JPH10268078A - In-pile lower part structure of pressurized water reactor - Google Patents

In-pile lower part structure of pressurized water reactor

Info

Publication number
JPH10268078A
JPH10268078A JP9075905A JP7590597A JPH10268078A JP H10268078 A JPH10268078 A JP H10268078A JP 9075905 A JP9075905 A JP 9075905A JP 7590597 A JP7590597 A JP 7590597A JP H10268078 A JPH10268078 A JP H10268078A
Authority
JP
Japan
Prior art keywords
core
reactor vessel
plate
reactor
vessel body
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
Application number
JP9075905A
Other languages
Japanese (ja)
Inventor
Tsuyoshi Matsuoka
強 松岡
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Mitsubishi Heavy Industries Ltd
Original Assignee
Mitsubishi Heavy Industries Ltd
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by Mitsubishi Heavy Industries Ltd filed Critical Mitsubishi Heavy Industries Ltd
Priority to JP9075905A priority Critical patent/JPH10268078A/en
Publication of JPH10268078A publication Critical patent/JPH10268078A/en
Pending legal-status Critical Current

Links

Classifications

    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

PROBLEM TO BE SOLVED: To enable maintaining melt in the reactor vessel at the step before the progression of a core meltdown accident to a large scale by providing a multitude of ceramic member on the upper surface of lower head in the form without any adverse effects due to coolant flow in the lower plenum. SOLUTION: At the tip end of a lower core support column 31 extended downward from a lower core support plate 11, a lower connection plate 33 practically having no flow hole is horizontally supported. The surface shape of the lower connection plate 33 is circle and the outer edge is close to the inner surface of the lower head part 1a of the reactor vessel main body 1 with a narrow gap. In the space between the lower connection plate 33 and the upper surface of the lower head 1a, a ceramic form 35 is charged. The shape of the ceramic form 35 can be like particle, saddle or cylinder and the material is desired to have high temperature resistivity not to melt out at the coolant temperature during reactor operation. As the ceramic form 35 receives molten core, the lower head 1a is thermally protected and its melting penetration is prevented.

Description

【発明の詳細な説明】DETAILED DESCRIPTION OF THE INVENTION

【0001】[0001]

【発明の属する技術分野】本発明は、原子炉の構造に関
し、特に事故時に炉心構成物の溶融物を保持する機能を
備えた炉内下部構造に関する。
BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a structure of a nuclear reactor, and more particularly to a lower structure in a reactor having a function of holding a melt of core components in an accident.

【0002】[0002]

【従来の技術】図8及び図9に加圧水型原子炉の従来構
造の一例を示している。図において、原子炉容器本体1
は着脱自在の上部蓋3により上部開口が閉じられ、そこ
から炉心槽5が垂下支持されている。炉心槽5の下部に
は水平な下部炉心板7が支持され、炉心を構成する多数
の燃料集合体9がその上に並べられている。下部炉心板
7の下方には下部炉心支持板11が設けられていて、こ
れは原子炉容器本体1の内面から水平方向に支持されて
いるが、その下面に連結した下部炉心支持柱13が下部
連接板15と落下緩衝板17とに連絡している。更に下
部炉心支持板15に連結されて鉛直方向に延びた複数の
炉内計装案内管19が、原子炉容器本体1の下部鏡板部
に接続開口した炉内計装用導管に整列しており、これが
中間部で上部連接板21により互いに連接されている。
下部連接板15及び上部連接板21の平面形状は、特に
図9に示されるように、かなりの内部空間を形成するよ
うになっていて、そこを流れる冷却材に実質的な抵抗を
与えないようになっている。そして、原子炉の運転時に
おいて、冷却材は入口ノズル23を通って原子炉容器内
に流入し、環状下降空間25を流れ下り、下部プレナム
27内で流れ方向を反転し、下部炉心支持板11及び下
部炉心板7を通過して炉心に入り、燃料集合体9に接触
して加熱されつつ上昇し、上部プレナム28で流れ方向
を横向とし、出口ノズル29を通って流出する。
2. Description of the Related Art FIGS. 8 and 9 show an example of a conventional structure of a pressurized water reactor. In the figure, the reactor vessel main body 1
The upper opening is closed by a detachable upper lid 3, from which the core vessel 5 is supported by hanging. A horizontal lower core plate 7 is supported below the core tank 5, and a number of fuel assemblies 9 constituting the core are arranged thereon. A lower core support plate 11 is provided below the lower core plate 7 and is horizontally supported from the inner surface of the reactor vessel main body 1. A lower core support column 13 connected to a lower surface of the lower core support plate 11 is provided below the lower core support plate 11. It is connected to the connecting plate 15 and the drop buffer plate 17. Further, a plurality of in-core instrumentation guide tubes 19 connected to the lower core support plate 15 and extending in the vertical direction are aligned with the in-core instrumentation conduits connected and opened to the lower end plate portion of the reactor vessel main body 1. These are connected to each other by an upper connecting plate 21 at an intermediate portion.
The planar shape of the lower connecting plate 15 and the upper connecting plate 21 is designed to form a considerable internal space, as shown in particular in FIG. 9, so that there is no substantial resistance to the coolant flowing therethrough. It has become. During operation of the reactor, the coolant flows into the reactor vessel through the inlet nozzle 23, flows down the annular descending space 25, reverses the flow direction in the lower plenum 27, and Then, it passes through the lower core plate 7 and enters the core, rises while being heated while being in contact with the fuel assembly 9, flows laterally in the upper plenum 28, and flows out through the outlet nozzle 29.

【0003】[0003]

【発明が解決しようとする課題】上述の加圧水型原子炉
において、重大事故時には炉心の核反応熱が十分に除去
されずに一部が溶融して落下する惧れがある。従来の設
計思想では、原子炉容器の外の直下にコアキャッチャー
と称する溶融炉心受け設備を設け、溶融炉心が原子炉容
器を溶かして貫通落下した場合にはこれを受けて冷却す
ることとしていた。このようにして、炉心熔融事故が生
じても最終的にはコアキャッチャーで冷却されて安全が
確保されるが、溶融炉心による原子炉容器の貫通を防止
して事故の進行を阻止する機能に欠けるきらいがあっ
た。従って、本発明は、炉心溶融事故が大規模に進行し
ない段階で溶融物を原子炉容器内に保持できるようにし
た加圧水型原子炉の炉内下部構造を提供することを課題
とする。
In the above-mentioned pressurized water reactor, at the time of a serious accident, the nuclear reaction heat of the reactor core may not be sufficiently removed and a part of the reactor may melt and fall. According to the conventional design concept, a molten core receiving facility called a core catcher is provided directly below the reactor vessel, and when the molten core melts down the reactor vessel and falls through, the vessel is cooled in response thereto. In this way, even if a core melting accident occurs, the core is finally cooled by the core catcher to ensure safety, but lacks the function of preventing the penetration of the reactor vessel by the molten core and preventing the progress of the accident. I hate it. Accordingly, it is an object of the present invention to provide a reactor internal lower structure of a pressurized water reactor capable of holding a melt in a reactor vessel at a stage where a core melting accident does not proceed on a large scale.

【0004】[0004]

【課題を解決するための手段】如上の課題を解決するた
め、本発明によれば、開閉自在の上部蓋により上部開口
が閉じられた原子炉容器本体、この原子炉容器本体内に
上部開口から垂下支持され且つ原子炉容器本体と協働し
て冷却材の環状下降空間を画成する炉心槽、この炉心槽
の下部に展延支持された下部炉心板、この下部炉心板上
に形成された炉心及び前記下部炉心板の下方に位置して
前記炉心槽の下端部に連結支持された下部炉心支持板を
有し、その原子炉容器本体の下部鏡板部と前記下部炉心
支持板との間に前記環状下降空間に連通した下部プレナ
ムを画成している加圧水型原子炉において、炉内下部構
造は、下部プレナム内の冷却材の流れによって悪影響を
受けない態様で下部鏡板部の上面に多数のセラミック部
材を設けたことを特徴とする。好適には、セラミック部
材の上面を覆って下部プレナム内の冷却材流から隔離す
る円板を下部炉心支持板から垂下支持して構成され、或
いは下部鏡板部の上部内周面に外周縁が連結固定された
仕切円板を設け、下部鏡板部と仕切円板との間に多数の
セラミック部材を充填して構成される。そして、前者の
好適例において、原子炉容器の下部鏡板部に炉内計装用
導管が接続される原子炉では、その導管の内側延長部が
セラミック部材間を延びて前記円板の下面に臨んで開口
するように構成される。
According to the present invention, in order to solve the above problems, according to the present invention, a reactor vessel body having an upper opening closed by an openable / closable upper lid, and a reactor vessel body having an upper opening formed therein. A core vessel that is suspended and defines an annular descent space for the coolant in cooperation with the reactor vessel body, a lower core plate that is extended and supported below the core vessel, and formed on the lower core plate; A lower core support plate which is located below the core and the lower core plate and is connected to and supported by a lower end portion of the core vessel, between a lower head portion of the reactor vessel body and the lower core support plate; In a pressurized water reactor defining a lower plenum communicating with the annular descending space, the lower structure in the reactor has a plurality of upper surfaces on a lower end plate portion in a manner not adversely affected by a flow of coolant in the lower plenum. That the ceramic member was provided And butterflies. Preferably, a disk that covers the upper surface of the ceramic member and is isolated from the coolant flow in the lower plenum is suspended from the lower core support plate, or the outer peripheral edge is connected to the upper inner peripheral surface of the lower head plate portion. A fixed partition disk is provided, and a number of ceramic members are filled between the lower end plate portion and the partition disk. In the former preferred embodiment, in a nuclear reactor in which an in-core instrumentation conduit is connected to a lower head portion of the reactor vessel, an inner extension of the conduit extends between the ceramic members and faces the lower surface of the disk. It is configured to open.

【0005】[0005]

【発明の実施の形態】以下添付の図面を参照して、本発
明の実施形態を説明する。なお、前述の図8及び図9を
含む全図に亙り、同一部分には同一の符号を付し、発明
の内容の理解を容易化を図っている。図1を参照する
に、原子炉容器本体1は着脱自在の上部蓋3により上部
開口が閉じられ、そこから炉心槽5が垂下支持されてい
る。原子炉容器本体1の上方側部には、通常2乃至4個
の入口ノズル23が一体的に形成され、同数の出口ノズ
ル29が同様に一体的に形成されている。そして炉心槽
5と原子炉容器本体1の内面との間に環状下降空間25
が画成され、入口ノズル23がこれに開口している。更
に、炉心槽5の下部には水平な下部炉心板7が支持さ
れ、炉心を構成する多数の燃料集合体9(1体のみ図示
されている。)がその上に並べられて装荷される。下部
炉心板7の下方には炉心槽5の下端部に連結して下部炉
心支持板11が設けられていて、これらは原子炉容器本
体1の内面から水平方向に支持されている。一方、燃料
集合体9の上端は、上部炉心板8により押さえられ、上
部炉心支持板12が上部炉心板8を支持している。
Embodiments of the present invention will be described below with reference to the accompanying drawings. The same reference numerals are given to the same parts throughout all the drawings including FIGS. 8 and 9 to facilitate understanding of the contents of the invention. Referring to FIG. 1, an upper opening of a reactor vessel main body 1 is closed by a detachable upper lid 3, from which a reactor core vessel 5 is supported by hanging. Usually, two to four inlet nozzles 23 are integrally formed on the upper side of the reactor vessel main body 1, and the same number of outlet nozzles 29 are also integrally formed. An annular descending space 25 is provided between the core tank 5 and the inner surface of the reactor vessel main body 1.
And an inlet nozzle 23 is open to it. Further, a horizontal lower core plate 7 is supported at a lower portion of the core tank 5, and a number of fuel assemblies 9 (only one is shown) constituting the core are arranged and loaded thereon. A lower core support plate 11 is provided below the lower core plate 7 and connected to a lower end portion of the core tank 5, and these are horizontally supported from the inner surface of the reactor vessel main body 1. On the other hand, the upper end of the fuel assembly 9 is pressed by the upper core plate 8, and the upper core support plate 12 supports the upper core plate 8.

【0006】そして、本発明の特徴的部分について更に
説明すると、下部炉心支持板11から複数の下部炉心支
持柱31が下方に向かって延出し、その先端に実質的に
流れ穴の無い円板即ち下部連接板33が水平に支持され
ている。下部連接板33の平面形状は図2に示すように
円形であり、その外周縁は、原子炉容器本体1の下部鏡
板部1aの内周面に狭い間隔で近接している。そして、
下部連接板33と下部鏡板部1aの上面との間のセグメ
ント空間内に、セラミック成形体35が敷き詰め、充填
されている。セラミック成形体35の形状は、粒状、鞍
状、円筒状等適宜なものでよく、材質的には原子炉運転
時の冷却材温度において、溶出しないような高温耐熱性
があればよく、数種類の材質のものを混合して使用して
もよい。尚、上部連接板37は、図3に示すような略環
状の形状をしている。
Further, the characteristic portion of the present invention will be further described. A plurality of lower core support columns 31 extend downward from the lower core support plate 11, and a disk having substantially no flow hole at the tip thereof, that is, a disk having no flow hole. The lower connecting plate 33 is supported horizontally. The planar shape of the lower connecting plate 33 is circular as shown in FIG. 2, and the outer peripheral edge thereof is close to the inner peripheral surface of the lower end plate 1 a of the reactor vessel main body 1 at a narrow interval. And
In a segment space between the lower connecting plate 33 and the upper surface of the lower end plate portion 1a, a ceramic molded body 35 is spread and filled. The shape of the ceramic molded body 35 may be an appropriate one such as a granular shape, a saddle shape, a cylindrical shape, and the material may be any material as long as it has high-temperature heat resistance so as not to elute at a coolant temperature during operation of the reactor. A mixture of materials may be used. The upper connecting plate 37 has a substantially annular shape as shown in FIG.

【0007】上述の炉心構造の加圧水型原子炉におい
て、通常運転時には、冷却材は入口ノズル23を通って
原子炉容器本体1内に流入し、環状下降空間25を流れ
下り、下部プレナム27内で流れ方向を反転し、下部炉
心支持板11及び下部炉心板7を通過して炉心に入り、
燃料集合体9に接触して加熱されつつ上昇し、上部プレ
ナム28内で流れ方向を横向とし、出口ノズル29を通
って流出する。そして、環状下降空間25から下部プレ
ナム27に流入した冷却材は、低部の下部連接板33の
上面に衝突して向きを変えるが、セラミック成形体35
の層の上面は実質的に蓋をされた形になっているので、
冷却材流からは何の悪影響も受けない。そして、事故に
より燃料集合体9の一部が溶融したときは、重力により
下部炉心板7及び下部炉心支持板11の穴を通って落下
するが、セラミック成形体35により受け止められ、原
子炉容器本体1の下部鏡板部1aへの伝熱は緩和され、
長期に亙り或いは次の安全確保動作が行われるまで、そ
の健全性が保持される。
In the pressurized water reactor having the above-described core structure, during normal operation, the coolant flows into the reactor vessel main body 1 through the inlet nozzle 23, flows down the annular descending space 25, and falls in the lower plenum 27. The flow direction is reversed, passes through the lower core support plate 11 and the lower core plate 7 and enters the core,
The fuel flows upward while being heated in contact with the fuel assembly 9, flows laterally in the upper plenum 28, and flows out through the outlet nozzle 29. The coolant flowing into the lower plenum 27 from the annular descending space 25 collides with the upper surface of the lower lower connecting plate 33 and changes its direction.
Since the top surface of the layer is substantially covered,
There is no adverse effect from the coolant flow. When a part of the fuel assembly 9 is melted due to an accident, the fuel assembly 9 falls through the holes of the lower core plate 7 and the lower core support plate 11 due to gravity, but is received by the ceramic molded body 35, 1, the heat transfer to the lower end plate 1a is reduced,
The soundness is maintained for a long time or until the next safety operation is performed.

【0008】尚、原子炉の型式によっては炉心の中性子
束を検出する炉内検出器等を案内する炉内計装用導管が
原子炉容器本体1の下部鏡板部1aに接続される場合が
ある。このような型式の原子炉に本発明を適用するに
は、図4乃至図6に示す実施形態となる。これを説明す
るに、図4において下部炉心支持板11から下方に延出
した下部炉心支持柱41の下端に下部連接板43が水平
に支持されている。下部連接板43の平面形状は図5に
示されているが、前述の図2に示された下部連接板31
とは、後述するように炉内計装案内管が取り付けられる
点で異なっている。即ち、原子炉容器本体1の下部鏡板
部1aを水密に貫通した炉内計装用導管48の上端が下
部連接板43の下面近傍まで延び、その対応する穴に臨
んで開口している。この炉内計装用導管48に整列して
炉内計装案内管49の下端が下部連接板43に固定され
ている。一方、炉内計装案内管49の上端が下部炉心支
持板11の下面に固定され、下部連接板43の上方に位
置する上部連接板47が複数の炉内計装案内管49を互
いに連結している。上部連接板47の平面形状が図6に
示されている。そして、前述の実施形態と同様のセラミ
ック成形体45が下部連接板43と下部鏡板部1aとの
間に充填されている。以上、変更部分についてのみ説明
したが、上述以外の構成は第1の実施形態の場合と同様
であるので、本実施形態においても前述の実施形態と同
様の作用効果が得られる。
Depending on the type of the reactor, an in-core instrumentation conduit for guiding an in-reactor detector for detecting a neutron flux of the core may be connected to the lower head 1a of the reactor vessel body 1. In order to apply the present invention to a reactor of this type, the embodiment shown in FIGS. To explain this, a lower connecting plate 43 is horizontally supported at a lower end of a lower core support column 41 extending downward from the lower core support plate 11 in FIG. The plan shape of the lower connecting plate 43 is shown in FIG. 5, but the lower connecting plate 31 shown in FIG.
Is different in that an in-furnace instrumentation guide tube is attached as described later. In other words, the upper end of the in-core instrumentation conduit 48 that penetrates the lower end plate portion 1a of the reactor vessel body 1 in a water-tight manner extends to near the lower surface of the lower connecting plate 43, and opens to the corresponding hole. The lower end of the in-furnace instrumentation guide tube 49 is fixed to the lower connecting plate 43 in line with the in-furnace instrumentation conduit 48. On the other hand, the upper end of the in-core instrumentation guide tube 49 is fixed to the lower surface of the lower core support plate 11, and the upper connecting plate 47 located above the lower connecting plate 43 connects the plurality of in-core instrumentation guide tubes 49 to each other. ing. FIG. 6 shows a plan shape of the upper connecting plate 47. Then, a ceramic molded body 45 similar to that of the above-described embodiment is filled between the lower connecting plate 43 and the lower end plate portion 1a. As described above, only the changed part has been described. However, since the configuration other than the above is the same as that of the first embodiment, the same effects as those of the above-described embodiment can be obtained in this embodiment.

【0009】更に別の実施形態について説明する。図7
を参照して前述の第1及び第2の実施形態と異なる部分
のみ説明すると、下部炉心支持板11の下方には下部連
接板や上部連接板がなく、皿状の仕切円板53が下部鏡
板部1aの上部内周面に密接して固定され、仕切円板5
3と下部鏡板部1aとの間に前述と同様なセラミック成
形体55が充填されている。このような炉内下部構造に
おいても、下部プレナム51が環状下降空間25に連通
しているので、正常運転時の冷却材の流れには大差がな
く、事故時に溶融炉心を受け止めて原子炉容器本体1の
下部鏡板部1aを溶融、貫通から保護するという本発明
の作用が得られる。
Another embodiment will be described. FIG.
Only the portions different from the above-described first and second embodiments will be described with reference to FIG. 6. There is no lower connecting plate or upper connecting plate below the lower core support plate 11, and the dish-shaped partitioning disk 53 is a lower head plate. The partition disk 5 is fixed in close contact with the upper inner peripheral surface of the portion 1a.
A ceramic molded body 55 similar to that described above is filled between the lower end plate 3 and the lower end plate portion 1a. Even in such a lower structure inside the reactor, since the lower plenum 51 communicates with the annular descending space 25, there is no large difference in the flow of the coolant during the normal operation. The effect of the present invention of protecting the lower end plate portion 1a from melting and penetration can be obtained.

【0010】[0010]

【発明の効果】以上説明したように、本発明によれは、
原子炉容器本体の下部鏡板部の上面に敷き詰めたセラミ
ック成形体が溶融炉心を受け止めるので、その下部鏡板
部を熱的に保護し、その溶融貫通を防止することができ
る。更に本発明によれば、前述のセラミック成形体を下
部連接板のような円板又は仕切円板により冷却材流から
隔離して長期にわたってその機能を保持し、溶融炉心が
落下して来れば、これを前述のように受け止めて原子炉
容器の溶融貫通を防止することができる。
As described above, according to the present invention,
Since the ceramic molded body spread over the upper surface of the lower head portion of the reactor vessel main body receives the molten core, the lower head portion can be thermally protected and its penetration through the melt can be prevented. Furthermore, according to the present invention, if the above-mentioned ceramic molded body is separated from the coolant flow by a disk such as a lower connecting plate or a partition disk and retains its function for a long time, and the molten core falls, By receiving this as described above, it is possible to prevent melt penetration of the reactor vessel.

【図面の簡単な説明】[Brief description of the drawings]

【図1】本発明の実施形態を示す立断面図である。FIG. 1 is an elevational sectional view showing an embodiment of the present invention.

【図2】図1のII−II線に沿う平断面図である。FIG. 2 is a plan sectional view taken along the line II-II in FIG.

【図3】図1のIII−III線に沿う平断面図である。FIG. 3 is a plan sectional view taken along the line III-III of FIG. 1;

【図4】本発明の別の実施形態を示す立断面図である。FIG. 4 is an elevational sectional view showing another embodiment of the present invention.

【図5】図4のV−V線に沿う平断面図である。FIG. 5 is a plan sectional view taken along the line VV of FIG. 4;

【図6】図4のVI−VI線に沿う平断面図である。6 is a plan sectional view taken along the line VI-VI in FIG. 4;

【図7】本発明の更に別の実施形態を示す立断面図であ
る。
FIG. 7 is an elevational sectional view showing still another embodiment of the present invention.

【図8】従来の加圧水型原子炉の炉内構造の一例を示す
立断面図である。
FIG. 8 is a vertical sectional view showing an example of the internal structure of a conventional pressurized water reactor.

【図9】図8のIX−IX線に沿う平断面図である。FIG. 9 is a plan sectional view taken along line IX-IX of FIG. 8;

【符号の説明】[Explanation of symbols]

1 原子炉容器本体 1a 下部鏡板部 3 上部蓋 5 炉心槽 7 下部炉心板 8 上部炉心板 9 燃料集合体 11 下部炉心支持板 12 上部炉心支持板 23 入口ノズル 25 環状下降空間 27 下部プレナム 28 上部プレナム 29 出口ノズル 31 下部炉心支持柱 33 下部連接板 35 セラミック成形体 37 上部連接板 41 下部炉心支持柱 43 下部連接板 45 セラミック成形体 47 上部連接板 48 炉内計装用導管 49 炉内計装案内管 51 下部プレナム 53 仕切円板 55 セラミック成形体 DESCRIPTION OF SYMBOLS 1 Reactor vessel main body 1a Lower head plate part 3 Upper lid 5 Core tank 7 Lower core plate 8 Upper core plate 9 Fuel assembly 11 Lower core support plate 12 Upper core support plate 23 Inlet nozzle 25 Annular descending space 27 Lower plenum 28 Upper plenum 29 Outlet nozzle 31 Lower core support column 33 Lower connecting plate 35 Ceramic molded body 37 Upper connecting plate 41 Lower core supporting column 43 Lower connecting plate 45 Ceramic molded body 47 Upper connecting plate 48 In-core instrumentation conduit 49 In-core instrumentation guide tube 51 Lower plenum 53 Partition disk 55 Ceramic molded body

Claims (4)

【特許請求の範囲】[Claims] 【請求項1】 開閉自在の上部蓋により上部開口が閉じ
られた原子炉容器本体、同原子炉容器本体内に前記上部
開口から垂下支持され、該原子炉容器本体と協働して冷
却材の環状下降空間を画成する炉心槽、同炉心槽の下部
に展延支持された下部炉心板、同下部炉心板上に形成さ
れた炉心、及び前記下部炉心板の下方に位置して前記炉
心槽の下端部に連結支持された下部炉心支持板を有し、
前記原子炉容器本体の下部鏡板部と前記下部炉心支持板
との間に前記環状下降空間に連通した下部プレナムを画
成している加圧水型原子炉において、前記下部鏡板部の
上面に多数のセラミック部材を敷き詰めたことを特徴と
する加圧水型原子炉の炉内下部構造。
1. A reactor vessel body whose upper opening is closed by an openable and closable upper lid. The reactor vessel body is suspended from the upper opening in the reactor vessel body, and the coolant is cooperated with the reactor vessel body. A core tank defining an annular descending space, a lower core plate extended and supported below the core tank, a core formed on the lower core plate, and the core tank positioned below the lower core plate Having a lower core support plate connected and supported at the lower end of the
In a pressurized water reactor having a lower plenum communicating with the annular descending space between a lower head plate portion of the reactor vessel body and the lower core support plate, a large number of ceramics are formed on an upper surface of the lower head plate portion. Lower part structure of a pressurized water reactor, characterized by laying down members.
【請求項2】 前記セラミック部材の上面を覆って前記
下部プレナム内の冷却材流から隔離する円板を前記下部
炉心支持板から垂下支持したことを特徴とする請求項1
記載の加圧水型原子炉の炉内下部構造。
2. A disk supporting an upper surface of said ceramic member and separating from a coolant flow in said lower plenum is supported by said lower core support plate.
The lower inside structure of the pressurized water reactor described in the above.
【請求項3】 前記原子炉容器本体の下部鏡板部に接続
する炉内計装用導管の内側延長部が前記セラミック部材
間を延びて前記円板の下面に臨んで開口していることを
特徴とする請求項2記載の加圧水型原子炉の炉内下部構
造。
3. An in-core extension of an in-core instrumentation conduit connected to a lower head portion of the reactor vessel main body extends between the ceramic members and opens to a lower surface of the disk. The lower part structure of the pressurized water reactor according to claim 2.
【請求項4】 開閉自在の上部蓋により上部開口が閉じ
られた原子炉容器本体、同原子炉容器本体内に前記上部
開口から垂下支持され、該原子炉容器本体と協働して冷
却材の環状下降空間を画成する炉心槽、同炉心槽の下部
に展延支持された下部炉心板、同下部炉心板上に形成さ
れた炉心、及び前記下部炉心板の下方に位置して前記炉
心槽の下端部に連結支持された下部炉心支持板を有し、
前記原子炉容器本体の下部鏡板部と前記下部炉心支持板
との間に前記環状下降空間に連通した下部プレナムを画
成している加圧水型原子炉において、前記下部鏡板部の
上部内周面に外周縁が連結固定された仕切円板を設け、
前記下部鏡板部と前記仕切円板との間に多数のセラミッ
ク部材を充填してなることを特徴とする加圧水型原子炉
の炉内下部構造。
4. A reactor vessel body whose upper opening is closed by an openable and closable upper lid, the reactor vessel body is suspended from the upper opening in the reactor vessel body, and the coolant is cooperated with the reactor vessel body. A core tank defining an annular descending space, a lower core plate extended and supported below the core tank, a core formed on the lower core plate, and the core tank positioned below the lower core plate Having a lower core support plate connected and supported at the lower end of the
In a pressurized water reactor having a lower plenum communicating with the annular descending space between a lower head portion of the reactor vessel body and the lower core support plate, an upper inner peripheral surface of the lower head portion is provided. Provide a partition disk whose outer peripheral edge is connected and fixed,
A lower inside structure of a pressurized water reactor, wherein a plurality of ceramic members are filled between the lower end plate portion and the partition disk.
JP9075905A 1997-03-27 1997-03-27 In-pile lower part structure of pressurized water reactor Pending JPH10268078A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP9075905A JPH10268078A (en) 1997-03-27 1997-03-27 In-pile lower part structure of pressurized water reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP9075905A JPH10268078A (en) 1997-03-27 1997-03-27 In-pile lower part structure of pressurized water reactor

Publications (1)

Publication Number Publication Date
JPH10268078A true JPH10268078A (en) 1998-10-09

Family

ID=13589828

Family Applications (1)

Application Number Title Priority Date Filing Date
JP9075905A Pending JPH10268078A (en) 1997-03-27 1997-03-27 In-pile lower part structure of pressurized water reactor

Country Status (1)

Country Link
JP (1) JPH10268078A (en)

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
KR100436978B1 (en) * 2001-11-15 2004-06-23 한국수력원자력 주식회사 The Reactor cavity geometric structure of nuclear power plant
JP2016003908A (en) * 2014-06-16 2016-01-12 株式会社東芝 Reactor bottom protection structure of nuclear reactor pressure vessel
JP2016145785A (en) * 2015-02-09 2016-08-12 三菱重工業株式会社 Reactor core internal structure assembly adjustment device and assembly method

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
KR100436978B1 (en) * 2001-11-15 2004-06-23 한국수력원자력 주식회사 The Reactor cavity geometric structure of nuclear power plant
JP2016003908A (en) * 2014-06-16 2016-01-12 株式会社東芝 Reactor bottom protection structure of nuclear reactor pressure vessel
JP2016145785A (en) * 2015-02-09 2016-08-12 三菱重工業株式会社 Reactor core internal structure assembly adjustment device and assembly method

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