in the internal inspection device and After monitoring the vicinity of the contact portion and inspecting the soundness, after the inspection, the inert gas filled in the inert gas space flows out to the outside from the small hole to extinguish the inert gas space, and then the furnace The internal inspection device is withdrawn, and the primary pump is returned to this withdrawal point.
(2)上記仕切板に囲まれた領域に不活性ガスを送り込
むための不活性ガス供給装置をドアバルブを介してルー
フスラブ上に設置する。(2) An inert gas supply device for sending an inert gas into a region surrounded by the partition plate is installed on the roof slab via a door valve.
(3)上記不活性ガス空間に炉内観察のためのファイバ
ースコープ又はCCDカメラを導く炉内検査装置をドアバ
ルブを介してルーフスラブ上に設置する。(3) Install a fiberscope or a CCD camera for in-furnace inspection to guide the CCD camera into the inert gas space on the roof slab via a door valve.
(4)上記不活性ガス供給装置と炉内検査装置の機能を
併せ持つ不活性ガス供給・検査装置を配備する。(4) An inert gas supply / inspection device having the functions of the above inert gas supply device and the in-furnace inspection device is provided.
(5)原子炉容器内構造物の溶接部のうち、バウンダリ
を形成するか又は炉心を支持する重要溶接部については
すべて前記の不活性ガス空間に位置するように板取りす
る。(5) Of the welded portions of the internal structure of the reactor vessel, all the important welded portions that form the boundary or support the core are trimmed so as to be located in the inert gas space.
[発明の効果] 本発明によれば、原子炉容器1次冷却材の内部に不活
性ガス空間を形成するための仕切板を有し、かつ、ルー
フスラブ上の一次ポンプ設置場所に不活性ガス供給装置
及び炉内検査装置を設置する構造となっているため、仕
切板に囲まれた領域を不活性ガス空間に置換することに
よりそこをファイバースコープ又はCCDカメラにより詳
細にかつ効率よく観察することができる。また、仕切板
上端には小孔が設けられているため、検査終了後に不活
性ガスの供給を停止すればガス空間からのガス流出によ
って不活性ガス空間を消滅させ、容易に運転状態に復帰
することができる。[Effects of the Invention] According to the present invention, a partition plate for forming an inert gas space inside a reactor vessel primary coolant is provided, and an inert gas is provided at a place where a primary pump is installed on a roof slab. Since the supply device and the in-furnace inspection device are installed, the area surrounded by the partition plate should be replaced with an inert gas space to observe it in detail and efficiently with a fiberscope or CCD camera. Can be. In addition, since a small hole is provided at the upper end of the partition plate, if the supply of the inert gas is stopped after the end of the inspection, the inert gas space is extinguished by gas outflow from the gas space, and the operation state is easily returned to the operating state. be able to.
さらに、本発明では原子炉容器内構造物の溶接部のう
ち、バウンダリを形成するか又は炉心を支持する重要溶
接部についてはすべて前記不活性ガス空間に位置するよ
うに板取りしているので、これら重要溶接部をすべて詳
細にかつ効率よく観察することができる。Further, in the present invention, among the welded portions of the reactor vessel internal structure, since the boundary is formed or all the important welded portions supporting the core are plate-cut so as to be located in the inert gas space, All of these important welds can be observed in detail and efficiently.
第1図は本発明に係る高速増殖炉内の検査方法の一実施
例における検査前の状態を示す縦断面図、第2図は第1
図において検査対象となる重要溶接部位を示す縦断面
図、第3図(a)は第1図の状態から一次ポンプを取り
外して炉内検査装置を据付けた状態を示す縦断面図、第
3図(b)は第3図(a)の要部拡大図、第4図(a)
は第3図の状態から検査中の炉内検査装置の作動状態を
示す縦断面図、第4図(b)は第4図(a)の要部拡大
図、第5図は従来の高速増殖炉を示す縦断面図、第6図
は第5図において検査対象となる重要溶接部位を示す縦
断面図である。 1……原子炉容器、3……炉心支持構造物、3c……入口
プレナム、7……下部隔壁、7a……スタンドパイプ、12
……第1の仕切板、12a……第1の小孔、13……第2の
仕切板、13a……第2の小孔、14……第3の仕切板、14a
……第3の小孔、15……炉内検査装置、15a……支持
脚、15b……多関節構造、16……不活性ガス空間。FIG. 1 is a longitudinal sectional view showing a state before an inspection in an embodiment of an inspection method in a fast breeder reactor according to the present invention, and FIG.
FIG. 3A is a longitudinal sectional view showing an important welding portion to be inspected, and FIG. 3A is a longitudinal sectional view showing a state in which a primary pump is removed from the state shown in FIG. 1 and an in-furnace inspection apparatus is installed, FIG. (B) is an enlarged view of a main part of FIG. 3 (a), and FIG. 4 (a)
3 is a longitudinal sectional view showing the operating state of the furnace inspection apparatus during the inspection from the state of FIG. 3, FIG. 4 (b) is an enlarged view of a main part of FIG. 4 (a), and FIG. FIG. 6 is a longitudinal sectional view showing a furnace, and FIG. 6 is a longitudinal sectional view showing an important welding portion to be inspected in FIG. 1 ... Reactor vessel, 3 ... Core support structure, 3c ... Inlet plenum, 7 ... Bottom bulkhead, 7a ... Stand pipe, 12
... First partition plate, 12a First small hole, 13 Second partition plate, 13a Second small hole, 14 Third partition plate, 14a
... third small hole, 15 ... furnace inspection device, 15a ... support leg, 15b ... articulated structure, 16 ... inert gas space.
───────────────────────────────────────────────────── フロントページの続き (58)調査した分野(Int.Cl.6,DB名) G21C 17/00 G21C 1/00 G21C 13/00 G21C 17/08 G21C 15/02 G21C 19/02 ──────────────────────────────────────────────────続 き Continued on the front page (58) Fields investigated (Int. Cl. 6 , DB name) G21C 17/00 G21C 1/00 G21C 13/00 G21C 17/08 G21C 15/02 G21C 19/02
Claims (1)
れた炉心を支持する炉心支持構造物と、前記炉心内に制
御棒を挿入する制御棒駆動機構と、前記原子炉容器の上
部を覆う蓋と、この蓋に支持されて前記制御棒駆動機構
を支持する炉心上部機構と、前記原子炉容器内の冷却材
を強制循環させる循環部が前記蓋内を貫通し上部が前記
蓋に固定して設置された一次ポンプとからなる高速増殖
炉内の検査方法において、前記一次ポンプを取り外して
その一次ポンプの設置位置に炉内検査装置を設置し、前
記原子炉容器内に配設された原子炉内構造物の溶接部近
傍に不活性ガスを貯留しかつ上部に不活性ガス空間消滅
用小孔を有する仕切板を設置して不活性ガス空間を形成
し、この不活性ガス空間に前記炉内検査装置に設けた監
視カメラを挿入して前記溶接部近傍を監視し健全性を検
査するとともに、検査後に前記小孔から前記不活性ガス
空間内に充満した不活性ガスを外部に流出して前記不活
性ガス空間を消滅させた後、前記炉内検査装置を引抜
き、この引抜き個所に前記一次ポンプを戻すことを特徴
とする高速増殖炉内の検査方法。1. A reactor vessel, a core supporting structure for supporting a core disposed in the reactor vessel, a control rod driving mechanism for inserting a control rod into the core, A lid covering the upper part, a core upper mechanism supported by the lid to support the control rod drive mechanism, and a circulating unit for forcibly circulating the coolant in the reactor vessel penetrates through the lid and the upper part is the lid. In a method for inspecting a fast breeder reactor comprising a primary pump fixed and installed in a reactor, the primary pump is removed, an in-core inspection device is installed at the installation position of the primary pump, and the primary pump is disposed in the reactor vessel. Inert gas is stored in the vicinity of the welded portion of the reactor internal structure, and a partition plate having an inert gas space extinguishing hole is installed on the upper portion to form an inert gas space. Into the monitoring camera provided in the furnace inspection device After monitoring the vicinity of the welded portion and inspecting the soundness, after the inspection, the inert gas filled in the inert gas space is discharged from the small hole to the outside and the inert gas space is extinguished. A method for inspecting the inside of a fast breeder reactor, wherein the in-furnace inspection apparatus is withdrawn and the primary pump is returned to the withdrawn point.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP2201151A JP2965635B2 (en) | 1990-07-31 | 1990-07-31 | Inspection method in fast breeder reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP2201151A JP2965635B2 (en) | 1990-07-31 | 1990-07-31 | Inspection method in fast breeder reactor |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPH0486595A JPH0486595A (en) | 1992-03-19 |
| JP2965635B2 true JP2965635B2 (en) | 1999-10-18 |
Family
ID=16436234
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP2201151A Expired - Lifetime JP2965635B2 (en) | 1990-07-31 | 1990-07-31 | Inspection method in fast breeder reactor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JP2965635B2 (en) |
-
1990
- 1990-07-31 JP JP2201151A patent/JP2965635B2/en not_active Expired - Lifetime
Also Published As
| Publication number | Publication date |
|---|---|
| JPH0486595A (en) | 1992-03-19 |
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