JPH01142496A - Nuclear reactor vessel - Google Patents
Nuclear reactor vesselInfo
- Publication number
- JPH01142496A JPH01142496A JP62300234A JP30023487A JPH01142496A JP H01142496 A JPH01142496 A JP H01142496A JP 62300234 A JP62300234 A JP 62300234A JP 30023487 A JP30023487 A JP 30023487A JP H01142496 A JPH01142496 A JP H01142496A
- Authority
- JP
- Japan
- Prior art keywords
- reactor vessel
- vessel
- reactor
- nuclear reactor
- buckling
- 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
- 238000001816 cooling Methods 0.000 claims 1
- 238000010008 shearing Methods 0.000 abstract 1
- 239000002826 coolant Substances 0.000 description 8
- 230000000694 effects Effects 0.000 description 3
- 230000008646 thermal stress Effects 0.000 description 3
- 238000003466 welding Methods 0.000 description 3
- 238000005192 partition Methods 0.000 description 2
- 230000002787 reinforcement Effects 0.000 description 2
- 239000000498 cooling water Substances 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 230000004992 fission Effects 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 239000012528 membrane Substances 0.000 description 1
- 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 1
- 230000000149 penetrating effect Effects 0.000 description 1
- 230000003014 reinforcing effect Effects 0.000 description 1
- 230000035882 stress Effects 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
- Micro-Organisms Or Cultivation Processes Thereof (AREA)
- Biological Treatment Of Waste Water (AREA)
- Treatment Of Biological Wastes In General (AREA)
- Purification Treatments By Anaerobic Or Anaerobic And Aerobic Bacteria Or Animals (AREA)
Abstract
Description
【発明の詳細な説明】
〔産業上の利用分野〕
本発明は、高速増殖炉（以下ＦＢＲと略す）の原子炉容
器に係り、特に、地震時に原子炉全体に作用するせん断
力により発生する原子炉容器の耐座屈強度を増すのに好
適な原子炉の構造に関する。[Detailed Description of the Invention] [Industrial Application Field] The present invention relates to a nuclear reactor vessel of a fast breeder reactor (hereinafter abbreviated as FBR), and in particular, the present invention relates to a nuclear reactor vessel of a fast breeder reactor (hereinafter abbreviated as FBR), and in particular, the present invention relates to a nuclear reactor vessel of a fast breeder reactor (hereinafter abbreviated as FBR). The present invention relates to a nuclear reactor structure suitable for increasing the buckling strength of a reactor vessel.
従来の構造について、スーパーフェニックスを例にとり
、第３図を用いて説明する。The conventional structure will be explained using FIG. 3, taking the Super Phoenix as an example.
原子炉容器１は、板厚が５０ｍ＋、直径２０ｍ程度の薄
肉容器原子炉−次冷却材１１及び炉内構造物を内包し、
ルーフスラブ構造３より直接溶接により吊り下げられて
いる。主要器内は、水平隔壁１４により冷却材が上部の
ホットプレナムと下部のコールドプレナムに分けられ、
炉心４は容器１の底の鎖部に設置する炉心支持構造物５
により支持されている。The reactor vessel 1 is a thin-walled vessel with a plate thickness of 50 m+ and a diameter of about 20 m, and contains the sub-reactor coolant 11 and reactor internals,
It is suspended from the roof slab structure 3 by direct welding. Inside the main vessel, the coolant is divided into an upper hot plenum and a lower cold plenum by a horizontal partition wall 14.
The core 4 has a core support structure 5 installed in the chain at the bottom of the vessel 1.
Supported by
ルーフスラブ強度部材は、軽量で、かつ、高剛性を確保
するためマルチセルボックスビーム構造で構成され、容
器１及び熱交換器８、ポンプ等の機器を塔載し、最外周
でルーフスラブ３の支持部によりペデスタルに設置しで
ある。ルーフスラブは軽量であるが剛性が大きいため、
地震に対しても十分な強度を持っている。The roof slab strength member is constructed of a multi-cell box beam structure to ensure lightweight and high rigidity, and carries the container 1, heat exchanger 8, pump and other equipment, and supports the roof slab 3 at the outermost periphery. Depending on the section, it is installed on the pedestal. Roof slabs are lightweight but have high rigidity, so
It has sufficient strength to withstand earthquakes.
炉心４は、十数枚の半径方向リブで構成された炉心支持
構造物５で支持されている。この各々のリブの内周部は
、中性子連へい体を収納する円筒容器に溶接で接続°さ
れ、外周部は容器鎖部に設置されるスカート構造１３に
溶接で接続される。The core 4 is supported by a core support structure 5 made up of more than ten radial ribs. The inner periphery of each rib is connected by welding to a cylindrical container housing the neutron shield, and the outer periphery is welded to a skirt structure 13 installed on the container chain.
次に地震の場合について述べる。水平地震時には、原子
炉容器１及び原子炉容器内部の炉心４など原子炉容器全
体に荷重が作用する。これに対して、原子炉容器１はル
ーフスラブ３の支持部で支持されることにより、原子炉
容器の上部が固定されて下部が振動する形となる。この
ため、原子炉容器上部にある炉心上機構６、熱交換器８
、及び、循環ポンプに作用する荷重は支持部に近いため
に、原子炉容器をあまり振動させないが、原子炉容器内
部の炉心４及び冷却水等に作用する荷重や原子炉容器本
体に作用する荷重は支持点から離れているために原子炉
容器を大きく振動させる。原子炉容器１は、この荷重に
耐えられるだけの剛性が必要とされる。Next, we will discuss the case of an earthquake. At the time of a horizontal earthquake, a load acts on the entire reactor vessel, including the reactor vessel 1 and the reactor core 4 inside the reactor vessel. On the other hand, the reactor vessel 1 is supported by the supporting portion of the roof slab 3, so that the upper part of the reactor vessel is fixed and the lower part vibrates. For this reason, the above-core mechanism 6 and heat exchanger 8 located at the top of the reactor vessel
, and the load acting on the circulation pump is close to the support part, so it does not cause the reactor vessel to vibrate much, but the load acting on the reactor core 4 and cooling water inside the reactor vessel, and the load acting on the reactor vessel body. Because it is far from the support point, it causes the reactor vessel to vibrate greatly. The reactor vessel 1 is required to have enough rigidity to withstand this load.
一方、原子炉容器１には高温の冷却材１１によって、熱
応力が発生するので、これを小さくするために板厚を小
さくすることも要求され、結果的に薄肉の構造となって
いる。On the other hand, since thermal stress is generated in the reactor vessel 1 by the high-temperature coolant 11, it is also required to reduce the plate thickness in order to reduce this stress, resulting in a thin structure.
図中、１６は垂直隔壁。In the figure, 16 is a vertical partition wall.
〔発明が解決しようとする問題点〕
上記従来構造は、水平地震時に、容器１の胴部が大きな
せん断力を受ける上に原子炉容器１が薄くなっているた
めに、せん断座屈が発生し易くなっている。また、容器
１の胴体には補強となるものが無いので結果的に容器胴
体１の剛性が小さく、せん断座屈に対する強度が低くな
っている。[Problems to be Solved by the Invention] In the above conventional structure, shear buckling occurs during a horizontal earthquake because the body of the vessel 1 receives a large shear force and the reactor vessel 1 is thin. It's getting easier. Further, since there is no reinforcement in the body of the container 1, the rigidity of the body 1 is low as a result, and the strength against shear buckling is low.
第２図に原子炉容器のせん断座屈をあられした図を示す
。原子炉容器に矢印Ａ方向にせん断荷重が作用した場合
、容器の円筒部には矢印Ｂの方向に膜力が働き、容器に
は図に示すように、いくつかの座屈波が生じる。これを
せん断座屈と呼んでいる。Figure 2 shows a diagram showing shear buckling of the reactor vessel. When a shear load is applied to the reactor vessel in the direction of arrow A, a membrane force acts on the cylindrical portion of the vessel in the direction of arrow B, and several buckling waves are generated in the vessel as shown in the figure. This is called shear buckling.
本発明の目的は、容器胴体１に加わるせん断力に対して
、熱応力の増加する容器板厚増加の方法を取らずに容器
の剛性を上げてせん断座屈に対する強度を上げることに
ある。An object of the present invention is to increase the rigidity of the container against shear buckling by increasing the rigidity of the container against the shear force applied to the container body 1 without increasing the thickness of the container, which increases thermal stress.
上記の目的は、タンク型ＦＢＲの原子炉構造において、
容器の胴部に斜めにリブを設けることによって達成され
る。The above purpose is to
This is achieved by providing diagonal ribs on the body of the container.
本発明の原子炉構造において水平方向に地震が作用した
場合、原子炉容器の上部の構造物、容器内部の構造物、
及び、容器本体等、原子炉容器全体に荷重が作用し、原
子炉容器１がルーフスラブ３の支持部で支持されること
により、原子炉容器１の上部が固定されて下部が容器内
部、及び、容器本体の荷重を受けて振動する。この時の
座屈はせん断座屈となり、容器胴体に斜めの座屈波が生
じる。よって、容器胴体に斜めにリブを溶接し、座屈波
の発生を抑えることにより、原子炉容器の耐座屈強度を
向上させる。When an earthquake acts in the horizontal direction on the reactor structure of the present invention, the structures above the reactor vessel, the structures inside the vessel,
Then, a load acts on the entire reactor vessel, such as the vessel body, and the reactor vessel 1 is supported by the supporting part of the roof slab 3, so that the upper part of the reactor vessel 1 is fixed and the lower part is inside the vessel, and , vibrates under the load of the container body. The buckling at this time becomes shear buckling, and oblique buckling waves are generated in the container body. Therefore, by diagonally welding ribs to the vessel body to suppress the generation of buckling waves, the buckling strength of the reactor vessel is improved.
以下１本発明の一実施例を第１図により説明する。第１
図は原子炉本体の縦断面図である。An embodiment of the present invention will be described below with reference to FIG. 1st
The figure is a longitudinal cross-sectional view of the reactor main body.
図において、１は原子炉容器、２は安全容器、３は原子
炉容器蓋、４は炉心、６は炉心上部機構、７は制御棒駆
動機構、８は熱交換器、９は循環ポンプ、１０は配管、
１２は原子炉建屋、１７はリブである。In the figure, 1 is a reactor vessel, 2 is a safety vessel, 3 is a reactor vessel lid, 4 is a reactor core, 6 is a core upper mechanism, 7 is a control rod drive mechanism, 8 is a heat exchanger, 9 is a circulation pump, 10 is piping,
12 is a reactor building, and 17 is a rib.
原子炉容器１と原子炉容器１の外側に設けられた安全容
器２は原子炉容器蓋３に取り付けられている。原子炉容
器１内には炉心４が設けられ炉心４は炉心支持構造（図
示せず）を介し、原子炉容器１に取り付けられている。A reactor vessel 1 and a safety vessel 2 provided outside the reactor vessel 1 are attached to a reactor vessel lid 3. A reactor core 4 is provided within the reactor vessel 1, and the reactor core 4 is attached to the reactor vessel 1 via a core support structure (not shown).
また、原子炉容器蓋３を貫通して炉心上部機構６が設け
られており、炉心上部機構６には制御棒駆動機構７が設
けられている。制御棒駆動機構７によって制御棒（図示
せず）が炉心４内に対し、挿入、引き抜きが行われ出力
が制御されるようになっている。Further, a core upper mechanism 6 is provided passing through the reactor vessel lid 3, and a control rod drive mechanism 7 is provided in the core upper mechanism 6. A control rod drive mechanism 7 inserts and withdraws a control rod (not shown) into the reactor core 4, thereby controlling the output.
また、原子炉容器蓋３を貫通して熱交換器８と循環ポン
プ９が設けられており、熱交換器８の上部には熱を原子
炉容器１の外に導く配管１０が設けられ、配管１０には
原子炉建屋１２側と熱交換器８側との間がフレキシブル
構造（図示せず）に接続されており、互いに独立に動く
ことができるようになっている。また、炉心４と炉心支
持構造５は冷却材（図示せず）中に浸漬され、熱交換器
８、循環ポンプ９及び炉心上部機構６は下部を冷却材中
に浸漬されている。炉心４内で核分裂によって生じた熱
により加熱された冷却材は炉心４の上面から原子炉容器
１の中を上部に流れ、熱交換器８内に流入し熱交換して
いる。そして、熱交換により低温となった冷却材は熱交
換器８の下部から原子炉容器１内の下部に流出し循環ポ
ンプ９によって炉心４の下部に送られる。Further, a heat exchanger 8 and a circulation pump 9 are provided penetrating the reactor vessel lid 3, and a pipe 10 is provided above the heat exchanger 8 to guide heat to the outside of the reactor vessel 1. 10 has a flexible structure (not shown) connected between the reactor building 12 side and the heat exchanger 8 side so that they can move independently of each other. Further, the core 4 and the core support structure 5 are immersed in a coolant (not shown), and the lower portions of the heat exchanger 8, circulation pump 9, and core upper mechanism 6 are immersed in the coolant. The coolant heated by the heat generated by nuclear fission in the reactor core 4 flows from the upper surface of the reactor core 4 upwards in the reactor vessel 1, and flows into the heat exchanger 8 for heat exchange. The coolant whose temperature has become low due to the heat exchange flows out from the lower part of the heat exchanger 8 to the lower part of the reactor vessel 1 and is sent to the lower part of the reactor core 4 by the circulation pump 9.
容器１の胴部には、斜めのＶ形状のリブ１７が円周上に
一周設けられており、これにより容器１は斜め方向に補
強がなされている。A diagonal V-shaped rib 17 is provided around the circumference of the body of the container 1, thereby reinforcing the container 1 in the diagonal direction.
第２図に、リブ１７の詳細図を示す。このようにリブ１
７が設けられているので、容器の斜め方向の力に対して
剛な補強となっている。FIG. 2 shows a detailed view of the rib 17. Like this rib 1
7 provides rigid reinforcement against forces in the diagonal direction of the container.
本発明はこのように構成されているので、以下に示す作
用がある。Since the present invention is configured as described above, it has the following effects.
すなわち、地震が発生し、本原子炉構造に水平方向地震
荷重が作用した場合、原子炉容器上部の構造物、容器内
部の構造物及び容器本体等、原子炉容器全体に荷重が作
用し、原子炉容器１がルーフスラブ３の支持部で支持さ
れることにより、原子炉容器１の上部が固定されて下部
が容器内部、及び、容器本体の荷重を受けて振動する。In other words, when an earthquake occurs and a horizontal seismic load acts on the reactor structure, the load acts on the entire reactor vessel, including the structure on the top of the reactor vessel, the structure inside the vessel, and the vessel itself, causing nuclear damage. Since the reactor vessel 1 is supported by the supporting portion of the roof slab 3, the upper part of the reactor vessel 1 is fixed, and the lower part vibrates under the load of the inside of the vessel and the vessel body.
この際、容器の周部に斜め方向に力が生じるのに対して
、斜めのリブを円周上に一周設けるので、斜め方向の剛
性を大きくすることができ、これによって、せん断座屈
が生じるのを防ぐことができる。At this time, a force is generated in a diagonal direction around the periphery of the container, but since diagonal ribs are provided all around the circumference, the rigidity in the diagonal direction can be increased, which causes shear buckling. can be prevented.
このように、リブを容器のせん断座屈に対して有効な形
で設けているので、地震に対して高い安全性をもたせる
ことができる。In this way, since the ribs are provided in a form that is effective against shear buckling of the container, high safety against earthquakes can be provided.
従って、本発明によれば、地震時に発生するせん断力に
対して、容器の剛性が大きくなっているのでせん断座屈
の発生を防ぐことができる。Therefore, according to the present invention, the rigidity of the container is increased against the shear force generated during an earthquake, so that shear buckling can be prevented from occurring.
また、原子炉容器１は高温の冷却材によって生じる熱応
力を少なくするために、板厚を薄くする必要があるが、
胴部に設けるリブによって有効に補強されるので、現在
の板厚よりも薄くしても座屈に対して強度を確保できる
ので、材料費の低減を図ることができる。In addition, the reactor vessel 1 needs to be made thinner in order to reduce the thermal stress caused by the high-temperature coolant.
Since it is effectively reinforced by the ribs provided on the body, it is possible to ensure strength against buckling even if the thickness of the plate is thinner than the current thickness, so material costs can be reduced.
本発明によれば、容器の剛性が高まり、座屈を発生しに
くくすることができる。According to the present invention, the rigidity of the container can be increased and buckling can be made less likely to occur.
第１図は本発明の一実施例の原子炉構造の正面図、第２
図は本発明によるリブの斜視図、第３図は従来の原子炉
構造の縦断面図、第４図は原子炉容器のせん断座屈を表
わす斜視図である。
１・・・原子炉容器、２・・・安全容器、３・・・原子
炉容器蓋、４・・・炉心、５・・・炉心支持構造、６・
・・炉心上部機構、７・・・制御棒駆動機構、８・・・
熱交換器。
菖 Ｉ の
下 ２ 口
冨 Ｊｅ！］Figure 1 is a front view of a nuclear reactor structure according to an embodiment of the present invention;
3 is a perspective view of a rib according to the present invention, FIG. 3 is a longitudinal sectional view of a conventional nuclear reactor structure, and FIG. 4 is a perspective view showing shear buckling of a reactor vessel. DESCRIPTION OF SYMBOLS 1... Reactor vessel, 2... Safety vessel, 3... Reactor vessel lid, 4... Reactor core, 5... Core support structure, 6...
... Core upper mechanism, 7... Control rod drive mechanism, 8...
Heat exchanger. Under Iris I 2 Kuchifu Je! ]
Claims (1)
型の原子炉容器において、 前記原子炉容器の円筒部に斜めのリブを設けたことを特
徴とする原子炉容器。[Scope of Claims] 1. A fast breeder reactor tank-type nuclear reactor vessel including a reactor core and primary cooling system equipment, characterized in that a diagonal rib is provided on a cylindrical portion of the reactor vessel.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP62300234A JPH01142496A (en) | 1987-11-30 | 1987-11-30 | Nuclear reactor vessel |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP62300234A JPH01142496A (en) | 1987-11-30 | 1987-11-30 | Nuclear reactor vessel |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH01142496A true JPH01142496A (en) | 1989-06-05 |
Family
ID=17882326
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP62300234A Pending JPH01142496A (en) | 1987-11-30 | 1987-11-30 | Nuclear reactor vessel |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH01142496A (en) |
-
1987
- 1987-11-30 JP JP62300234A patent/JPH01142496A/en active Pending
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| US4175005A (en) | Component nuclear containment structure | |
| US20030169839A1 (en) | Prefabricated in-core instrumentation chase | |
| FI74830C (en) | Nuclear reactor, whose core is shielded with a construction of rods and transverse plates. | |
| US4302296A (en) | Apparatus for insulating hot sodium in pool-type nuclear reactors | |
| SU1036256A3 (en) | Support arrangement for supplying heat carrier circulation system | |
| JPH01142496A (en) | Nuclear reactor vessel | |
| US4681731A (en) | Nuclear reactor construction with bottom supported reactor vessel | |
| US3775250A (en) | Device for suspending and supporting a reactor pressure vessel in a nuclear power plant | |
| US4198271A (en) | Liquid metal cooled nuclear reactor constructions | |
| US3769161A (en) | Reactor vessel supporting device | |
| JPH01109298A (en) | Nuclear reactor vessel | |
| JP3222597B2 (en) | Concrete structures in the containment vessel | |
| US3127046A (en) | Pressure vessels | |
| US4294661A (en) | Liquid metal cooled fast breeder nuclear reactor constructions | |
| JPH0314151B2 (en) | ||
| JPS6330785A (en) | Reactor pressure-vessel support structure | |
| JPH09236684A (en) | Double steel sheet reactor container | |
| US6563900B2 (en) | Ring plate around openings in reinforced concrete containment vessel | |
| JP2667856B2 (en) | Boiling water reactor | |
| JPH0325193Y2 (en) | ||
| JPS6346392B2 (en) | ||
| JPS5963590A (en) | Tank type fast breeder | |
| JPH0362234B2 (en) | ||
| JPH0367599B2 (en) | ||
| JPS62182696A (en) | Roof slab |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| A621 | Written request for application examination |
Effective date: 20040723 Free format text: JAPANESE INTERMEDIATE CODE: A621 |
|
| A977 | Report on retrieval |
Free format text: JAPANESE INTERMEDIATE CODE: A971007 Effective date: 20060406 |
|
| A131 | Notification of reasons for refusal |
Free format text: JAPANESE INTERMEDIATE CODE: A131 Effective date: 20060418 |
|
| A602 | Written permission of extension of time |
Free format text: JAPANESE INTERMEDIATE CODE: A602 Effective date: 20060704 |
|
| A521 | Written amendment |
Effective date: 20060724 Free format text: JAPANESE INTERMEDIATE CODE: A523 |
|
| A02 | Decision of refusal |
Effective date: 20070116 Free format text: JAPANESE INTERMEDIATE CODE: A02 |