JPH0262840B2 - - Google Patents
Info
- Publication number
- JPH0262840B2 JPH0262840B2 JP58009823A JP982383A JPH0262840B2 JP H0262840 B2 JPH0262840 B2 JP H0262840B2 JP 58009823 A JP58009823 A JP 58009823A JP 982383 A JP982383 A JP 982383A JP H0262840 B2 JPH0262840 B2 JP H0262840B2
- Authority
- JP
- Japan
- Prior art keywords
- carbon dioxide
- dioxide gas
- pipe
- iron water
- support flange
- 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
- CURLTUGMZLYLDI-UHFFFAOYSA-N Carbon dioxide Chemical compound O=C=O CURLTUGMZLYLDI-UHFFFAOYSA-N 0.000 claims description 68
- 229910002092 carbon dioxide Inorganic materials 0.000 claims description 34
- 239000001569 carbon dioxide Substances 0.000 claims description 34
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 19
- 235000006506 Brasenia schreberi Nutrition 0.000 claims description 14
- 244000267222 Brasenia schreberi Species 0.000 claims description 14
- 238000000034 method Methods 0.000 claims description 5
- 229910000831 Steel Inorganic materials 0.000 claims description 4
- 239000010959 steel Substances 0.000 claims description 4
- CWYNVVGOOAEACU-UHFFFAOYSA-N Fe2+ Chemical compound [Fe+2] CWYNVVGOOAEACU-UHFFFAOYSA-N 0.000 claims 4
- XEEYBQQBJWHFJM-UHFFFAOYSA-N Iron Chemical compound [Fe] XEEYBQQBJWHFJM-UHFFFAOYSA-N 0.000 description 52
- 229910052742 iron Inorganic materials 0.000 description 26
- 238000012423 maintenance Methods 0.000 description 7
- 238000010586 diagram Methods 0.000 description 3
- 238000004891 communication Methods 0.000 description 2
- 230000000903 blocking effect Effects 0.000 description 1
- 238000007796 conventional method Methods 0.000 description 1
- 239000000498 cooling water Substances 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000009434 installation Methods 0.000 description 1
- 239000002184 metal Substances 0.000 description 1
- 229910052751 metal Inorganic materials 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
-
- 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
- Rigid Pipes And Flexible Pipes (AREA)
- Pipeline Systems (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Description
【発明の詳細な説明】
〔発明の利用分野〕
本発明は、配管の引廻し構造に係り、特に密集
した配管群内の狭空間における保守、補修作業ス
ペースを確保するのに好適な配管引廻し方法に係
る。[Detailed Description of the Invention] [Field of Application of the Invention] The present invention relates to a piping routing structure, and particularly to a piping routing structure suitable for securing maintenance and repair work space in a narrow space within a group of densely packed pipes. Regarding the method.
従来の炭酸ガス配管に対する引廻し方法は、第
1図及び第2図に示す方式が採用されている。こ
こで、第1図は、原子炉本体を真上から見た図で
あり、第2図は正面から見た図である。
As a conventional method for routing carbon dioxide gas piping, the system shown in FIGS. 1 and 2 is adopted. Here, FIG. 1 is a view of the reactor body viewed from directly above, and FIG. 2 is a view of the reactor body viewed from the front.
炭酸ガス入口管1は第1図及び第2図のA部に
示されるように、制御系配管2をさけるようにし
て鉄水スリーブ3群内を引廻され、さらに分配管
4により、炭酸ガスを供給するようになつてい
る。 As shown in part A of FIGS. 1 and 2, the carbon dioxide gas inlet pipe 1 is routed through a group of iron water sleeves 3, avoiding the control system piping 2, and is further routed through a distribution pipe 4 to supply carbon dioxide gas. It has become possible to supply
ここで、炭酸ガス入口管1が支持フランジ5よ
り上にあり、またA部に見られるように炭酸ガス
入口管1が支持フランジ5の上方に重なつている
ため、支持ボルト6を取り外す作業等において支
持フランジ5への接近が困難であるため、炭酸ガ
スシール部8の保守、補修が困難であつた。 Here, since the carbon dioxide gas inlet pipe 1 is above the support flange 5, and as seen in part A, the carbon dioxide gas inlet pipe 1 overlaps above the support flange 5, the work of removing the support bolts 6, etc. Since it is difficult to access the support flange 5, maintenance and repair of the carbon dioxide seal portion 8 is difficult.
本発明の目的は炭酸ガスシール部の保守、補修
時における圧力管支持フランジ部付近への接近性
の向上をはかり得る炭酸ガス引廻し方法を提供す
ることにある。
SUMMARY OF THE INVENTION An object of the present invention is to provide a carbon dioxide gas routing method that can improve accessibility to the vicinity of the pressure pipe support flange portion during maintenance and repair of the carbon dioxide gas seal portion.
支持フランジ部への接近性を向上させるために
は、炭酸ガス配管を支持フランジ部より下方に配
置する必要がある。
In order to improve the accessibility to the support flange, it is necessary to arrange the carbon dioxide pipe below the support flange.
このため、炭酸ガス配管を支持フランジと鉄水
遮へい体の間の鉄水スリーブ間で引き廻す構造と
した。 For this reason, a structure was adopted in which the carbon dioxide gas piping was routed between the iron water sleeve between the support flange and the iron water shield.
以下、本発明の一実施例を第3図〜第8図で説
明する。
An embodiment of the present invention will be described below with reference to FIGS. 3 to 8.
第3図は、圧力管型原子炉本体構造を示してお
り、圧力管7及び鉄水スリーブ3、上部鉄水遮へ
い体9、下部鉄水遮へい体10、カランドリアタ
ンク11、側部鉄水遮へい体12ならびにコンク
リート13より構成されている。ここで、第3図
を真上から見た図が第4図である。 Figure 3 shows the structure of the pressure tube type nuclear reactor body, which includes a pressure pipe 7, a steel water sleeve 3, an upper iron water shield 9, a lower iron water shield 10, a calandria tank 11, and a side iron water shield. It is composed of a body 12 and concrete 13. Here, FIG. 4 is a view of FIG. 3 viewed from directly above.
炭酸ガスは炭酸ガスタンク15より炭酸ガス分
配管14を通つて各炭酸ガス配管1に分配され
る。炭酸ガス配管1は数本の鉄水スリーブを1グ
ループとして一直線上に連通している。 Carbon dioxide gas is distributed from a carbon dioxide tank 15 to each carbon dioxide gas pipe 1 through a carbon dioxide gas distribution pipe 14. The carbon dioxide gas pipe 1 connects several iron water sleeves as one group in a straight line.
炭酸ガスは2つのタンク15を用いて2系統よ
り供給される。第4図のB部の拡大図を第5図及
び側面図を第6図に示す。 Carbon dioxide gas is supplied from two systems using two tanks 15. An enlarged view of section B in FIG. 4 is shown in FIG. 5, and a side view is shown in FIG. 6.
炭酸ガス配管1は支持フランジ5(上限位置)
と下部鉄水遮へい体9(下限位置)との間の鉄水
スリーブ内を貫通している。ここで、炭酸ガスは
炭酸ガス配管1を通つて、圧力管7と鉄水スリー
ブ3との間隙内に供給され、圧力管7の中を流れ
る高温一次冷却水からの熱を遮断している。 Carbon dioxide pipe 1 has support flange 5 (upper limit position)
and the lower iron water shield 9 (lower limit position). Here, carbon dioxide gas is supplied through the carbon dioxide pipe 1 into the gap between the pressure pipe 7 and the iron water sleeve 3, thereby blocking heat from the high temperature primary cooling water flowing inside the pressure pipe 7.
これにより、支持フランジ5より上方に配管が
無くなつたため、支持フランジ5に容易に接近し
て支持ボルト6及び支持フランジ5を取り外し
て、炭酸ガスシール部8の保守、補修をすること
ができ、また万が一の場合の圧力管7の保守、補
修作業も容易となる。 As a result, since there is no piping above the support flange 5, it is possible to easily access the support flange 5, remove the support bolts 6 and the support flange 5, and perform maintenance and repair of the carbon dioxide seal part 8. In addition, maintenance and repair work on the pressure pipe 7 in case of emergency becomes easier.
一方、第1図及び第2図で示したような従来の
炭酸ガス引廻し構造をそのまま下方に平行移動し
た鉄水スリーブ3の位置に設置することは、支持
フランジ5の間隔が狭まく、また制御系配管2の
干渉を受けるため不可能である。 On the other hand, if the conventional carbon dioxide gas distribution structure as shown in FIGS. 1 and 2 is installed in the position of the iron water sleeve 3 that has been moved downward in parallel, the spacing between the support flanges 5 will become narrower. This is not possible due to interference from the control system piping 2.
このため、支持フランジ5と上部鉄水遮へい体
9との間の鉄水スリーブ3内に炭酸ガス配管を引
き廻すには、本発明のように、一本の配管による
連通構造としなければならない。また、一本の配
管により、炭酸ガスを供給できることにより、配
管の本数が減り、保守、補修作業スペースを増大
させることができる。 Therefore, in order to route the carbon dioxide gas pipe within the iron water sleeve 3 between the support flange 5 and the upper iron water shield 9, it is necessary to have a communication structure using one pipe as in the present invention. Furthermore, since carbon dioxide gas can be supplied through a single pipe, the number of pipes can be reduced, and the space for maintenance and repair work can be increased.
次に、上部鉄水遮へい体9を配管引き廻しの下
限位置とする理由を図7で説明する。 Next, the reason why the upper iron water shielding body 9 is set at the lower limit position of piping routing will be explained with reference to FIG.
第7図は、原子炉本体を構成する各構造物の現
地における据付け手順を示しており、はじめに、
コンクリート13の上に下部鉄水遮へい体10を
設置し、次にカランドリアタンク11、側部鉄水
遮へい体12、上部鉄水遮へい体9の順で据付
け、さらに鉄水スリーブ3及び鉄水スリーブ3を
差し込んだ後、炭酸ガス配管1を取り付ける。こ
のような現地作業工程において、炭酸ガス配管1
を上部鉄水遮へい体9の間のすきま16の中を引
き廻して鉄水スリーブ3に取り付けることは不可
能である。 Figure 7 shows the on-site installation procedure for each structure that makes up the reactor body.
The lower iron water shield 10 is installed on the concrete 13, then the calandria tank 11, the side iron water shield 12, and the upper iron water shield 9 are installed in this order, and then the iron water sleeve 3 and iron water sleeve are installed. After inserting 3, attach the carbon dioxide pipe 1. In such on-site work process, carbon dioxide piping 1
It is impossible to attach the metal water shield to the iron water sleeve 3 by routing it through the gap 16 between the upper iron water shields 9.
このことからも、本発明で示すように、支持フ
ランジ5を上限位置とし、上部鉄水遮へい体9を
下限位置として、鉄水スリーブ5に炭酸ガス配管
1を取り付けるのが最適である。 For this reason, as shown in the present invention, it is optimal to attach the carbon dioxide pipe 1 to the iron water sleeve 5 with the support flange 5 at the upper limit position and the upper iron water shield 9 at the lower limit position.
また、原子炉本体下部の鉄水スリーブにも同様
の炭酸ガス引廻し配管を設置する。 Similar carbon dioxide gas piping will also be installed in the iron water sleeve at the bottom of the reactor body.
本発明によれば、鉄水スリーブ複数本を1グル
ープとして、1本の炭酸ガス配管により鉄水スリ
ーブ群内を引廻す連通間構造にしたことにより、
支持フランジへの接近性の向上により、炭酸ガス
シール部の保守補修性が向上し、ひいては作業空
間の増加により、作業時間が短縮し、作業者の被
曝量の低減がはかられる効果がある。
According to the present invention, by creating a communication structure in which a plurality of iron water sleeves are grouped into one group and the inside of the iron water sleeve group is routed through one carbon dioxide pipe,
The improved accessibility to the support flange improves the ease of maintenance and repair of the carbon dioxide gas seal, and the increased work space shortens working time and reduces the amount of radiation exposure for workers.
第1図は従来の炭酸ガス引廻し構造図、第2図
は第2図の正面図、第3図は圧力管型原子炉本体
構造図、第4図は第3図の平面図、第5図は第4
図のB部拡大図、第6図は第4図のB部正面図、
第7図は原子炉本体据付手順図である。
1…炭酸ガス配管、2…制御系配管、3…鉄水
スリーブ、5…支持フランジ、6…支持ボルト、
7…圧力管、9…上部鉄水遮へい体。
Figure 1 is a structural diagram of the conventional carbon dioxide gas circulation, Figure 2 is a front view of Figure 2, Figure 3 is a structural diagram of the pressure tube reactor main body, Figure 4 is a plan view of Figure 3, Figure 5 The figure is number 4
An enlarged view of part B in the figure, Figure 6 is a front view of part B in Figure 4,
FIG. 7 is a diagram showing the procedure for installing the reactor main body. 1... Carbon dioxide gas piping, 2... Control system piping, 3... Steel water sleeve, 5... Support flange, 6... Support bolt,
7...Pressure pipe, 9...Upper iron water shield.
Claims (1)
おいて、両者の間の間隙に熱遮へい用炭酸ガスを
供給する炭酸ガス配管及び鉄水スリーブの上部に
接続される支持フランジより構成され、鉄水スリ
ーブ複数本を1グループとして、各グループ内の
鉄水スリーブ間を、上限位置である支持フランジ
と下限位置である鉄水遮へい体との間で管路によ
り順次連結して、鉄水スリーブ群内を引廻す連通
管構造を特徴とする炭酸ガス配管引廻し方法。1 In a double pipe structure consisting of a pressure pipe and a steel water sleeve, it consists of a carbon dioxide pipe that supplies carbon dioxide gas for heat shielding into the gap between the two, and a support flange connected to the top of the steel water sleeve. A plurality of sleeves are considered as one group, and the ferrous sleeves in each group are sequentially connected by pipes between the support flange at the upper limit position and the ferrous water shield at the lower limit position, and the ferrous water sleeves within the ferrous sleeve group are A method for routing carbon dioxide gas piping, which features a communicating pipe structure for routing.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP58009823A JPS59136690A (en) | 1983-01-26 | 1983-01-26 | Method of drawing around carbonic acid gas pipe |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP58009823A JPS59136690A (en) | 1983-01-26 | 1983-01-26 | Method of drawing around carbonic acid gas pipe |
Publications (2)
Publication Number | Publication Date |
---|---|
JPS59136690A JPS59136690A (en) | 1984-08-06 |
JPH0262840B2 true JPH0262840B2 (en) | 1990-12-26 |
Family
ID=11730855
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP58009823A Granted JPS59136690A (en) | 1983-01-26 | 1983-01-26 | Method of drawing around carbonic acid gas pipe |
Country Status (1)
Country | Link |
---|---|
JP (1) | JPS59136690A (en) |
-
1983
- 1983-01-26 JP JP58009823A patent/JPS59136690A/en active Granted
Also Published As
Publication number | Publication date |
---|---|
JPS59136690A (en) | 1984-08-06 |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
JPS6038505A (en) | Steam generator | |
WO1995015565A1 (en) | Neutral shielding for reactor vessel | |
US3893886A (en) | Removable diagrid for supporting the fuel assemblies of a nuclear reactor | |
US4101377A (en) | Fast neutron reactor | |
FI73333B (en) | ARRANGEMANG FOER UPPBAERANDE AV AONGUTSLAEPPNINGSVENTILER VID ETT KAERNKRAFTVERK. | |
US4093513A (en) | Water moderated reactor | |
US4148281A (en) | Steam generator and pressurized-water nuclear reactors | |
JPH0262840B2 (en) | ||
CN105625754B (en) | A kind of HTGR Nuclear Power Plant steam generator partition module | |
US5960602A (en) | Shielded metallic reflective insulation assembly | |
JP4301604B2 (en) | Pressurized water reactor | |
US4737338A (en) | Nuclear reactor containing connecting means for connecting a reactor vessel and at least one receiver vessel | |
JP2023517207A (en) | Molten-salt fast reactor | |
JPH08105990A (en) | Installation method for structure in nuclear reactor, nuclear reactor shroud welder therefor, and nuclear reactor combination shroud hanger and core measuring device therefore | |
US3638684A (en) | Method of repairing tube structures | |
JP3425217B2 (en) | Sealing device for repairing pressure vessel penetration housing | |
JP2000137089A (en) | Core structure of pressurized water reactor | |
JPH0713662B2 (en) | Small liquid metal cooled fast reactor | |
JPH0220960B2 (en) | ||
JP2613637B2 (en) | Nuclear power plant | |
JPH02228593A (en) | Installation of equipment structure in nuclear reactor | |
JPS60108792A (en) | Spraying pipe of container for nuclear reactor | |
JPH10260290A (en) | Method and apparatus for replacing structure in reactor pressure vessel | |
Branchu et al. | Superphenix 1 reactor block fabrication | |
JP2544409B2 (en) | Reactor pressure tube support structure |