JPS6341437B2 - - Google Patents
Info
- Publication number
- JPS6341437B2 JPS6341437B2 JP56034587A JP3458781A JPS6341437B2 JP S6341437 B2 JPS6341437 B2 JP S6341437B2 JP 56034587 A JP56034587 A JP 56034587A JP 3458781 A JP3458781 A JP 3458781A JP S6341437 B2 JPS6341437 B2 JP S6341437B2
- Authority
- JP
- Japan
- Prior art keywords
- water
- main steam
- pressure vessel
- reactor
- reactor pressure
- 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
Links
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 44
- 230000002285 radioactive effect Effects 0.000 claims description 17
- 238000005260 corrosion Methods 0.000 claims description 16
- 230000007797 corrosion Effects 0.000 claims description 16
- 238000000034 method Methods 0.000 claims description 11
- 239000000446 fuel Substances 0.000 claims description 5
- 238000002347 injection Methods 0.000 claims description 2
- 239000007924 injection Substances 0.000 claims description 2
- 238000002955 isolation Methods 0.000 description 6
- 239000003758 nuclear fuel Substances 0.000 description 5
- 238000007689 inspection Methods 0.000 description 3
- 238000009835 boiling Methods 0.000 description 2
- 238000011109 contamination Methods 0.000 description 2
- 238000009792 diffusion process Methods 0.000 description 2
- 230000005855 radiation Effects 0.000 description 2
- 230000000712 assembly Effects 0.000 description 1
- 238000000429 assembly Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 230000000737 periodic effect Effects 0.000 description 1
- 238000010248 power generation Methods 0.000 description 1
- 230000001105 regulatory effect Effects 0.000 description 1
- 239000008400 supply water Substances 0.000 description 1
- 238000013022 venting Methods 0.000 description 1
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
Landscapes
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Description
【発明の詳細な説明】
本発明は、沸騰水型原子炉における燃料交換時
の原子炉設備の水張り方法に関する。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a method for filling reactor equipment with water during refueling in a boiling water nuclear reactor.
発電用沸騰水型原子炉設備は一般に、原子炉圧
力容器（RPV）と、この圧力容器に接続された
複数本の主蒸気配管（MS）および主蒸気隔離弁
（MSIV）ならびにその他の諸設備からなる。原
子炉運転中、原子炉圧力容器内の水位は、前記主
蒸気管が原子炉圧力容器に接続されている蒸気が
流出するノズル部より低い位置に保たれて運転さ
れ、主蒸気管には通常、蒸気のみが流れるように
なつている。このため、原子炉圧力容器内の下
部、すなわち、水層部は、炉水中に存在する放射
性腐蝕生成物が堆積されており、炉壁内面にも前
記放射性腐蝕生成物が付着している。また、原子
炉圧力容器内上部および主蒸気管内、つまり蒸気
層部は蒸気内に放射性腐蝕生成物がほとんど存在
していないため放射性腐蝕生成物の付着が水層部
よりはるかに少ない。 Boiling water reactor equipment for power generation generally consists of a reactor pressure vessel (RPV), multiple main steam pipes (MS) and main steam isolation valves (MSIV), and other equipment connected to the reactor pressure vessel (RPV). Become. During reactor operation, the water level in the reactor pressure vessel is maintained at a level lower than the nozzle section from which steam flows out, where the main steam pipe is connected to the reactor pressure vessel. , so that only steam can flow. Therefore, the radioactive corrosion products present in the reactor water are deposited in the lower part of the reactor pressure vessel, that is, the water layer, and the radioactive corrosion products also adhere to the inner surface of the reactor wall. In addition, in the upper part of the reactor pressure vessel and in the main steam pipe, that is, in the steam layer, there are almost no radioactive corrosion products in the steam, so the adhesion of radioactive corrosion products is much less than in the water layer.
ところで、原子炉圧力容器内の核燃料集合体を
交換する時には、原子炉圧力容器の上蓋を開放
し、炉内上部構造物を取り去つてから、核燃料集
合体の放射能を遮蔽するため原子炉圧力容器内と
その上方に水を満たす。つまり水張りする必要が
ある。通常、この水張り方法は原子炉圧力容器に
接続された各種配管から水を注入することによつ
てなされる。しかしながら、この方法は前に述べ
た放射性腐蝕生成物を含んだ炉水が主蒸気管内に
流入し、主蒸気管内が放射能汚染を来たし、その
周辺放射線線量率を上昇させるような事態になる
欠点がある。また、主蒸気管の各位置に取付けら
れた主蒸気逃し安全弁や、主蒸気隔離弁のような
高度の信頼性を要求される各弁に、前記放射性腐
蝕生成物が付着すると、各弁に機械的損傷を与え
たり、その分解点検時には周辺環境に放射性腐蝕
生成物を拡散される欠点がある。 By the way, when replacing the nuclear fuel assembly in the reactor pressure vessel, the upper cover of the reactor pressure vessel is opened and the upper structure inside the reactor is removed. Fill the container with water. That means you need to fill it with water. Normally, this water filling method is performed by injecting water from various pipes connected to the reactor pressure vessel. However, this method has the disadvantage that reactor water containing the radioactive corrosion products mentioned above flows into the main steam pipe, causing radioactive contamination within the main steam pipe and increasing the radiation dose rate in the surrounding area. There is. In addition, if the radioactive corrosion products adhere to valves that require a high degree of reliability, such as main steam relief safety valves and main steam isolation valves installed at various positions in the main steam pipe, mechanical damage to each valve may occur. They have the drawback of causing physical damage and dispersing radioactive corrosion products into the surrounding environment during overhaul.
本発明は上記欠点を除去するためになされたも
ので、原子炉系諸設備点検時の被曝低減および、
主蒸気管各部に取付けられた各種弁類分解時の放
射線腐蝕生成物拡散を有効に防止し得る燃料交換
時の原子炉設備の水張りの方法を提供することに
ある。 The present invention was made to eliminate the above-mentioned drawbacks, and it reduces radiation exposure during inspection of various nuclear reactor equipment, and
It is an object of the present invention to provide a method for filling nuclear reactor equipment with water during refueling, which can effectively prevent the diffusion of radiation corrosion products during disassembly of various valves attached to various parts of the main steam pipe.
すなわち、本発明は原子炉圧力容器に接続され
た主蒸気配管を有する原子炉設備で、燃料交換時
に前記原子炉圧力容器内に水張りするにあたり、
あらかじめ前記主蒸気配管に接続された小径配管
から放射性腐蝕生成物を含まない水である純水を
注入して該主蒸気配管内を満水したのち、該原子
炉圧力容器内に水を注入することを特徴とする燃
料交換時の原子炉設備の水張り方法である。 That is, the present invention is a nuclear reactor equipment having a main steam pipe connected to a reactor pressure vessel, and when filling the reactor pressure vessel with water during fuel exchange,
Injecting pure water, which is water that does not contain radioactive corrosion products, from a small-diameter pipe connected to the main steam pipe in advance to fill the main steam pipe with water, and then injecting water into the reactor pressure vessel. This is a method of filling nuclear reactor equipment with water during fuel exchange, which is characterized by:
以下図面を参照して、本発明に係る水張り方法
の一実施例を説明する。 An embodiment of the water filling method according to the present invention will be described below with reference to the drawings.
図において符号１は、原子炉圧力容器で、この
原子炉圧力容器１は半球状の底部１ａと同じく、
半球状の上蓋２で気密に閉塞され、上蓋２と原子
炉圧力容器１は、複数本のボルト１０により結合
されて１体化される。原子炉圧力容器１内には、
上下位置においてほぼ中央部に炉心を構成する核
燃料集合体８が多数配列され、その炉心の上方に
炉内上部構造物９が収納されている。主蒸気管３
は主蒸気ノズル４に連通して、原子炉容器１の比
較的上部に位置して接続されている。主蒸気管３
には主蒸気隔離弁５および主蒸気逃し安全弁６を
それぞれ接続している。 In the figure, reference numeral 1 indicates a reactor pressure vessel, and this reactor pressure vessel 1 has a hemispherical bottom portion 1a as well as
The upper lid 2 is airtightly closed with a hemispherical upper lid 2, and the upper lid 2 and the reactor pressure vessel 1 are connected by a plurality of bolts 10 to be integrated. Inside the reactor pressure vessel 1,
A large number of nuclear fuel assemblies 8 constituting a reactor core are arranged approximately in the center in vertical positions, and an in-core upper structure 9 is housed above the reactor core. Main steam pipe 3
is connected to the main steam nozzle 4 at a relatively upper portion of the reactor vessel 1 . Main steam pipe 3
A main steam isolation valve 5 and a main steam relief safety valve 6 are connected to the main steam isolation valve 5 and the main steam relief safety valve 6, respectively.
また、原子炉圧力容器１内には炉水７が収納さ
れ、原子炉運転中その炉水７の水面は、前記主蒸
気ノズル４より数ｍ下方に保たれている。尚、図
中１１は、原子炉圧力容器の空気抜きに設けられ
たベント配管で、その１端は上蓋２のフランジ２
ａに他端は主蒸気管３から導出された小径配管１
４のフランジ１２に接続されている。また１３は
各種の他系統配管である。 Further, reactor water 7 is stored in the reactor pressure vessel 1, and the water surface of the reactor water 7 is maintained several meters below the main steam nozzle 4 during reactor operation. In addition, 11 in the figure is a vent pipe provided for air venting of the reactor pressure vessel, one end of which is connected to the flange 2 of the upper cover 2.
The other end of a is a small diameter pipe 1 led out from the main steam pipe 3.
It is connected to the flange 12 of No. 4. Moreover, 13 is various other system piping.
つぎに、以上の構成を有する原子炉設備におい
て、本発明に係る水張り方法を説明する。まず、
原子炉圧力容器１の上蓋２を取り去るためその上
部に位置するベント配管１１を取り去る。この配
管１１は、通常両端に設けられたフランジ２ａ，
１２をボルトにより結合されているので、そのボ
ルトを外すことによつて容易に取外せるものであ
る。 Next, a water filling method according to the present invention will be described in a nuclear reactor facility having the above configuration. first,
In order to remove the upper cover 2 of the reactor pressure vessel 1, the vent pipe 11 located above it is removed. This piping 11 usually has flanges 2a provided at both ends,
12 are connected by bolts, and can be easily removed by removing the bolts.
つぎに、原子炉圧力容器１と上蓋２とを結合し
ているボルト１０を緩め、上蓋２を取り去る。つ
いで、主蒸気管３から導出した小径配管１４に接
続されたフランジ１２に、注水用の仮設配管を接
続し、この仮設配管を通流させて主蒸気管３内に
放射性腐蝕生成物を含まない水である純水を注入
する。主蒸気管３内に水が満たされ原子炉圧力容
器１内へ純水が逆流したら、他系統１３により、
炉水位を上昇させ、同時に高放射能の炉内上部構
造物７を取り出し原子炉圧力容器１への水張りが
完了したのち、核燃料集合体８の取り出し、作業
に移る。なお、核燃料集合体８の取出し作業中、
継続して前記仮設配管から放射性腐蝕生成物を含
まない水である純水を注入することにより、炉内
の有害な放射性腐蝕生成物は、主蒸気３内へ混入
されることがない。ここで、仮設配管は補給水系
（MUW）配管に接続されて給水される。 Next, the bolts 10 connecting the reactor pressure vessel 1 and the upper cover 2 are loosened, and the upper cover 2 is removed. Next, a temporary pipe for water injection is connected to the flange 12 connected to the small-diameter pipe 14 led out from the main steam pipe 3, and water is allowed to flow through the temporary pipe to ensure that no radioactive corrosion products are contained in the main steam pipe 3. Inject pure water. When the main steam pipe 3 is filled with water and pure water flows back into the reactor pressure vessel 1, the other system 13
After the reactor water level is raised and at the same time the highly radioactive reactor upper structure 7 is removed and the reactor pressure vessel 1 is filled with water, the nuclear fuel assembly 8 is removed and the work begins. In addition, during the removal work of the nuclear fuel assembly 8,
By continuously injecting pure water that does not contain radioactive corrosion products from the temporary piping, harmful radioactive corrosion products in the furnace are not mixed into the main steam 3. Here, the temporary piping is connected to the make-up water system (MUW) piping to supply water.
以上説明のように、本発明によれば、簡単な操
作で主蒸気管内へ放射性腐蝕生成物を流入させる
ことなく原子炉圧力容器内の燃料交換作業を実施
することができる。従つて、主蒸気配管系配管の
内面汚染を防止でき、もつて原子炉設備の定期検
査時の被曝低減に寄与し、また主蒸気系の主蒸気
隔離弁、主蒸気止め弁、主蒸気逃し安全弁、調圧
弁などの各弁の点検作業性を改善でき、さらに所
内用水系への放射性腐蝕生成物拡散を有効に防止
できる効果がある。 As described above, according to the present invention, it is possible to carry out fuel exchange work in the reactor pressure vessel with a simple operation without causing radioactive corrosion products to flow into the main steam pipe. Therefore, it is possible to prevent internal contamination of the main steam piping system piping, thereby contributing to the reduction of radiation exposure during periodic inspections of nuclear reactor equipment, and also to prevent the main steam isolation valve, main steam stop valve, and main steam relief safety valve of the main steam system. , it is possible to improve the inspection workability of each valve such as a pressure regulating valve, and furthermore, it has the effect of effectively preventing the diffusion of radioactive corrosion products into the internal water system.
図は、本発明に係る水張り方法の一実施例を説
明するための原子炉設備を示す縦断面図である。
１…原子炉圧力容器、２…原子炉圧力容器上
蓋、３…主蒸気管、４…主蒸気ノズル、５…主蒸
気隔離弁、６…主蒸気逃し安全弁、７…炉水、８
…核燃料集合体、９…炉内上部構造物、１０…ボ
ルト、１１…ベント配管、１２…フランジ、１３
…各種の他系統配管、１４…小径配管。
The figure is a longitudinal sectional view showing nuclear reactor equipment for explaining an embodiment of the water filling method according to the present invention. 1...Reactor pressure vessel, 2...Reactor pressure vessel upper cover, 3...Main steam pipe, 4...Main steam nozzle, 5...Main steam isolation valve, 6...Main steam relief safety valve, 7...Reactor water, 8
...Nuclear fuel assembly, 9...Inner reactor upper structure, 10...Bolt, 11...Vent piping, 12...Flange, 13
...Various other system piping, 14...Small diameter piping.
Claims (1)
する原子炉設備で、燃料交換時に前記原子炉圧力
容器内に水張りするにあたり、あらかじめ前記主
蒸気配管内を放射性腐食生成物を含まない水で満
水にしたのち該原子炉圧力容器内に水を注入する
ことを特徴とする燃料交換時の原子炉設備の水張
り方法。 ２ 前記主蒸気配管内を満水にさせる放射性腐食
生成物を含まない水は主蒸気配管から導出した小
径配管に接続された注水用の仮設配管を介して注
入されて成ることを特徴とする特許請求の範囲第
１項記載の燃料交換時の原子炉設備の水張り方
法。[Claims] 1. In nuclear reactor equipment having a main steam pipe connected to a reactor pressure vessel, when filling the reactor pressure vessel with water during fuel exchange, the main steam pipe is preliminarily filled with radioactive corrosion products. A method for filling nuclear reactor equipment with water during refueling, the method comprising filling the reactor pressure vessel with water that does not contain water and then injecting water into the reactor pressure vessel. 2. A patent claim characterized in that the water that does not contain radioactive corrosion products and fills the inside of the main steam pipe is injected through a temporary pipe for water injection connected to a small-diameter pipe led out from the main steam pipe. A method for filling nuclear reactor equipment with water during fuel exchange as described in item 1.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP56034587A JPS57149993A (en) | 1981-03-12 | 1981-03-12 | Method of filling nuclear reactor facility with water at fuel exchange |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP56034587A JPS57149993A (en) | 1981-03-12 | 1981-03-12 | Method of filling nuclear reactor facility with water at fuel exchange |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS57149993A JPS57149993A (en) | 1982-09-16 |
| JPS6341437B2 true JPS6341437B2 (en) | 1988-08-17 |
Family
ID=12418448
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP56034587A Granted JPS57149993A (en) | 1981-03-12 | 1981-03-12 | Method of filling nuclear reactor facility with water at fuel exchange |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS57149993A (en) |
-
1981
- 1981-03-12 JP JP56034587A patent/JPS57149993A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS57149993A (en) | 1982-09-16 |
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