JPH0326798B2 - - Google Patents
Info
- Publication number
- JPH0326798B2 JPH0326798B2 JP58179237A JP17923783A JPH0326798B2 JP H0326798 B2 JPH0326798 B2 JP H0326798B2 JP 58179237 A JP58179237 A JP 58179237A JP 17923783 A JP17923783 A JP 17923783A JP H0326798 B2 JPH0326798 B2 JP H0326798B2
- Authority
- JP
- Japan
- Prior art keywords
- reactor vessel
- pressurizer
- dismantling
- support frame
- passage
- 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
- 238000000034 method Methods 0.000 claims description 6
- NJPPVKZQTLUDBO-UHFFFAOYSA-N novaluron Chemical compound C1=C(Cl)C(OC(F)(F)C(OC(F)(F)F)F)=CC=C1NC(=O)NC(=O)C1=C(F)C=CC=C1F NJPPVKZQTLUDBO-UHFFFAOYSA-N 0.000 description 2
- 230000005855 radiation Effects 0.000 description 2
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 2
- 230000000694 effects Effects 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 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
- Working Measures On Existing Buildindgs (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Description
【発明の詳細な説明】
本発明は原子力発電所における原子炉容器の解
体方法に関するものである。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a method for dismantling a nuclear reactor vessel in a nuclear power plant.
加圧水型原子炉の原子炉容器は、ノズル部によ
り支持されているが、原子力発電所の廃止措置に
伴つて原子炉容器を解体するときには、原子炉容
器を底部から別に支持する必要があり、これを行
なう支持架台を原子炉容器の下方へ搬入しなけれ
ばならない。この支持架台の搬入は、炉内計装用
コンジツトチユーブの設置されている通路から行
なうしかないが、この通路は狭くて、支持架台を
組立てた状態で搬入することができず、原子炉容
器の下方で組立てることになるが、原子炉容器の
下方は、高放射線雰囲気下にあり、ここで支持架
台の組立て等を行なうのは、作業員の放射線被曝
量を多くして、好ましくない。 The reactor vessel of a pressurized water reactor is supported by the nozzle part, but when the reactor vessel is dismantled due to decommissioning of a nuclear power plant, it is necessary to separately support the reactor vessel from the bottom. The support frame that performs this must be carried below the reactor vessel. The only way to transport this support frame is through the passageway where the in-core instrumentation conduit tube is installed, but this passageway is narrow and it is not possible to carry the support frame in an assembled state. However, the lower part of the reactor vessel is under a high radiation atmosphere, and it is not preferable to assemble the support frame here because it increases the radiation exposure of the workers.
本発明は前記の問題点に対処するもので、下部
に炉内計装用コンジツトチユーブを通す通路を画
成された円筒状コクリート壁内に原子炉容器が設
置され、前記コンクリート壁の外部に設けられた
前記通路の上方に位置する加圧器室を有する原子
力プラントを解体するに際し、前記加圧器室内の
加圧器を除去し、前記加圧器室の床を除去して、
同加圧器室を前記通路に連絡し、前記炉内計装用
コンジツトチユーブを除去した後、前記加圧器室
と通路とを通つて支持架台を搬入し、前記原子炉
容器の下部に同支持架台を設置して、同原子炉容
器の落下を防止しつつ同原子炉容器の解体をする
ことを特徴とした原子炉容器の解体方法に係り、
その目的とする処は、原子炉容器を解体するとき
の支持架台の組立、据付に伴う作業者の放射線被
曝量を少なくすることができる改良された原子炉
容器の解体方法を供する点にある。 The present invention addresses the above-mentioned problems, in that the reactor vessel is installed within a cylindrical cocrete wall with a passage defined at the bottom for passing a conduit tube for in-core instrumentation, and the reactor vessel is installed outside the concrete wall. When dismantling a nuclear power plant having a pressurizer room located above the passageway, the pressurizer in the pressurizer room is removed, the floor of the pressurizer room is removed,
After connecting the pressurizer chamber to the passageway and removing the in-core instrumentation conduit tube, a support frame is carried in through the pressurizer chamber and the passageway, and the support frame is placed in the lower part of the reactor vessel. Relating to a method for dismantling a reactor vessel, which is characterized in that the reactor vessel is dismantled while preventing the reactor vessel from falling by installing a
The objective is to provide an improved method for dismantling a nuclear reactor vessel that can reduce the amount of radiation exposure of workers involved in assembling and installing a support frame when dismantling the reactor vessel.
次に本発明の原子炉容器の解体方法を図面に示
す実施例により説明すると、第１図は、加圧水型
原子力発電所の廃止措置前の原子炉容器１の周り
の状態を示している。同原子炉容器１の底部から
は、炉内計装用コンジツトチユーブ３が出てお
り、原子炉容器１の下方への接近は、炉内計装用
コンジツトチユーブ３の通路以外からは行なえな
い。同原子炉容器１の解体時は、第２図に示すよ
うに原子炉容器１の下方に、支持架台７を設置す
る必要がある。第１図に示すように炉内計装用コ
ンジツトチユーブ３の通路が狭い場合には、支持
架台７を組立てた状態で、原子炉容器１の下方へ
搬入することができない。ところが本発明は第２
図に示すように、加圧器２と加圧器室天井６と加
圧器室床５と炉内計装用コンジツトチユーブ３の
通路天井部４等とを解体して、原子炉容器１の下
方に通じる搬入通通路を形成し、次いで原子炉容
器解体用支持架台７を同搬入通路を経て原子炉容
器１の下方へ搬入して、原子炉容器１を支持す
る。このことにより、原子炉容器１の下方の高放
射線雰囲気下における原子炉容器解体用支持架台
の組立作業時間を減少させることができて、作業
員の放射線被曝量を低減させることができる効果
がある。 Next, the method for dismantling a reactor vessel of the present invention will be explained with reference to an embodiment shown in the drawings. Fig. 1 shows the state around a reactor vessel 1 before decommissioning of a pressurized water nuclear power plant. An in-core instrumentation conduit tube 3 protrudes from the bottom of the reactor vessel 1, and the lower part of the reactor vessel 1 can only be accessed from the passageway of the in-core instrumentation conduit tube 3. When dismantling the reactor vessel 1, it is necessary to install a support frame 7 below the reactor vessel 1, as shown in FIG. As shown in FIG. 1, if the passage of the in-core instrumentation conduit tube 3 is narrow, it is not possible to carry it into the lower part of the reactor vessel 1 with the support pedestal 7 assembled. However, the present invention
As shown in the figure, the pressurizer 2, the pressurizer chamber ceiling 6, the pressurizer chamber floor 5, the passage ceiling 4 of the in-core instrumentation conduit tube 3, etc. are dismantled to connect the reactor vessel 1 to the lower part. A carry-in passage is formed, and then the reactor vessel dismantling support frame 7 is carried below the reactor vessel 1 through the carry-in passage to support the reactor vessel 1. This has the effect of reducing the time taken to assemble the reactor vessel disassembly support frame in the high radiation atmosphere below the reactor vessel 1, and reducing the amount of radiation exposure of workers. .
以上本発明を実施例について説明したが、勿論
本発明はこのような実施例にだけ局限されるもの
ではなく、本発明の精神を逸脱しない範囲内で
種々の設計の改変を施しうるものである。 Although the present invention has been described above with reference to embodiments, it goes without saying that the present invention is not limited to such embodiments, and that various design modifications can be made without departing from the spirit of the present invention. .
第１図は原子力発電所の廃止措置前の原子炉容
器の周りの状態を示す縦断側面図、第２図は本発
明の原子炉容器の解体方法の一実施例を示す縦断
側面図である。
１……原子炉容器、２……加圧器、３……炉内
計装用コンジツトチユーブ、４……通路天井部、
５……加圧器室床、６……加圧器室天井、７……
支持架台。
FIG. 1 is a longitudinal side view showing the state around a reactor vessel before decommissioning of a nuclear power plant, and FIG. 2 is a longitudinal side view showing an embodiment of the reactor vessel dismantling method of the present invention. 1... Reactor vessel, 2... Pressurizer, 3... Conduit tube for in-reactor instrumentation, 4... Passage ceiling,
5... Pressurizer room floor, 6... Pressurizer room ceiling, 7...
Support pedestal.
Claims (1)
通路を画成された円筒状コンクリート壁内に原子
炉容器が設置され、前記コンクリート壁の外部に
設けられ前記通路の上方に位置する加圧器室を有
する原子力プラントを解体するに際し、前記加圧
器室内の加圧器を除去し、前記加圧器室の床を除
去して、同加圧器室を前記通路に連絡し、前記炉
内計装用コンジツトチユーブを除去した後、前記
加圧器室と通路とを通つて支持架台を搬入し、前
記原子炉容器の下部に同支持架台を設置して、同
原子炉容器の落下を防止しつつ同原子炉容器の解
体をすることを特徴とした原子炉容器の解体方
法。1. A reactor vessel is installed within a cylindrical concrete wall that defines a passage through which an in-reactor instrumentation conduit tube passes through at the bottom, and a pressurizer chamber is provided outside the concrete wall and located above the passage. When dismantling a nuclear power plant having a reactor, the pressurizer in the pressurizer chamber is removed, the floor of the pressurizer chamber is removed, the pressurizer chamber is connected to the passage, and the in-core instrumentation conduit tube is connected. After the removal, a support frame is carried in through the pressurizer room and the passageway, and the support frame is installed at the bottom of the reactor vessel to prevent the reactor vessel from falling and secure the reactor vessel. A method of dismantling a nuclear reactor vessel characterized by dismantling it.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP58179237A JPS6071999A (en) | 1983-09-29 | 1983-09-29 | Method of overhauling reactor vessel in nuclear power plant |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP58179237A JPS6071999A (en) | 1983-09-29 | 1983-09-29 | Method of overhauling reactor vessel in nuclear power plant |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS6071999A JPS6071999A (en) | 1985-04-23 |
| JPH0326798B2 true JPH0326798B2 (en) | 1991-04-11 |
Family
ID=16062336
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP58179237A Granted JPS6071999A (en) | 1983-09-29 | 1983-09-29 | Method of overhauling reactor vessel in nuclear power plant |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS6071999A (en) |
-
1983
- 1983-09-29 JP JP58179237A patent/JPS6071999A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS6071999A (en) | 1985-04-23 |
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