JPH01287500A - Assembly structure of biological shielding member of nuclear reactor - Google Patents
Assembly structure of biological shielding member of nuclear reactorInfo
- Publication number
- JPH01287500A JPH01287500A JP11682688A JP11682688A JPH01287500A JP H01287500 A JPH01287500 A JP H01287500A JP 11682688 A JP11682688 A JP 11682688A JP 11682688 A JP11682688 A JP 11682688A JP H01287500 A JPH01287500 A JP H01287500A
- Authority
- JP
- Japan
- Prior art keywords
- neutron
- shielding members
- neutron shielding
- concrete
- shielding
- 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.)
- Pending
Links
- 239000004567 concrete Substances 0.000 claims abstract description 23
- 239000000463 material Substances 0.000 claims description 13
- 238000009415 formwork Methods 0.000 claims description 8
- 230000003014 reinforcing effect Effects 0.000 abstract description 11
- 230000004913 activation Effects 0.000 abstract description 7
- 238000009434 installation Methods 0.000 abstract description 7
- 229910000831 Steel Inorganic materials 0.000 abstract description 3
- 239000010959 steel Substances 0.000 abstract description 3
- 238000010276 construction Methods 0.000 abstract description 2
- XEEYBQQBJWHFJM-UHFFFAOYSA-N iron Substances [Fe] XEEYBQQBJWHFJM-UHFFFAOYSA-N 0.000 description 5
- 238000000034 method Methods 0.000 description 5
- 229910052782 aluminium Inorganic materials 0.000 description 3
- XAGFODPZIPBFFR-UHFFFAOYSA-N aluminium Chemical compound [Al] XAGFODPZIPBFFR-UHFFFAOYSA-N 0.000 description 3
- 238000010586 diagram Methods 0.000 description 3
- 230000005251 gamma ray Effects 0.000 description 3
- 229920002379 silicone rubber Polymers 0.000 description 3
- 239000004945 silicone rubber Substances 0.000 description 3
- 229910052742 iron Inorganic materials 0.000 description 2
- 239000007769 metal material Substances 0.000 description 2
- 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
- 230000002285 radioactive effect Effects 0.000 description 2
- 206010073306 Exposure to radiation Diseases 0.000 description 1
- 239000004698 Polyethylene Substances 0.000 description 1
- 229910001294 Reinforcing steel Inorganic materials 0.000 description 1
- 239000004699 Ultra-high molecular weight polyethylene Substances 0.000 description 1
- 238000010521 absorption reaction Methods 0.000 description 1
- 238000002485 combustion reaction Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 230000004907 flux Effects 0.000 description 1
- 239000002440 industrial waste Substances 0.000 description 1
- -1 polyethylene Polymers 0.000 description 1
- 229920000573 polyethylene Polymers 0.000 description 1
- 238000010248 power generation Methods 0.000 description 1
- 239000012857 radioactive material Substances 0.000 description 1
- 239000011150 reinforced concrete Substances 0.000 description 1
- 229920000785 ultra high molecular weight polyethylene Polymers 0.000 description 1
Abstract
Description
【発明の詳細な説明】
〔産業上の利用分野〕
本発明は、運転を終了した原子力発電施設において、放
射化されたコンクリート構造物の解体を容易に実施でき
る構造物に係り、特に、原子炉生体遮蔽壁の解体に適用
するに好適なコンクリート構造物の組み立て構造に関す
る。[Detailed Description of the Invention] [Field of Industrial Application] The present invention relates to a structure that allows easy dismantling of radioactive concrete structures in nuclear power generation facilities that have finished operating, and in particular, to The present invention relates to an assembly structure for a concrete structure suitable for dismantling biological shielding walls.
従来の生体遮蔽壁の形状を第３図に示す。生体遮蔽壁１
は１円筒形と円錐形を組み合わせた形状をしており、そ
の構造は、第４図に示すように、ｓｇ格納容器１３．鉄
板型枠１１及びその外側に鉄筋コンクリート層から構成
されている。コンクリート内の鉄筋は、縦方向筋９、円
周方向筋８゜及び、巾止め筋１０が数百本組合わされて
おり、強固な構造物となっている。FIG. 3 shows the shape of a conventional biological shielding wall. Living body shielding wall 1
1 has a shape that is a combination of a cylindrical shape and a conical shape, and its structure is as shown in FIG. It consists of a steel plate formwork 11 and a reinforced concrete layer on the outside thereof. The reinforcing bars in the concrete are a combination of several hundred longitudinal bars 9, circumferential bars 8°, and stop bars 10, making it a strong structure.
一方、生体遮蔽壁は、プラント通常運転中、炉心３の燃
焼により原子炉圧力容器２、熱遮蔽壁４と同様に中性子
照射を受け、放射化される。生体遮蔽壁１内に生成され
る放射性核種としては、Ｇｏ−６０，Ｆｅ、−５５，Ｍ
ｎ−５４等が主体となっており、さらに、放射化コンク
リートからの空間線量率の寄与もある。放射化される範
囲は、第５図に示すように、炉心３のレベルを中心とし
た生体遮蔽壁１内側部分であり、放射化される範囲は、
中性子フラックス、照射化される原子の中性子吸収断面
積等により異なるため、プラント毎により異なり、特定
することはできない。On the other hand, during normal plant operation, the biological shielding wall is irradiated with neutrons due to combustion of the reactor core 3, similar to the reactor pressure vessel 2 and the heat shielding wall 4, and is activated. Radionuclides generated within the biological shielding wall 1 include Go-60, Fe, -55, M
n-54 etc. are the main sources, and there is also a contribution from the air dose rate from radioactive concrete. As shown in FIG. 5, the area to be activated is the inner part of the biological shielding wall 1 centered at the level of the reactor core 3, and the area to be activated is:
It varies depending on the neutron flux, the neutron absorption cross section of the irradiated atoms, etc., and therefore varies from plant to plant and cannot be specified.
この放射化される範囲を限定する方策は特願昭５９−２
３０７３３ ｒ原子炉生体遮蔽壁構造」に述べられてい
るように、鉄板型枠１１の外側に中性子遮蔽部材を埋め
込む方法がある。ただし、この方策を用いる場合には、
従来と同様な鉄板型枠１１が必要となり、また、建設現
場での据付工数も、中性子遮蔽部材の据付分だけ増加す
るため１発電所全体の据付工期にも影響を及ぼす可能性
があった。The measures to limit the range of radioactivity were proposed in the patent application No. 59-2.
There is a method of embedding a neutron shielding member on the outside of the iron plate form 11, as described in ``Nuclear Reactor Bioshielding Wall Structure''. However, when using this strategy,
A steel plate form 11 similar to the conventional one is required, and the number of man-hours required for installation at the construction site increases by the amount of neutron shielding members installed, which may affect the installation period for the entire power plant.
本発明の目的は、従来技術の課題の解決策として、放射
化エリアを中性子遮蔽部材を用いたコンクリート打込型
枠のみとして、外型鉄筋・コンクリートの放射化を回避
し、また、現地での据付を容易とした原子炉生体遮蔽壁
の組み立て構造を得ることにある。The purpose of the present invention is to solve the problems of the prior art by limiting the activation area to concrete pouring formwork using neutron shielding members to avoid activation of external reinforcing bars and concrete. The object of the present invention is to obtain an assembly structure for a biological shielding wall for a nuclear reactor that is easy to install.
〔課題を解決するための手段〕
上記目的を達成する為に、コンクリート打込型枠として
中性子遮蔽部材をアルミニウム等で成形した部材を前も
って工場で組み立て、現地での据付作業はこれら中性子
遮蔽部材の接続、つなぎ込みだけとしてコンクリート打
込型枠を組み立て、これを従来の鉄筋型枠の代りに使用
し、それ以降の配筋、コンクリート作業は従来と同一手
順で進める。[Means for solving the problem] In order to achieve the above objective, neutron shielding members molded from aluminum etc. are pre-assembled in a factory as concrete pouring formwork, and installation work on site is carried out using these neutron shielding members. Concrete pouring formwork is assembled for only connections and connections, and this is used in place of the conventional reinforcing steel formwork, and subsequent reinforcing and concrete work proceed in the same manner as before.
以下、本発明の一実施例を第１図および第２図により説
明する。An embodiment of the present invention will be described below with reference to FIGS. 1 and 2.
第１図は、中性子遮蔽部材の一例である。中性子遮蔽部
材１４は、内部に中性子遮蔽機能をもつ材料を充填し、
外部をアルミニウム等の金属材料で包み込み、遮蔽上の
要求機能、および、構造上の要求機能を満足する部材と
して構成される。FIG. 1 is an example of a neutron shielding member. The neutron shielding member 14 is filled with a material having a neutron shielding function,
The exterior is wrapped in a metal material such as aluminum, and it is constructed as a member that satisfies the required shielding and structural functions.
内部に充填される中性子遮蔽材としては、遮蔽機能の他
に、耐放射線性、加工性等が要求されるが、既存の材料
で上記の機能の満足が期待できる。The neutron shielding material filled inside is required to have radiation resistance, workability, etc. in addition to the shielding function, and existing materials can be expected to satisfy the above functions.
具体的な中性子遮蔽材の例を以下に示す。Specific examples of neutron shielding materials are shown below.
中性子遮蔽材は、シリコンゴム系のＳ Ｅ １８１１゜
ＲＸ−２３７、あるいは、ポリエチレン系のニューライ
トＢＦ等がある。これ等の材料は、それぞれ普通コンク
リート以上の中性子遮蔽性能をもち。Examples of the neutron shielding material include silicone rubber S E 1811° RX-237, polyethylene Newlite BF, and the like. Each of these materials has neutron shielding performance greater than that of ordinary concrete.
普通コンクリートの二倍程度までの遮蔽性能をもってい
る。中性子に対して、コンクリート３０ａｍと等価な遮
蔽厚さは、それぞれ、５Ｅ１８１１の場合、約１８ａ＋
＋、 ＲＸ −２３７で約１３ａｌ、ニューライトＢＦ
で約１０ａｍで等価な遮蔽性能を持つことが可能である
。また、これ等の中性子遮蔽材は同時にガンマ線に対し
ての遮蔽機能をもっており、それぞれ普通コンクリート
に対して半分以上のガンマ線遮蔽能力を持っているため
、ガンマ線に対しての遮蔽機能を同時に期待できる。It has a shielding performance up to twice that of ordinary concrete. For neutrons, the equivalent shielding thickness of 30 am of concrete is approximately 18 a+ for 5E1811, respectively.
+, about 13al in RX-237, New Light BF
It is possible to have equivalent shielding performance at about 10 am. In addition, these neutron shielding materials also have a gamma ray shielding function, and each has more than half the gamma ray shielding ability of ordinary concrete, so they can be expected to have a gamma ray shielding function at the same time.
また、これ等の中性子遮蔽材料１４には耐放射線性の機
能が要求されるが、原子力発電所における最も厳しい条
件、炉心近傍の炉心レベルに於ける使用を仮定しても、
５Ｅ１８１１．ＲＸ−２３７゜ニューライトＢＦ、それ
ぞれ、中性子線に対して７ Ｘ １０”以上、ガンマ線
に対して２Ｘ１０”以上の耐用年数をもっており、原子
炉の耐用年数である四十年間の健全性が確保できる。In addition, these neutron shielding materials 14 are required to have a radiation-resistant function, but even if we assume that they are used at the core level near the reactor core, which is the most severe condition in a nuclear power plant,
5E1811. RX-237゜Neurite BF has a service life of 7 x 10" or more for neutron beams and 2 x 10" or more for gamma rays, ensuring soundness for 40 years, which is the service life of a nuclear reactor. .
次に、これ等の材料を中性子遮蔽部材として使用する場
合の加工性について説明する。５Ｅ１８１１は二液混合
タイプのシリコンゴムであるため、機械加工は容易にで
き、また、あらかじめ用意した型枠により希望の形状・
大きさに成形できるため、加工性、および、施工性は良
い、ＲＸ−２３７もシリコンゴムであるため、５ＥＩ８
１１と同様機械加工性も良好であり、希望の形状・大き
さのブロック等にキャスティング成形でき、加工性、お
よび。Next, processability when using these materials as a neutron shielding member will be explained. Since 5E1811 is a two-component mixed silicone rubber, it can be easily machined, and it can be shaped into the desired shape using pre-prepared molds.
Since RX-237 can be molded to any size, it has good processability and workability.Since RX-237 is also made of silicone rubber, it is 5EI8.
Like No. 11, it has good machinability, and can be cast into blocks of desired shape and size, and has good workability.
施工性は良い。ニューライトＢＦは、超高分子量ポリエ
チレンが主成分であるため、機械加工は鉄工用はもちろ
ん、木工用加工機械で簡単に行なえる。非常に滑りのよ
い材料であるため、通常、切削熱によりトラブルは生じ
ない。Workability is good. Since Newlite BF is mainly composed of ultra-high molecular weight polyethylene, it can be easily machined using not only ironworking but also woodworking processing machines. Since it is a very slippery material, cutting heat usually does not cause any trouble.
以上に述べた様な中性子遮蔽材をアルミニウム、鉄板等
の金属材料で包み込み、第１図に示したような中性子遮
蔽部材を構成する。A neutron shielding member as shown in FIG. 1 is constructed by wrapping the neutron shielding material as described above in a metal material such as aluminum or iron plate.
次に、第２図を用いて、実際の組み立て方法について説
明する。Next, the actual assembly method will be explained using FIG. 2.
第２図は、原子炉生体遮蔽壁の断面図である。FIG. 2 is a cross-sectional view of the reactor biological shielding wall.
１４は生体遮蔽壁建設時のコンクリート打ち込み型枠に
使用する前述の中性子遮蔽部材、１５は中性子遮蔽部材
をコンクリート中に固定するスタッド、１６は、中性子
遮蔽部材同士を固定する止め金具、１７は、止め金具固
定用のボルト、８は生体遮蔽壁円周方向構造鉄筋、９は
同じく縦方向構造鉄筋、１０は巾止め鉄筋である。14 is the above-mentioned neutron shielding member used in concrete pouring formwork when constructing a bioshielding wall; 15 is a stud for fixing the neutron shielding member in concrete; 16 is a fastener for fixing the neutron shielding members to each other; 17 is a Bolts for fixing the fasteners, 8 are structural reinforcing bars in the circumferential direction of the biological shielding wall, 9 are longitudinal structural reinforcing bars, and 10 are stopper reinforcing bars.
組み立ての手順は、原子炉格納容４９）１３の据付完了
後、先ず、中性子遮蔽部材１４の組み立てを行なう、こ
の組み立ては、遮蔽部材に固定されたボルト１７を止め
金具１６を用い工接続し、中性子遮蔽部材同士を固定す
る。この固定は、従来と同様、必要に応じて゛原子炉格
納容器１３からのサポートを使用する。この後、鉄筋８
，９．１０の設定を行ない、外側型枠の設定後にコンク
リート１２を打設して、コンクリートの養生を待って据
え付けが完了する。The assembly procedure is as follows: After the installation of the reactor containment vessel 49) 13 is completed, the neutron shielding member 14 is first assembled.This assembly involves connecting the bolts 17 fixed to the shielding member using the fasteners 16. Fix the neutron shielding members together. This fixation uses support from the reactor containment vessel 13 as necessary, as in the past. After this, reinforcing bar 8
, 9.10, and after setting the outer formwork, concrete 12 is poured, and the installation is completed after the concrete has cured.
上記の手順で据え付けられた原子炉生体遮蔽壁では、炉
心よりの中性子線照射エリアを中性子遮蔽部材１４でカ
バーしているために、放射化エリアは、中性子遮蔽部材
１４に限定することができる。また、この中性子遮蔽部
材１４についても、炉停止後１０日後で１０″″’Ｃｉ
／ｌｏｎのオーダとなり、一般産業廃棄物として取扱え
る可能性が高い、この場合には、放射化物量を微量とす
ることが可能となる。In the reactor biological shielding wall installed in the above procedure, the neutron beam irradiation area from the reactor core is covered by the neutron shielding member 14, so the activation area can be limited to the neutron shielding member 14. Also, regarding this neutron shielding member 14, 10""' Ci
/lon, and there is a high possibility that it can be treated as general industrial waste.In this case, it is possible to reduce the amount of radioactive materials to a trace amount.
なお１図中５は原子炉圧力容器ペデスタル、６はダイヤ
フラムフロア、７は格納容器、生体遮蔽壁間ギャップ、
１２はコンクリートである。In Figure 1, 5 is the reactor pressure vessel pedestal, 6 is the diaphragm floor, 7 is the containment vessel, the gap between biological shield walls,
12 is concrete.
本発明によれば、遮蔽壁の放射化エリアは中性子遮蔽部
材に限定され、鉄筋およびコンクリートの放射化回避が
可能となる。中性子吸収部材のみを機械的切断工法によ
り剥離することができ、解体工数の低減、作業時の被曝
低減を図ることができる。According to the present invention, the activation area of the shielding wall is limited to the neutron shielding member, making it possible to avoid activation of reinforcing bars and concrete. Only the neutron absorbing member can be peeled off using a mechanical cutting method, reducing the number of dismantling steps and reducing exposure to radiation during work.
第１図は本発明の一実施例の中性子遮蔽体の側面図、第
２図は本発明を採用した生体遮蔽壁の断面図、第３図は
本発明の原子力発電所原子炉生体遮蔽壁の形状の説明図
、第４図は第３図で示した原子炉生体遮蔽壁構造の説明
図、第５図はプラント運転時の中性子照射により生体遮
蔽壁が放射化される範囲を示す説明図である。
１・・・原子炉生体遮蔽壁、２・・・原子炉圧力容器、
３・・・炉心、４・・・熱遮蔽壁、５・・・原子炉圧力
容器ペデスタル、６・・・ダイアフラムフロア、７・・
・格納容器と生体遮蔽壁間のギャップ、８・・・円周方
向鉄筋。
９・・・縦方向鉄筋。
第１図
第２図
ｉ
第３図
第４図
第５図FIG. 1 is a side view of a neutron shield according to an embodiment of the present invention, FIG. 2 is a sectional view of a biological shielding wall adopting the present invention, and FIG. 3 is a cross-sectional view of a biological shielding wall for a nuclear power plant reactor according to the present invention. An explanatory diagram of the shape, Figure 4 is an explanatory diagram of the reactor biological shielding wall structure shown in Figure 3, and Figure 5 is an explanatory diagram showing the range where the biological shielding wall is activated by neutron irradiation during plant operation. be. 1... Reactor biological shielding wall, 2... Reactor pressure vessel,
3... Reactor core, 4... Heat shield wall, 5... Reactor pressure vessel pedestal, 6... Diaphragm floor, 7...
・Gap between containment vessel and biological shielding wall, 8...Circumferential reinforcing bars. 9... Vertical reinforcing bars. Figure 1 Figure 2 i Figure 3 Figure 4 Figure 5
Claims (1)
射される中性子に対し好適な遮蔽材料として機能する材
料よりなる前記中性子の遮蔽部材をコンクリート打設時
の型枠として使用して生体遮蔽壁を組み立てることによ
り、原子カプラントの寿命中の前記中性子の照射によつ
て放射化されるエリアを前記中性子遮蔽部材だけにとど
めることを特徴とする原子炉生体遮蔽壁の組み立て構造
。1. In assembling the reactor biological shielding wall, the neutron shielding member made of a material that functions as a suitable shielding material for neutrons irradiated from the reactor core is used as a formwork during concrete pouring to construct the biological shielding wall. 1. An assembly structure for a nuclear reactor bioshielding wall, characterized in that by assembling the neutron shielding member, the area activated by the neutron irradiation during the lifetime of the nuclear couplant is limited to the neutron shielding member.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP11682688A JPH01287500A (en) | 1988-05-16 | 1988-05-16 | Assembly structure of biological shielding member of nuclear reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP11682688A JPH01287500A (en) | 1988-05-16 | 1988-05-16 | Assembly structure of biological shielding member of nuclear reactor |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH01287500A true JPH01287500A (en) | 1989-11-20 |
Family
ID=14696582
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP11682688A Pending JPH01287500A (en) | 1988-05-16 | 1988-05-16 | Assembly structure of biological shielding member of nuclear reactor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH01287500A (en) |
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2007304070A (en) * | 2006-05-15 | 2007-11-22 | Taisei Corp | Shielding structure of nuclear reactor pressure vessel |
| JP2010281647A (en) * | 2009-06-03 | 2010-12-16 | Taisei Corp | Activation reducing method |
| JP2016102650A (en) * | 2014-11-27 | 2016-06-02 | 株式会社安藤・間 | Neutron shield structure and neutron irradiation chamber |
-
1988
- 1988-05-16 JP JP11682688A patent/JPH01287500A/en active Pending
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2007304070A (en) * | 2006-05-15 | 2007-11-22 | Taisei Corp | Shielding structure of nuclear reactor pressure vessel |
| JP2010281647A (en) * | 2009-06-03 | 2010-12-16 | Taisei Corp | Activation reducing method |
| JP2016102650A (en) * | 2014-11-27 | 2016-06-02 | 株式会社安藤・間 | Neutron shield structure and neutron irradiation chamber |
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