JPH0252238B2 - - Google Patents
Info
- Publication number
- JPH0252238B2 JPH0252238B2 JP60196957A JP19695785A JPH0252238B2 JP H0252238 B2 JPH0252238 B2 JP H0252238B2 JP 60196957 A JP60196957 A JP 60196957A JP 19695785 A JP19695785 A JP 19695785A JP H0252238 B2 JPH0252238 B2 JP H0252238B2
- Authority
- JP
- Japan
- Prior art keywords
- reactor
- vessel
- safety
- roof slab
- 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
- 238000000034 method Methods 0.000 claims description 12
- 238000010276 construction Methods 0.000 claims description 7
- 238000003466 welding Methods 0.000 description 12
- 238000010586 diagram Methods 0.000 description 8
- 238000009659 non-destructive testing Methods 0.000 description 6
- 229910000831 Steel Inorganic materials 0.000 description 4
- 239000010959 steel Substances 0.000 description 4
- DGAQECJNVWCQMB-PUAWFVPOSA-M Ilexoside XXIX Chemical compound C[C@@H]1CC[C@@]2(CC[C@@]3(C(=CC[C@H]4[C@]3(CC[C@@H]5[C@@]4(CC[C@@H](C5(C)C)OS(=O)(=O)[O-])C)C)[C@@H]2[C@]1(C)O)C)C(=O)O[C@H]6[C@@H]([C@H]([C@@H]([C@H](O6)CO)O)O)O.[Na+] DGAQECJNVWCQMB-PUAWFVPOSA-M 0.000 description 3
- 238000001816 cooling Methods 0.000 description 3
- 238000001514 detection method Methods 0.000 description 3
- 230000000694 effects Effects 0.000 description 3
- 238000011900 installation process Methods 0.000 description 3
- 229910052708 sodium Inorganic materials 0.000 description 3
- 239000011734 sodium Substances 0.000 description 3
- 239000000446 fuel Substances 0.000 description 2
- 238000009434 installation Methods 0.000 description 2
- 239000007788 liquid Substances 0.000 description 2
- 125000006850 spacer group Chemical group 0.000 description 2
- 229910001220 stainless steel Inorganic materials 0.000 description 2
- 239000010935 stainless steel Substances 0.000 description 2
- 238000007796 conventional method Methods 0.000 description 1
- 230000000630 rising effect Effects 0.000 description 1
- 238000004904 shortening Methods 0.000 description 1
- 235000021419 vinegar Nutrition 0.000 description 1
- 239000000052 vinegar Substances 0.000 description 1
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 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
- Pressure Vessels And Lids Thereof (AREA)
- Conveying And Assembling Of Building Elements In Situ (AREA)
Description
【発明の詳細な説明】
〔発明の利用分野〕
本発明は、タンク型高速増殖炉の安全容器と原
子炉容器とを工場で組立て、現地での組立作業工
程を大幅に削減する組立方法に関するものであ
る。[Detailed Description of the Invention] [Field of Application of the Invention] The present invention relates to an assembly method for assembling a safety vessel and a reactor vessel for a tank-type fast breeder reactor in a factory, thereby significantly reducing the on-site assembly work process. It is.
〔発明の背景〕
タンク型高速増殖炉の原子炉構造の縦断面を第
5図に示す。この原子炉本体の構造において、原
子炉容器1と安全容器2は、ルーフスラブ3に溶
接で固着され、密閉空間を形成している。原子炉
容器1の中では炉心4が原子炉支持構造10によ
り支持されている。一方、ルーフスラブ3には、
炉心4により加熱された高温の1次ナトリウムと
2次ナトリウムの熱交換を行う主冷却熱交換器
6、1次ナトリウムを炉内で循環させる主循環ポ
ンプ7、炉心4の出力を制御する制御棒駆動機構
(図示せず)を内包する炉心上部機構8、および
燃料交換時に図示していない燃料交換機を所定の
位置に位置決めする回転プラグ9等の機器が搭載
される構造となつている。[Background of the Invention] FIG. 5 shows a longitudinal section of the reactor structure of a tank-type fast breeder reactor. In the structure of this reactor body, a reactor vessel 1 and a safety vessel 2 are fixed to a roof slab 3 by welding to form a sealed space. Inside the reactor vessel 1 , a reactor core 4 is supported by a reactor support structure 10 . On the other hand, roof slab 3 has
A main cooling heat exchanger 6 that exchanges heat between high-temperature primary sodium and secondary sodium heated by the reactor core 4, a main circulation pump 7 that circulates the primary sodium within the reactor, and control rods that control the output of the reactor core 4. It has a structure in which equipment such as a core upper mechanism 8 that includes a drive mechanism (not shown) and a rotary plug 9 that positions a fuel exchanger (not shown) at a predetermined position during fuel exchange are mounted.
この原子炉の現地での組立方法を第6図により
説明する。各々現地に別送されてきたパーツのう
ち、先ず安全容器2を原子炉キヤビテイ11に取
り付けられた複数個のAジヤツキ12上に仮置す
る。次いで、安全容器2の底部に設けられた仮開
口13を貫通する状態で原子炉キヤビテイ11の
基礎面上に同じく複数個取り付けられているRジ
ヤツキ14上に、原子炉容器1を安全容器2の上
方から吊り降ろし仮置する。しかるのち、ルーフ
スラブ3を原子炉キヤビテイ11上に設置し、原
子炉容器1をRジヤツキ14で持ち上げて方向調
整し、ルーフスラブ3と溶接して一体とする。次
に、Aジヤツキ12上に置かれている安全容器2
をジヤツキアツプし方向調整して、ルーフスラブ
3に溶接により継ぐ。この結果、原子炉容器1、
安全容器2、ルーフスラブ3は一体化される。こ
の状態を基として逐次、炉心4、主冷却熱交換器
6、主循環ポンプ7、回転プラグ9、炉心上部機
構8、が各々組込まれ、組立が大略完了となる。 The on-site assembly method of this nuclear reactor will be explained with reference to FIG. Among the parts sent separately to the site, first, the safety container 2 is temporarily placed on a plurality of A jacks 12 attached to the reactor cavity 11. Next, the reactor vessel 1 is placed on the R jacks 14, which are also installed in plural numbers on the base surface of the reactor cavity 11, passing through the temporary opening 13 provided at the bottom of the safety vessel 2. Hang it from above and place it temporarily. Thereafter, the roof slab 3 is installed on the reactor cavity 11, the reactor vessel 1 is lifted with the R jack 14 to adjust its direction, and is welded to the roof slab 3 to be integrated. Next, the safety container 2 placed on the A jack 12
After jacking up and adjusting the direction, connect it to roof slab 3 by welding. As a result, reactor vessel 1,
The safety container 2 and the roof slab 3 are integrated. Based on this state, the core 4, main cooling heat exchanger 6, main circulation pump 7, rotary plug 9, and core upper mechanism 8 are assembled one after another, and the assembly is almost completed.
ここで、安全容器2は直径約20m強のステンレ
ス鋼製容器で、重量数百トン、または原子炉容器
もステンレス鋼製で直径約20m、重量数百トンに
も及ぶ超大型容器であるため、その組立作業は困
難を極める。この2つの容器を各々ルーフスラブ
3に取付ける作業は、原子炉構造組立期間中でも
長期間を要し、いわゆるクリテイカルパスとなる
ので、その短縮が望まれている。また、この従来
例では安全容器2と原子炉容器1との仮置の関係
で、原子炉容器1の仮置のために安全容器2の底
部には仮開口13を設ける必要がある。この仮開
口13は、原子炉容器1と安全容器2が各々ルー
フスラブ3に取付けられ、Aジヤツキ12とRジ
ヤツキ14とが撤去されたあとに溶接で閉塞され
る。この部分については、超音波探傷法等により
健全性を確認しなければならない。さらに、原子
炉容器1と安全容器2をルーフスラブ3に組付け
るときの方向調整は、各容器がいずれも数百トン
に及ぶため、非常に難かしい作業である。 Here, the safety vessel 2 is a stainless steel container with a diameter of about 20 m or more and weighs several hundred tons, and the reactor vessel is also made of stainless steel and is an extremely large container with a diameter of about 20 m and a weight of several hundred tons. The assembly work is extremely difficult. The work of attaching these two containers to the roof slab 3 requires a long period of time even during the reactor structure assembly period and constitutes a so-called critical path, so it is desired to shorten this time. Further, in this conventional example, due to the temporary placement relationship between the safety vessel 2 and the reactor vessel 1, it is necessary to provide a temporary opening 13 at the bottom of the safety vessel 2 for temporary placement of the reactor vessel 1. This temporary opening 13 is closed by welding after the reactor vessel 1 and safety vessel 2 are each attached to the roof slab 3 and the A jack 12 and R jack 14 are removed. The integrity of this part must be confirmed using ultrasonic flaw detection, etc. Furthermore, adjusting the orientation when assembling the reactor vessel 1 and the safety vessel 2 to the roof slab 3 is a very difficult task because each vessel weighs several hundred tons.
次に、現地での原子炉組立作業としては、安全
容器2に原子炉容器1の仮置用の仮開口を設けな
い方法もあり、安全容器内にスペーサを配備して
おき、原子炉容器1とルーフスラブ3との溶接後
スペーサを取り出す案も考えられるが、スペーサ
の撤去回収方法をどうするかということと、方向
調整が技術的に難かしいという問題点がある。 Next, for on-site reactor assembly work, there is a method that does not provide a temporary opening in the safety vessel 2 for temporary placement of the reactor vessel 1. Although it is conceivable to take out the spacer after welding it to the roof slab 3, there are problems in how to remove and recover the spacer and that it is technically difficult to adjust the direction.
さらに、原子炉容器の空間に液体を注入し、そ
の液体の浮力を利用することによりジヤツキ等を
不要にして、原子炉容器等を組立てる案(特開昭
56−27698)がある。ところが、この案では、何
らかの方法で浮力に抗して原子炉容器を安全容器
から浮き上がりすぎないようにしないと、所定の
間隔を保てなくなる。しかも、炉内構造物を組立
てる際に高応力が発生し、また、水に浮んだ状態
での作業は不安定であり、現地での作業量はあま
り減らず、クリテイカルパスとしての期間短縮の
問題は改善されない。 Furthermore, there is a proposal to assemble the reactor vessel, etc., by injecting liquid into the space of the reactor vessel and utilizing the buoyancy of the liquid, thereby eliminating the need for jacking.
56-27698). However, with this plan, the predetermined distance cannot be maintained unless some method is used to resist buoyancy and prevent the reactor vessel from rising too far above the safety vessel. Moreover, high stress occurs when assembling the reactor internals, and work while floating in water is unstable, so the amount of work on site does not decrease much, and it is necessary to shorten the period as a critical path. The problem is not improved.
本発明の目的は、タンク型高速増殖炉の安全容
器と原子炉容器となる超大形製缶品の現地組立工
程を大幅に削減する安全容器と原子炉容器の組立
方法を提供することである。
An object of the present invention is to provide a method for assembling a safety vessel and a reactor vessel, which greatly reduces the on-site assembly process of super-large canned products that become the safety vessel and reactor vessel of a tank-type fast breeder reactor.
本発明は、上記目的を達成するために、ルーフ
スラブの少なくとも一部に原子炉容器を伏せた状
態で位置決め固定した後、その上から安全容器を
被せて位置決めしルーフスラブに固定し、一体化
した安全容器と原子炉容器とをそのままの状態で
原子炉建設現地まで運搬して、それを現地で立直
し所定位置に据付ける方法を提案する。
In order to achieve the above object, the present invention positions and fixes a nuclear reactor vessel in a face down state on at least a part of a roof slab, then covers the safety vessel from above, positions it, fixes it to the roof slab, and integrates it. We propose a method of transporting the safety vessel and reactor vessel as they are to the reactor construction site, and then erecting them on-site and installing them in the designated position.
次に、第1図〜第4図を参照して、本発明の一
実施例を説明する。第1図は定盤上に伏せた状態
で製作された安全容器を示す図、第2図は定盤上
に伏せた状態で製作された原子炉容器とルーフス
ラブの一部とを示す図、第3図は第2図の横断面
を示す図、第4図は本発明により一体に組立てた
安全容器と原子炉容器を原子炉建設現地で据付け
る状態を示す図である。
Next, an embodiment of the present invention will be described with reference to FIGS. 1 to 4. Figure 1 is a diagram showing a safety vessel manufactured while lying face down on a surface plate, Figure 2 is a diagram showing a reactor vessel manufactured in a state lying face down on a surface plate and part of the roof slab, FIG. 3 is a cross-sectional view of FIG. 2, and FIG. 4 is a diagram showing how the safety vessel and reactor vessel assembled together according to the present invention are installed at the reactor construction site.
さて、第1図において、22は定盤である。安
全容器2は、工場内のこの定盤22上で、下部か
ら(裏返した時は上端になる)、順次鋼板を溶接
し、伏せた状態に製作される。製作した安全容器
2には、後述する如く、ルーフスラブへの組付作
業と、組立てられた原子炉容器1と安全容器2と
ルーフスラブ3との一体物の輸送据付作業とに充
分な強度のトラニオン20を取付ける。その後、
外観と寸法を検査し、更に溶接部については超音
波探傷試験等の非破壊検査により健全性を確認
し、安全容器2が完成する。 Now, in FIG. 1, 22 is a surface plate. The safety container 2 is fabricated in a face down state on this surface plate 22 in a factory by sequentially welding steel plates from the bottom (the top when turned over). As will be described later, the manufactured safety vessel 2 has sufficient strength for assembly to the roof slab and transportation and installation of the assembled reactor vessel 1, safety vessel 2, and roof slab 3 as one body. Install trunnion 20. after that,
The appearance and dimensions are inspected, and the integrity of the welded portion is confirmed by nondestructive testing such as ultrasonic flaw detection, and the safety container 2 is completed.
一方、原子炉容器1は、第2図のように、工場
内の他の定盤22上に裏返しに置かれたルーフス
ラブ3の少なくとも一部の上に、下部から順次鋼
板を溶接し、やはり伏せた状態で製作される。ま
た、ルーフスラブには、これと原子炉容器1と安
全容器2との一体物を、後述する如く、原子炉キ
ヤビテイ11に吊り込む作業に充分な強度のトラ
ニオン21を取付ける。 On the other hand, as shown in FIG. 2, the reactor vessel 1 is constructed by sequentially welding steel plates from the bottom onto at least a portion of the roof slab 3 placed upside down on another surface plate 22 in the factory. It is manufactured upside down. Furthermore, a trunnion 21 having sufficient strength is attached to the roof slab to suspend the roof slab, the reactor vessel 1, and the safety vessel 2 together into the reactor cavity 11, as will be described later.
ここでルーフスラブ3の少なくとも一部と述べ
たのは、吊り込み作業に充分な強度があれば、そ
の後の機器組込作業上便利なときは、ルーフスラ
ブすべてをその段階で組付けない方がよいからで
ある。 The reason for mentioning at least a part of the roof slab 3 here is that if the strength is sufficient for the lifting work, and if it is convenient for the subsequent equipment assembly work, it is better not to assemble the entire roof slab at that stage. Because it's good.
従つて本実施例の重要なポイントは、
(1) 吊り込み作業に充分な強度を示すルーフスラ
ブが組付けられていること、
(2) 原子炉建設現地の容器設定用基礎に載るベー
ス5がルーフスラブ3の一部として形成されて
いること、
(3) 安全容器2の上端部分となる鋼板が、工場段
階で、ルーフスラブ3に取付けられること、
である。 Therefore, the important points of this example are (1) that a roof slab that has sufficient strength for the lifting work is assembled, and (2) that the base 5, which rests on the vessel setting foundation at the reactor construction site, is installed. (3) The steel plate forming the upper end portion of the safety container 2 is attached to the roof slab 3 at the factory stage.
なおここで、安全容器2の上端部分となる鋼板
のみを、大部分の安全容器と分けて、先にルーフ
スラブ3に組付けたのは、作業性と精度上の問題
を考慮したからであり、それらの点で問題がなけ
れば安全容器を上端部まで一体に完成し、後述の
如く、ルーフスラブに組付けてもよい。 Note that the reason why only the steel plate that forms the upper end of the safety container 2 was assembled to the roof slab 3 first, separate from the majority of the safety container, was in consideration of workability and accuracy issues. If there are no problems in these respects, the safety container may be integrally completed up to the upper end and assembled to the roof slab as described below.
その後、原子炉容器1と安全容器上端部分及び
ルーフスラブ3の外観と寸法を検査し、更に溶接
部については超音波探傷試験等の非破壊検査によ
り健全性を確認し、原子炉容器1と安全容器上端
部分とルーフスラブ3の少なくとも一部との組立
が完了する。 After that, the appearance and dimensions of the reactor vessel 1, the upper end of the safety vessel, and the roof slab 3 are inspected, and the soundness of the welded parts is confirmed by non-destructive testing such as ultrasonic testing, and the safety of the reactor vessel 1 and safety vessel is confirmed. The assembly of the upper end portion of the container and at least a portion of the roof slab 3 is completed.
次に、別に完成している安全容器2を揚重機等
により吊り下げ、原子炉容器1上部に移動させ、
これに被せる。それから、予めルーフスラブ3に
取付けておいた安全容器2の上端部の上に静かに
降下させ、方向性や芯出しなどの微調整を行な
い、仮溶接の後に本溶接し、図に二点鎖線で示す
ように、安全容器2を取付ける。その後、外観と
寸法とを検査し、更に溶接部については超音波探
傷試験等の非破壊検査により健全性を確認する
と、原子炉容器1と安全容器2とルーフスラブ3
の少なくとも一部との一体物が、工場内で完成す
る。 Next, the safety vessel 2, which has been completed separately, is suspended by a lifting machine, etc., and moved to the top of the reactor vessel 1.
Cover this. Then, it is gently lowered onto the upper end of the safety container 2 that has been attached to the roof slab 3 in advance, and fine adjustments such as directionality and centering are made, and after preliminary welding, final welding is performed. Attach safety container 2 as shown. After that, the appearance and dimensions are inspected, and the soundness of the welded parts is confirmed by non-destructive testing such as ultrasonic testing.
An integrated product with at least a part of is completed in a factory.
工場で完成した容器の一体物は、伏せた状態で
現地まで輸送する。 The entire container completed at the factory is transported face down to the site.
現地での据付工程は、第6図の従来例とは異な
り、大幅に短縮される。すなわち、現地では、伏
せたまま送られてきた容器の一体物を揚重機等に
より立直し、第4図に示すように、原子炉キヤビ
テイ11の上部に移動させ、容器設定用基礎上に
吊り降す。位置を調整確認したら、ベース5を図
示しないボルト等により基礎に固定するだけで、
据付が完了する。 The on-site installation process is significantly shortened, unlike the conventional example shown in FIG. In other words, at the site, the container, which was sent face down, is erected using a lifting machine, moved to the upper part of the reactor cavity 11, and lowered onto the foundation for setting the container, as shown in Figure 4. vinegar. After adjusting and confirming the position, simply fix the base 5 to the foundation with bolts (not shown).
Installation is complete.
このように本実施例によれば、タンク型高速増
殖炉の安全容器と原子炉容器となる超大型製缶品
の現地組立工程が大幅に削減される。特にルーフ
スラブを工場内ですべて組付けたときは、原子炉
建設現地での組立ては、実質的に不要となる。 As described above, according to this embodiment, the on-site assembly process for super-large canned products that become the safety vessel and reactor vessel of a tank-type fast breeder reactor can be significantly reduced. Particularly when all the roof slabs are assembled in the factory, assembly at the reactor construction site is virtually unnecessary.
本発明によれば、次の効果が得られる。 According to the present invention, the following effects can be obtained.
(1) 現地据付工程が大幅に削減される。(1) The on-site installation process is significantly reduced.
(2) 安全容器が高品質化する。(2) The quality of safety containers will improve.
(a) 原子炉容器仮受け用に複数個の仮開口が不
要になるので、溶接部が減るとともに、超音
波探傷試験等の非破壊検査が不用となる。 (a) Multiple temporary openings for temporary reactor vessel reception are no longer required, reducing the number of welded parts and eliminating the need for non-destructive testing such as ultrasonic testing.
(b) ルーフスラブへの組付け部の現地溶接がな
くなり、作業が工場で確実にできるので、現
地での超音波探傷試験等の非破壊検査が不用
となる。 (b) On-site welding of the parts to be assembled to the roof slab is eliminated, and the work can be done reliably at the factory, eliminating the need for on-site non-destructive testing such as ultrasonic testing.
(3) 原子炉容器が高品質化する。工場内の良環境
で溶接作業ができ、ルーフスラブへの組付け部
の現地溶接がなくなるから、現地での超音波探
傷試験等の非破壊検査が不用となる。(3) Reactor vessels will be of higher quality. Welding work can be carried out in a good environment within the factory, and there is no need for on-site welding of the parts to be assembled to the roof slab, which eliminates the need for on-site non-destructive testing such as ultrasonic flaw detection.
(4) 安全容器と原子炉容器との組立作業効率が向
上する。(4) The efficiency of assembly work between the safety vessel and the reactor vessel is improved.
(a) 容器を伏せた状態で組立てるので、安定し
た作業条件の基に安全かつ容易に容器間の芯
出しができる。 (a) Since the containers are assembled face down, centering between the containers can be done safely and easily under stable working conditions.
(b) ルーフスラブへの組付け部の溶接作業を工
場でするから、作業性が良い。 (b) Workability is good because the welding work for the assembly to the roof slab is done at the factory.
(5) また、経済的効果がある。(5) It also has economic effects.
(a) 現地据付工程短縮により、人件費の削減が
可能である。 (a) Labor costs can be reduced by shortening the on-site installation process.
(b) 安全容器と原子炉容器とを一体で輸送する
から輸送費が削減される。 (b) Transportation costs are reduced because the safety container and reactor container are transported as one unit.
第1図は定盤上に伏せた状態で製作された安全
容器を示す図、第2図は定盤上に伏せた状態で製
作された原子炉容器とルーフスラブの一部とを示
す図、第3図は第2図の横断面を示す図、第4図
は本発明により一体に組立てた安全容器と原子炉
容器を原子炉建設現地で据付ける状態を示す図、
第5図はタンク型高速増殖炉の原子炉構造の縦断
面を示す図、第6図は原子炉建設現地における安
全容器と原子炉容器の従来の組立方法を示す図で
ある。
1…原子炉容器、2…安全容器、3…ルーフス
ラブ、4…炉心、5…ベース、6…主冷却熱交換
器、7…主循環ポンプ、8…炉心上部機構、9…
回転プラグ、10…原子炉支持構造、11…原子
炉キヤビテイ、12…Aジヤツキ、13…仮開
口、14…Rジヤツキ、20,21…トラニオ
ン、22…定盤。
Figure 1 is a diagram showing a safety vessel manufactured while lying face down on a surface plate, Figure 2 is a diagram showing a reactor vessel manufactured in a state lying face down on a surface plate and part of the roof slab, FIG. 3 is a cross-sectional view of FIG. 2; FIG. 4 is a diagram showing how the safety vessel and reactor vessel assembled together according to the present invention are installed at the reactor construction site;
FIG. 5 is a diagram showing a longitudinal section of the reactor structure of a tank-type fast breeder reactor, and FIG. 6 is a diagram showing a conventional method of assembling the safety vessel and reactor vessel at a reactor construction site. DESCRIPTION OF SYMBOLS 1...Reactor vessel, 2...Safety vessel, 3...Roof slab, 4...Reactor core, 5...Base, 6...Main cooling heat exchanger, 7...Main circulation pump, 8...Core upper mechanism, 9...
Rotating plug, 10... Reactor support structure, 11... Reactor cavity, 12... A jack, 13... Temporary opening, 14... R jack, 20, 21... Trunnion, 22... Surface plate.
Claims (1)
固定される安全容器と原子炉容器の組立方法にお
いて、ルーフスラブの少なくとも一部に原子炉容
器を伏せた状態で位置決め固定するステツプと、
その上から安全容器を被せて位置決めしルーフス
ラブに固定するステツプと、一体化した安全容器
と原子炉容器とをそのままの状態で原子炉建設現
地へ運搬するステツプと、現地で立直し所定位置
に据付けるステツプとからなることを特徴とする
安全容器と原子炉容器の組立方法。 2 特許請求の範囲第1項において、安全容器を
ルーフスラブに固定するステツプが、安全容器上
端となる部分を原子炉容器外側でルーフスラブ上
の所定位置に固定するステツプと、その上に安全
容器の残りの部分を載せて安全容器全体を形成す
るステツプとからなることを特徴とする安全容器
と原子炉容器の組立方法。[Claims] 1. A method for assembling a safety vessel and a reactor vessel that are fixed together to a roof slab of a tank-type fast breeder reactor, including a step of positioning and fixing the reactor vessel in a face down state on at least a part of the roof slab. and,
There are two steps: placing the safety container on top of the reactor, positioning it, and fixing it to the roof slab; transporting the integrated safety container and reactor vessel as they are to the reactor construction site; and rebuilding the reactor at the site. 1. A method for assembling a safety vessel and a reactor vessel, comprising the steps of installing. 2 In claim 1, the step of fixing the safety container to the roof slab includes the step of fixing the upper end of the safety container at a predetermined position on the roof slab outside the reactor vessel, and the step of fixing the safety container to the roof slab. A method for assembling a safety vessel and a reactor vessel, comprising the step of placing the remaining part of the safety vessel to form the entire safety vessel.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP60196957A JPS6256897A (en) | 1985-09-06 | 1985-09-06 | Method of assembling safety vessel and reactor vessel |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP60196957A JPS6256897A (en) | 1985-09-06 | 1985-09-06 | Method of assembling safety vessel and reactor vessel |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS6256897A JPS6256897A (en) | 1987-03-12 |
| JPH0252238B2 true JPH0252238B2 (en) | 1990-11-09 |
Family
ID=16366458
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP60196957A Granted JPS6256897A (en) | 1985-09-06 | 1985-09-06 | Method of assembling safety vessel and reactor vessel |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS6256897A (en) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN105452747B (en) * | 2013-08-30 | 2018-10-16 | 住友理工株式会社 | Fuel distribution tube blimp |
-
1985
- 1985-09-06 JP JP60196957A patent/JPS6256897A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS6256897A (en) | 1987-03-12 |
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