JPH0131158B2 - - Google Patents
Info
- Publication number
- JPH0131158B2 JPH0131158B2 JP59019873A JP1987384A JPH0131158B2 JP H0131158 B2 JPH0131158 B2 JP H0131158B2 JP 59019873 A JP59019873 A JP 59019873A JP 1987384 A JP1987384 A JP 1987384A JP H0131158 B2 JPH0131158 B2 JP H0131158B2
- Authority
- JP
- Japan
- Prior art keywords
- reactor
- core
- coolant
- support member
- container
- 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
- 239000002826 coolant Substances 0.000 claims description 22
- 239000012530 fluid Substances 0.000 claims description 18
- 229910001338 liquidmetal Inorganic materials 0.000 claims description 5
- 238000006073 displacement reaction Methods 0.000 description 5
- 230000036541 health Effects 0.000 description 3
- 239000000463 material Substances 0.000 description 3
- 230000007246 mechanism Effects 0.000 description 3
- 238000001816 cooling Methods 0.000 description 2
- 238000013016 damping Methods 0.000 description 2
- 239000004570 mortar (masonry) Substances 0.000 description 2
- 230000035882 stress Effects 0.000 description 2
- 230000008646 thermal stress Effects 0.000 description 2
- 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 1
- 230000009471 action Effects 0.000 description 1
- 238000005452 bending Methods 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 230000006872 improvement Effects 0.000 description 1
- 238000000034 method Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000035939 shock Effects 0.000 description 1
- 229910052708 sodium Inorganic materials 0.000 description 1
- 239000011734 sodium 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
- Treatment Of Water By Oxidation Or Reduction (AREA)
- Analysing Materials By The Use Of Radiation (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Description
【発明の詳細な説明】
〔発明の技術分野〕
本発明は、冷却材として液体金属を用いるとと
もに、炉心が原子炉容器内の上記冷却材中に吊下
げ支持されてなる原子炉の改良に関する。DETAILED DESCRIPTION OF THE INVENTION [Technical Field of the Invention] The present invention relates to an improvement in a nuclear reactor in which a liquid metal is used as a coolant and a reactor core is suspended and supported within the coolant in a reactor vessel.
原子炉、たとえば高速増殖炉は、一般に、冷却
材として液体金属ナトリウムで代表される液体金
属を用い、かつ軽水炉型原子炉に比較して高い温
度で運転される。このような高速増殖炉にあつて
は、原子炉運転開始時や停止時に、原子炉主容
器、炉心機材、配管等が熱応力で損傷されるのを
防止するため、通常、これら構成部材の肉厚を薄
くする方式が採用されている。
Nuclear reactors, such as fast breeder reactors, generally use liquid metal, typically liquid metal sodium, as a coolant and are operated at higher temperatures than light water reactors. In such fast breeder reactors, in order to prevent the reactor main vessel, core equipment, piping, etc. from being damaged by thermal stress when starting or stopping reactor operation, the walls of these components are usually A method is used to reduce the thickness.
また、このような高速増殖炉全体を簡潔な構造
とする為に、可能な限り配管類を無くすようにし
た原子炉、すなわち、具体的には一次冷却材と二
次冷却材とを熱交換させる一次熱交換器や冷却材
循環ポンプを原子炉主容器内に設置するようにし
た、いわゆるタンク型原子炉構造が考えられてい
る。 In addition, in order to make the overall structure of such a fast breeder reactor simple, a nuclear reactor that eliminates piping as much as possible, that is, a reactor that exchanges heat between the primary coolant and the secondary coolant. A so-called tank-type nuclear reactor structure is being considered, in which a primary heat exchanger and a coolant circulation pump are installed within the main reactor vessel.
このタンク型原子炉は、たとえば第1図に示す
ように、原子炉主容器1の図中上方開口部をルー
フスラブ2で閉塞し、内部に炉心3、炉心上部機
構4、一次熱交換器5、冷却材循環ポンプ6およ
び冷却材7を収容して構成されている。炉心3
は、ルーフスラブ2から吊下げられた炉心支持部
材8の図中下端部に収容されており、炉心上部機
構4は、上記炉心支持部材8の上方に回転自在に
設けられた回転プラグ9に支持されている。な
お、原子炉主容器1は、リングガータ10を介し
て原子炉室11に吊下げられており、原子炉主容
器1の外側にはこの原子炉主容器1を覆うように
安全容器12が設けられている。 In this tank-type nuclear reactor, for example, as shown in FIG. 1, the upper opening in the figure of the reactor main vessel 1 is closed with a roof slab 2, and the interior includes a reactor core 3, a core upper mechanism 4, a primary heat exchanger 5, , a coolant circulation pump 6 and a coolant 7. core 3
is housed at the lower end in the figure of a core support member 8 suspended from the roof slab 2, and the core upper mechanism 4 is supported by a rotary plug 9 rotatably provided above the core support member 8. has been done. The reactor main vessel 1 is suspended in the reactor room 11 via a ring gutter 10, and a safety vessel 12 is provided outside the reactor main vessel 1 so as to cover the reactor main vessel 1. It is being
このようなタンク型原子炉構造を採用すること
によつて、一次熱交換系、冷却材循環系の配管を
削除することができる。 By adopting such a tank-type nuclear reactor structure, piping for the primary heat exchange system and coolant circulation system can be eliminated.
しかしながら、このようなタンク型原子炉構造
を採用した原子炉であつても次のようなことが予
想される。すなわち、炉心支持部材8は、熱応力
上の面から比較的薄肉に形成され、かつ大型化に
伴なう大きな熱膨張量を吸収するために、ルーフ
スラブ2に支持されて原子炉主容器1内に吊り下
げられた片持梁構造となつている。そして重量物
である炉心3は炉心支持部材8の下端部で支持さ
れている。したがつて、外部からの衝撃入力また
は振動入力が加わつた場合、原子炉主容器1の振
動や冷却材7の振動とルーフスラブの曲げ変形と
が相俟つて、炉心支持部材8が垂直水平方向に複
雑な変形モードを呈し、その変形による局部的応
力の増大で炉心支持部材8や炉心3の一部が損傷
を受ける可能性があり、何らかの対策が望まれ
る。
However, even in a nuclear reactor that employs such a tank-type reactor structure, the following problems are expected. That is, the reactor core support member 8 is formed to be relatively thin in terms of thermal stress, and is supported by the roof slab 2 and attached to the reactor main vessel 1 in order to absorb a large amount of thermal expansion due to the increase in size. It has a cantilevered structure suspended inside. The core 3, which is a heavy object, is supported at the lower end of the core support member 8. Therefore, when shock or vibration input is applied from the outside, the vibrations of the reactor main vessel 1, the vibrations of the coolant 7, and the bending deformation of the roof slab combine to cause the core support member 8 to bend in the vertical and horizontal directions. It exhibits a complicated deformation mode, and there is a possibility that the core support member 8 and a part of the reactor core 3 may be damaged due to an increase in local stress due to the deformation, so some kind of countermeasure is desired.
そこで、このような不具合を解消するために炉
心支持部材8の下端部外周に環状体を嵌合させ、
この環状体を支持部材で原子炉主容器1の内面に
固定することが考えられるが、このようにする
と、地震時等に原子炉主容器1と炉心3とが互い
に連成し合い、複雑な動きを呈する虞れがある。 Therefore, in order to solve this problem, an annular body is fitted to the outer periphery of the lower end of the core support member 8.
It is conceivable to fix this annular body to the inner surface of the reactor main vessel 1 with a support member, but in this case, the reactor main vessel 1 and the reactor core 3 will be coupled to each other in the event of an earthquake, etc., resulting in a complicated There is a risk of movement.
さらに、このように炉心部と原子炉主容器1と
を支持部材で機械的に接続する場合には、支持部
材の熱膨張を吸収するため、支持部材をいわゆる
すり鉢状に形成するとともに、炉心支持部材8の
下端部外周と、この下端部外周に取付けられた環
状体とを上下方向に移動可能な如く接続する必要
がある。しかしながら、地震は、水平動のみなら
ず、上下動が存在するので、このような構造で
は、上下方向の拘束がルーフスラブ以外にないた
めに、炉心支持部材8および炉心3は上下方向に
大きく振動する可能性がある。 Furthermore, when mechanically connecting the reactor core and the reactor main vessel 1 using a support member, the support member is formed into a so-called mortar shape in order to absorb the thermal expansion of the support member, and the core support It is necessary to connect the outer periphery of the lower end of the member 8 and the annular body attached to the outer periphery of the lower end so as to be movable in the vertical direction. However, in an earthquake, there is not only horizontal motion but also vertical motion, so in such a structure, since there is no vertical restraint other than the roof slab, the core support member 8 and the reactor core 3 are subject to large vertical vibrations. there's a possibility that.
このように、炉心部が水平動と上下動の複雑な
連成挙動を示すと炉全体の健全性に大きな影響を
与えかねない。 In this way, if the reactor core exhibits complex coupled behavior of horizontal motion and vertical motion, it could have a significant impact on the health of the entire reactor.
本発明は、このような事情に鑑みてなされたも
のであり、その目的とするところは、全体の複雑
化を招くことなしに、地震発生時等における容器
と炉心部との水平および垂直方向の相対的な変位
を他に影響を与えることなしに速やかに抑制する
ことができ、もつて地震時等における炉全体の健
全性の向上を図ることができる原子炉を提供する
ことにある。
The present invention has been made in view of the above circumstances, and its purpose is to improve the horizontal and vertical alignment between the vessel and the reactor core during an earthquake, etc., without complicating the entire structure. It is an object of the present invention to provide a nuclear reactor that can quickly suppress relative displacement without affecting other components, thereby improving the health of the entire reactor during earthquakes and the like.
〔発明の概要〕
本発明は、冷却材として液体金属を用いるとと
もに炉心部が原子炉主容器内の上記冷却材中に吊
下げ支持されてなる原子炉において、上記炉心部
の側面および底面を流体ギヤツプを介して容器で
覆うとともに、この容器を前記原子炉容器に固定
部材で固定したことを特徴としている。[Summary of the Invention] The present invention provides a nuclear reactor in which a liquid metal is used as a coolant and a reactor core is suspended and supported in the coolant in a main reactor vessel. It is characterized in that it is covered with a container through a gap, and this container is fixed to the reactor container with a fixing member.
本発明では、炉心部の側面および底面を覆うよ
うに容器を設け、この容器と上記炉心部との間に
冷却材で埋められた流体ギヤツプを形成するよう
にしている。このため、原子炉に衝撃入力が印加
され、炉心が原子炉主容器に対して相対移動を起
こした場合には、原子炉主容器に固定された容器
と上記炉心部との間に相対変位が生じ、上記流体
ギヤツプに部分的な圧力差が発生する。したがつ
て、炉心は、この圧力差を相殺する向きの力を受
けて、おしもどされる。
In the present invention, a container is provided to cover the side and bottom surfaces of the core, and a fluid gap filled with coolant is formed between the container and the core. Therefore, when an impact input is applied to the reactor and the core moves relative to the reactor main vessel, there will be a relative displacement between the vessel fixed to the reactor main vessel and the reactor core. This results in a local pressure difference across the fluid gap. Therefore, the core is pushed back by a force that offsets this pressure difference.
また、衝撃入力によつて発生する炉心部の振動
エネルギーは、上述の如く流体ギヤツプ内を流動
する冷却材の流動摩擦によつて消散される。つま
り、流体ギヤツプを形成する冷却材が緩衝材とし
て効果的に作用し、炉心部の振動を速やかに抑制
することが可能となる。 Furthermore, the vibrational energy in the core generated by the impact input is dissipated by the flow friction of the coolant flowing in the fluid gap, as described above. In other words, the coolant forming the fluid gap effectively acts as a buffer, making it possible to quickly suppress vibrations in the core.
これに加え、炉心部の側面および底面は、流体
ギヤツプ内の冷却材を介して原子炉主容器に連結
されているので、炉心部と原子炉主容器とを機械
的に結合させた場合に較べて両者間での連成振動
が発生し難い関係にある。したがつて、連成振動
によつて予想される複雑な変形モードの発生を防
止することができ、結局、地震時等における炉全
体の健全性を向上させることができる。 In addition, the side and bottom surfaces of the reactor core are connected to the reactor main vessel via the coolant in the fluid gap, compared to a case where the reactor core and the reactor main vessel are mechanically connected. This relationship makes it difficult for coupled vibration to occur between the two. Therefore, it is possible to prevent the occurrence of complex deformation modes that would be expected due to coupled vibrations, and as a result, the health of the entire furnace during earthquakes can be improved.
しかも、この場合には、炉心部を容器で覆うと
いう至つて簡単な構成のみで上述の効果を呈する
ことができる。したがたつて、全体の複雑化を招
くようなこともない。 Moreover, in this case, the above-mentioned effects can be achieved with only a very simple configuration of covering the reactor core with a container. Therefore, it does not cause the overall complexity.
以下、第2図を参照し、本発明の一実施例につ
いて説明する。なお、第2図において第1図と同
一部分には同一符号を付し、重複する部分の説明
は省くことにする。
Hereinafter, one embodiment of the present invention will be described with reference to FIG. Note that in FIG. 2, the same parts as in FIG. 1 are given the same reference numerals, and explanations of the overlapping parts will be omitted.
第2図において、第1図と異なる点は、炉心支
持部材8の炉心収容部を覆うように振れ止め用の
容器16を設けた点である。すなわち、炉心支持
部材8は、たとえば薄肉の有底円筒体からなり、
内部下方に炉心3を収容し得る構造となつてい
る。容器16は、この炉心支持部材8の炉心収容
部分の側面および底面を外側から非接触で覆うよ
うに同軸配置され、内面に沿つて流体ギヤツプ1
7を形成するとともに、いわゆるすり鉢状に形成
された支持板19を介して原子炉主容器1に支持
されている。なお、容器16には、側面に孔20
が設けられ、この孔20に炉心3と循環ポンプ6
とを連通するパイプ21を非接触で貫通させるよ
うにしている。 2 differs from FIG. 1 in that a steady rest container 16 is provided to cover the core housing portion of the core support member 8. That is, the core support member 8 is made of, for example, a thin-walled cylinder with a bottom,
It has a structure that allows the reactor core 3 to be accommodated in the lower part of the interior. The container 16 is coaxially arranged so as to cover the side and bottom surfaces of the core housing portion of the core support member 8 from the outside without contact, and the fluid gap 1 is disposed along the inner surface of the container 16 .
7 and is supported by the reactor main vessel 1 via a support plate 19 formed in a so-called mortar shape. Note that the container 16 has a hole 20 on the side surface.
A core 3 and a circulation pump 6 are provided in this hole 20.
A pipe 21 communicating with the two is passed through without contact.
しかして、このように構成された本実施例に係
る原子炉において、いま水平方向の衝撃入力が加
えられ、炉心3が原子炉主容器1に対して水平方
向の振動を生起されたとする。この場合には、炉
心3を支持する炉心支持部材8の炉心収容部は、
容器16に対して径方向の変位を生じる。この結
果、流体ギヤツプ17では、瞬間的にギヤツプを
狭められる部分と、逆にギヤツプを拡げられる部
分とで圧力差が生じ、炉心3はこの圧力差を相殺
する向きの力を与えられて、上記変位を縮める向
きに移動する。 Suppose now that a horizontal impact input is applied to the nuclear reactor according to the present embodiment configured as described above, causing the reactor core 3 to vibrate in the horizontal direction relative to the reactor main vessel 1. In this case, the core housing portion of the core support member 8 that supports the core 3 is
A radial displacement occurs relative to the container 16. As a result, in the fluid gap 17, a pressure difference is created between the part where the gap is momentarily narrowed and the part where the gap is widened, and the core 3 is given a force in the direction that offsets this pressure difference, and the Move in the direction to reduce displacement.
また、上記原子炉主容器1に対する炉心3の変
位によつて生じた流体ギヤツプ17の圧力差は、
流体ギヤツプ17に存在する冷却材の流体ギヤツ
プ17内での流動を生じさせる。このため、上記
流体ギヤツプ17内では流動摩擦が発生し、炉心
3に与えられた振動エネルギーはこの流動摩擦に
よつて消散される。つまり、流体ギヤツプ17を
構成する冷却材7が緩衝材として有効に作用する
ため、炉心3の振動は速やかに抑制されることに
なる。 Furthermore, the pressure difference in the fluid gap 17 caused by the displacement of the reactor core 3 with respect to the reactor main vessel 1 is as follows:
This causes the coolant present in the fluid gap 17 to flow within the fluid gap 17. Therefore, fluid friction occurs within the fluid gap 17, and the vibration energy applied to the core 3 is dissipated by this fluid friction. In other words, since the coolant 7 constituting the fluid gap 17 effectively acts as a buffer material, the vibrations of the core 3 are quickly suppressed.
一方、炉心3が原子炉主容器1に対して、垂直
方向に振動した場合であつても、同様に流体ギヤ
ツプ17による効果的な制振作用が炉心3に働く
ことになる。 On the other hand, even if the reactor core 3 vibrates in the vertical direction with respect to the reactor main vessel 1, an effective vibration damping action by the fluid gap 17 will similarly act on the reactor core 3.
このように、本実施例によれば、炉心支持部材
8の炉心収容部を流体ギヤツプ17を介して容器
16で覆うという極めて簡単な構成によつて、通
常、炉心3の冷却に使用される冷却材を緩衝材と
して有効に利用して、地震時等における炉心部の
振動を抑制することができ、しかも、その制振効
果は、いずれの方向の振動に対しても非常に高い
ものとなる。そして、この場合には、炉心支持部
材8と容器16とは非接触状態である。したがつ
て、容器16、支持板19および炉心支持部材8
の熱膨張による変形を、ギヤツプ部で吸収するこ
とができ、これらの部材に過大な応力が作用する
こともない。このため、炉心3はルーフスラブ2
に常に安定支持され、原子炉の安全性を極めて高
いものとすることができる。 As described above, according to the present embodiment, the cooling that is normally used for cooling the core 3 is achieved by an extremely simple structure in which the core accommodating portion of the core support member 8 is covered with the container 16 via the fluid gap 17. The material can be effectively used as a buffer material to suppress vibrations in the reactor core during earthquakes, etc., and its damping effect is extremely high against vibrations in any direction. In this case, the core support member 8 and the container 16 are in a non-contact state. Therefore, the container 16, the support plate 19 and the core support member 8
The deformation caused by thermal expansion can be absorbed by the gap portion, and no excessive stress is applied to these members. For this reason, the core 3 is connected to the roof slab 2.
The reactor can be stably supported at all times, making the reactor extremely safe.
なお、本発明は上記実施例に限定されるもので
はなく、その要旨を逸脱しない範囲で種々変形が
可能である。 Note that the present invention is not limited to the above-mentioned embodiments, and various modifications can be made without departing from the gist thereof.
第1図は従来のタンク型原子炉を示す概略的な
縦断面図、第2図は本発明の一実施例に係るタン
ク型原子炉を示す概略的な縦断面図である。
1……原子炉主容器、2……ルーフスラブ、3
……炉心、4……炉心上部機構、5……一次熱交
換器、6……冷却材循環ポンプ、7……冷却材、
8……炉心支持部材、9……回転プラグ、10…
…リングガータ、11……原子炉室、12……安
全容器、16……容器、17……流体ギヤツプ、
19……支持板。
FIG. 1 is a schematic vertical cross-sectional view showing a conventional tank-type nuclear reactor, and FIG. 2 is a schematic vertical cross-sectional view showing a tank-type nuclear reactor according to an embodiment of the present invention. 1...Reactor main vessel, 2...Roof slab, 3
... Core, 4 ... Core upper mechanism, 5 ... Primary heat exchanger, 6 ... Coolant circulation pump, 7 ... Coolant,
8... Core support member, 9... Rotating plug, 10...
...Ring gutter, 11...Reactor room, 12...Safety vessel, 16...Container, 17...Fluid gap,
19...Support plate.
Claims (1)
炉容器内の上記冷却材中に吊下げられた炉心支持
部材の下部に炉心を収容してなる原子炉におい
て、上記炉心支持部材における下部の側面および
底面を流体ギヤツプを介して覆うように設けられ
た容器と、この容器を前記原子炉容器に固定する
部材とを具備してなることを特徴とする原子炉。1. In a nuclear reactor that uses liquid metal as a coolant and has a reactor core housed in the lower part of a core support member suspended in the coolant in the reactor vessel, the side and bottom surfaces of the lower part of the core support member are 1. A nuclear reactor comprising: a container provided to cover the reactor via a fluid gap; and a member for fixing the container to the reactor container.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP59019873A JPS60165587A (en) | 1984-02-08 | 1984-02-08 | Nuclear reactor |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP59019873A JPS60165587A (en) | 1984-02-08 | 1984-02-08 | Nuclear reactor |
Publications (2)
Publication Number | Publication Date |
---|---|
JPS60165587A JPS60165587A (en) | 1985-08-28 |
JPH0131158B2 true JPH0131158B2 (en) | 1989-06-23 |
Family
ID=12011327
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP59019873A Granted JPS60165587A (en) | 1984-02-08 | 1984-02-08 | Nuclear reactor |
Country Status (1)
Country | Link |
---|---|
JP (1) | JPS60165587A (en) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPH0541495U (en) * | 1991-11-12 | 1993-06-08 | 積水化学工業株式会社 | Sanitary unit |
-
1984
- 1984-02-08 JP JP59019873A patent/JPS60165587A/en active Granted
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPH0541495U (en) * | 1991-11-12 | 1993-06-08 | 積水化学工業株式会社 | Sanitary unit |
Also Published As
Publication number | Publication date |
---|---|
JPS60165587A (en) | 1985-08-28 |
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