JPS6288992A - Nuclear reactor vessel with wave return - Google Patents

Nuclear reactor vessel with wave return

Info

Publication number
JPS6288992A
JPS6288992A JP60229632A JP22963285A JPS6288992A JP S6288992 A JPS6288992 A JP S6288992A JP 60229632 A JP60229632 A JP 60229632A JP 22963285 A JP22963285 A JP 22963285A JP S6288992 A JPS6288992 A JP S6288992A
Authority
JP
Japan
Prior art keywords
reactor vessel
reactor
wave return
wave
return
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
JP60229632A
Other languages
Japanese (ja)
Inventor
卓哉 山下
田中 長年
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 Atomic Power Industries Inc
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 Atomic Power Industries Inc filed Critical Mitsubishi Atomic Power Industries Inc
Priority to JP60229632A priority Critical patent/JPS6288992A/en
Publication of JPS6288992A publication Critical patent/JPS6288992A/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

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  • Revetment (AREA)

Abstract

(57)【要約】本公報は電子出願前の出願データであるた
め要約のデータは記録されません。
(57) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.

Description

【発明の詳細な説明】 (イ)発明の目的 [産業上の利用分野] この発明は原子炉容器の構造に関するもので、特に、自
由液面を有する原子炉容器の地震時における容器内冷却
材の揺動(スロッシング)抑制構造を瀦えた原子炉容器
に関するものである。
Detailed Description of the Invention (a) Purpose of the Invention [Field of Industrial Application] This invention relates to the structure of a nuclear reactor vessel, and particularly relates to the construction of a coolant in a reactor vessel having a free liquid level during an earthquake. This relates to a nuclear reactor vessel with a structure to suppress sloshing.

[従来の技術] 自由液面を有する原子炉としては沸騰水型原子炉(BW
R)や高速増殖炉(FC3R)があるが、特に原子炉容
器内冷却材揺動に関しては冷却材の比重が大きいもの、
及び、原子炉容器径の大きいものが厳しいので、その−
例として、液体金属冷r!I高速増殖炉(タンク型)に
ついて説明する。
[Prior art] A boiling water reactor (BW) is a nuclear reactor with a free liquid level.
R) and fast breeder reactor (FC3R), especially those with a high specific gravity of the coolant, especially regarding the shaking of the coolant inside the reactor vessel.
Also, since it is difficult for reactor vessels with large diameters,
As an example, liquid metal cold r! The I fast breeder reactor (tank type) will be explained.

第3図は従来の液体金属冷却高速増殖炉(タンク型)の
原子炉構造の一例を示すもので、図にお   ゛いて符
号1は原子炉容器である。原子炉容器1はルーフスラブ
2により吊り下げられており、内部にはある一定量の液
体金属すl−リウム3を1次冷却材として貯留している
。また、原子炉容器内には炉内機器である中間熱交換器
14.1次冷却系ポンプ13及び炉心上部機構15がル
ーフスラブ2により吊り下げられている。なお、ルーフ
スラブ2の下面には熱損失を防ぎ、がっ、ルーフスラブ
を低温に保つ、ための熱遮蔽構造16が設けられている
。符号17は炉心であり、炉心17は原子炉容器1の容
器壁から容器の中央に向って張出した炉心支持構造18
により支持されている。
Figure 3 shows an example of the reactor structure of a conventional liquid metal cooled fast breeder reactor (tank type), and in the figure, numeral 1 is the reactor vessel. The reactor vessel 1 is suspended by a roof slab 2, and a certain amount of liquid metal sl-lium 3 is stored therein as a primary coolant. Further, inside the reactor vessel, an intermediate heat exchanger 14, a primary cooling system pump 13, and a core upper mechanism 15, which are in-core equipment, are suspended by a roof slab 2. A heat shielding structure 16 is provided on the lower surface of the roof slab 2 to prevent heat loss and keep the roof slab at a low temperature. Reference numeral 17 indicates a reactor core, and the reactor core 17 has a core support structure 18 extending from the vessel wall of the reactor vessel 1 toward the center of the vessel.
Supported by

タンク型液体金属冷W高速増殖炉において、炉心17を
出た冷却材3は自由液面5を形成する高温g1域の上部
ブレナム9へ流出し、中間熱交換器14を通って低温領
域の下部ブレナム8へ流出する。なJ3、通常、原子炉
容器1の容器壁1aの内側には、上部ブレナム9からの
入熱を低減するための炉壁断熱構造1oが設置される。
In a tank type liquid metal cooled W fast breeder reactor, the coolant 3 leaving the reactor core 17 flows out to the upper blennium 9 of the high temperature g1 region forming the free liquid level 5, passes through the intermediate heat exchanger 14, and flows to the lower part of the low temperature region. Flows into Blenheim 8. J3, normally, a reactor wall insulation structure 1o is installed inside the vessel wall 1a of the reactor vessel 1 to reduce heat input from the upper blemish 9.

このような自由液面を有する原子炉においては、地震時
に原子炉容器内の1次冷却材に揺e(スロッシング)が
生じる。一定の地震入力に対する自由液面の揺動の大き
さは、液体を満たす容器の径にほぼ比例するので、原子
炉容器径が大きいタンク型液体金属冷却高速増殖炉では
、揺動防止の対策が無い場合、数メートルのスロッシン
グ波高になる可能性がある。このような大きなスロッシ
ングが生じた場合、揺動圧によりルーフスラブ下面の熱
遮蔽構造や炉壁断熱構造、更には、中間熱交換器や1次
冷却系ポンプ等の炉内機器が損傷し、原子炉構造として
の健全性が保てないのではないかといった問題があり、
その対策が望まれていた。
In a nuclear reactor having such a free liquid level, sloshing occurs in the primary coolant in the reactor vessel during an earthquake. The magnitude of fluctuation of the free liquid level in response to a given seismic input is approximately proportional to the diameter of the container filled with liquid, so in tank-type liquid metal cooled fast breeder reactors with large reactor vessels, measures to prevent fluctuations are required. If not, sloshing wave heights of several meters may occur. If such large sloshing occurs, the rocking pressure will damage the heat shielding structure on the lower surface of the roof slab, the furnace wall insulation structure, and even the reactor equipment such as the intermediate heat exchanger and the primary cooling system pump, resulting in nuclear damage. There is a problem that the soundness of the reactor structure may not be maintained.
A countermeasure was desired.

[発明が解決しようとする問題点] この発明は、上記の如き事情に鑑みてなされたものであ
って、従来の技術がもつ地震時における原子炉容器内冷
却材の揺動の問題を解消し、炉内機器をはじめ原子炉構
造としての健全性を保ち得る原子炉容器を提供すること
を目的とするものである。
[Problems to be Solved by the Invention] This invention has been made in view of the above circumstances, and solves the problem of the shaking of the coolant in the reactor vessel during an earthquake, which the conventional technology has. The purpose of the present invention is to provide a reactor vessel that can maintain the integrity of the reactor structure, including internal equipment.

(ロ)発明の構成 [問題を解決するための手段] この目的に対応して、この発明の波返しを備えた原子炉
容器は、自由液面を有する原子炉容器において、原子炉
容器壁または原子容器壁に沿って原子炉容器の内側に配
置された炉内構造物に、前記原子炉容器の内方に向って
円弧状に伸びる波返しを設けたことを特徴としている。
(b) Structure of the Invention [Means for Solving the Problem] Corresponding to this object, the reactor vessel equipped with a wave return according to the present invention provides a reactor vessel wall or The reactor internal structure is arranged inside the reactor vessel along the wall of the reactor vessel, and is provided with a wave return extending in an arc shape toward the inside of the reactor vessel.

以下、この発明の詳細を一実施例を示す図面について説
明する。
Hereinafter, details of the present invention will be explained with reference to the drawings showing one embodiment.

第1図は本発明の一冥施例に係わる波返しを備えた原子
炉容器の縦断面図であり、第2図は第1図におけるA部
拡大図である。なお、従来と同一構成の部分については
同一符号を用いて説明する。
FIG. 1 is a longitudinal sectional view of a nuclear reactor vessel equipped with a wave return according to one embodiment of the present invention, and FIG. 2 is an enlarged view of section A in FIG. 1. Note that the same reference numerals are used to describe parts that have the same configuration as the conventional one.

図において符号6は波返しであり、波返し6は耐蝕性に
優れた材料、例えば、ステンレス鋼等をその断面が円弧
状となるように鍛造若しくは成形した円環状の構造物で
ある。図示の例では、その波返し6を炉内構造物である
炉壁断熱構造10の内側ライナー10aに設けたもので
、その設置位置は原子炉容器の軸長方向に自由液面5の
近傍の上方に1ケ所、そして、自由液面5近傍の下方に
2ケ所としている。波返し6の設置位置をこのように自
由液面近傍とする理由は、他の部分、即ち自由液面より
ずっと下方とするよりは、波返しの効果が大きいからで
あって、自由液面下に設置した波返しが効果的でないと
いうことではない。また、図示の波返しは原子炉容器壁
に沿って一周する円環状のものが示されているが、制作
上の都合により、これを分割型とし、或は不連続として
も支障はない。例えば、分割型とした場合、図示してい
ないが、最上段に設置した波返しを周方向に不連続に取
付けた場合、それより一段下に設置する波返しの不連続
部が前記上段の波返しの不連続部に一致しないように周
方向に位置をずらして交互に設置することによって波返
しとしての機能は十分発揮される。
In the figure, reference numeral 6 indicates a corrugation, and the corrugation 6 is an annular structure made of a material with excellent corrosion resistance, such as stainless steel, forged or molded so that its cross section is arcuate. In the illustrated example, the wave return 6 is provided on the inner liner 10a of the reactor wall insulation structure 10, which is a reactor internal structure, and its installation position is near the free liquid level 5 in the axial direction of the reactor vessel. There is one location above and two locations below near the free liquid level 5. The reason why the wave return 6 is installed near the free liquid level is that the effect of the wave return is greater than when it is installed in other parts, that is, far below the free liquid level. This is not to say that wave return installed in the area is not effective. Furthermore, although the wave return shown in the figure is an annular one that goes around the reactor vessel wall, there is no problem in making it a split type or discontinuous for manufacturing reasons. For example, in the case of a split type, if the wave return installed at the top level is installed discontinuously in the circumferential direction (not shown in the figure), the discontinuous part of the wave return installed one level below will be the wave return installed at the top level. The function as a wave return is fully demonstrated by shifting the position in the circumferential direction and installing the waves alternately so as not to coincide with the discontinuous part of the wave return.

第2図において波返しの情況を図中矢印で例示的に示し
ているが、波返し6は原子炉容器の内方に向かって円弧
状に伸びており、その先Q 6 aは水平か、或は若干
下向きに湾曲していることがスロッシング波高7を小さ
くするうえで効果的である。この湾曲の度合は原子炉容
器径によって適宜選択される。
In Fig. 2, the situation of the wave return is exemplified by the arrow in the figure, and the wave return 6 extends in an arc shape toward the inside of the reactor vessel, and its tip Q 6 a is horizontal or not. Alternatively, slightly curving downward is effective in reducing the sloshing wave height 7. The degree of curvature is appropriately selected depending on the reactor vessel diameter.

なお、前記波返し6の設置は炉壁断熱構造の内側ライナ
ーに限定されるものではなく、原子炉容器壁または原子
炉容器壁に沿って原子炉容器の内側に配置される炉内構
造物であってもよいことはいうまでもない。この場合に
おいても波返しの効果はほとんど変らない。
Note that the installation of the wave return 6 is not limited to the inner liner of the reactor wall insulation structure, but can be installed on the reactor vessel wall or on the reactor internal structure arranged inside the reactor vessel along the reactor vessel wall. Needless to say, it is possible. Even in this case, the wave return effect remains almost unchanged.

U作用コ 地震時に原子炉容器内冷却材の揺動によって生じる上部
ブレナムの波は、第2図に例示したように波返しに当た
り減衰すると共に、定常波の発生が抑制されるので、ス
ロッシングの生長が大幅に低減される。
U action: The waves in the upper brenum caused by the shaking of the coolant in the reactor vessel during an earthquake are attenuated by the wave return, as illustrated in Figure 2, and the generation of standing waves is suppressed, so the growth of sloshing is suppressed. significantly reduced.

(ハ)発明の効果 この発明によれば原子炉容器の内方に向かって円弧状に
伸びる、すなわち、全体として原子炉容器に対して内側
に向いた鍔状の波返しを設けるだけの簡単な構造により
スロッシングを抑制しうる原子炉容器を得ることができ
る。
(C) Effects of the Invention According to the present invention, it is simple to provide a flange-shaped return that extends inwardly in the reactor vessel in an arc shape, that is, faces inward as a whole with respect to the reactor vessel. It is possible to obtain a reactor vessel that can suppress sloshing depending on the structure.

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

第1図は本発明の一実施例に係わる波返しを備えた原子
炉容器の縦断面図、第2図は第1図ににJ3(プる△部
拡大図、及び第3図は従来のタンク型液体金属冷却高速
増殖炉の縦断面図である。 1・・・原子炉容器  1a・・・原子炉容器壁  3
・・・液体全屈ナトリウム  5・・・自由液面  6
・・・波返し  6a・・・先端  7・・・スロッシ
ング波高9・・・上部ブレナム  10・・・炉壁断熱
構造10a・・・内側ライナー 特許出願人      三菱原子カニ業株式会社代理人
弁理士         川 井 冶 男第1図
Fig. 1 is a vertical cross-sectional view of a reactor vessel equipped with a wave return according to an embodiment of the present invention, Fig. 2 is an enlarged view of the J3 (△) part in Fig. 1, and Fig. 3 is an enlarged view of the conventional reactor vessel. It is a longitudinal cross-sectional view of a tank-type liquid metal cooled fast breeder reactor. 1... Reactor vessel 1a... Reactor vessel wall 3
...Liquid total bending sodium 5...Free liquid level 6
...Return wave 6a...Tip 7...Sloshing wave height 9...Upper blemish 10...Reactor wall insulation structure 10a...Inner liner Patent applicant Mitsubishi Atomic Crab Industry Co., Ltd. Representative Patent Attorney Kawa Osamu Ii Figure 1

Claims (3)

【特許請求の範囲】[Claims] (1)自由液面を有する原子炉容器において、原子炉容
器壁または原子容器壁に沿って原子炉容器の内側に配置
された炉内構造物に、前記原子炉容器の内方に向って円
弧状に伸びる波返しを設けたことを特徴とする波返しを
備えた原子容器
(1) In a reactor vessel having a free liquid level, a circular motion toward the inside of the reactor vessel is applied to the reactor vessel wall or to the reactor internals arranged inside the reactor vessel along the reactor vessel wall. An atomic container equipped with a wave return that is characterized by having a wave return that extends in an arc shape.
(2)前記炉内構造物は炉壁断熱構造の内側ライナーで
ある特許請求の範囲第1項記載の波返しを備えた原子炉
容器
(2) A reactor vessel equipped with a wave return according to claim 1, wherein the reactor internal structure is an inner liner of a reactor wall insulation structure.
(3)前記波返しは原子炉容器の軸長方向に複数段設け
たことを特徴とする特許請求の範囲第1項または第2項
記載の波返しを備えた原子炉容器(4)前記波返しは自
由液面近傍の前記自由液面上及び液面下に設けたことを
特徴とする特許請求の範囲第3項記載の波返しを備えた
原子炉容器
(3) A reactor vessel equipped with a wave return according to claim 1 or 2, characterized in that the wave return is provided in a plurality of stages in the axial direction of the reactor vessel (4) The wave return A nuclear reactor vessel equipped with a wave return according to claim 3, wherein the wave return is provided near the free liquid surface above and below the liquid surface.
JP60229632A 1985-10-15 1985-10-15 Nuclear reactor vessel with wave return Pending JPS6288992A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP60229632A JPS6288992A (en) 1985-10-15 1985-10-15 Nuclear reactor vessel with wave return

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP60229632A JPS6288992A (en) 1985-10-15 1985-10-15 Nuclear reactor vessel with wave return

Publications (1)

Publication Number Publication Date
JPS6288992A true JPS6288992A (en) 1987-04-23

Family

ID=16895237

Family Applications (1)

Application Number Title Priority Date Filing Date
JP60229632A Pending JPS6288992A (en) 1985-10-15 1985-10-15 Nuclear reactor vessel with wave return

Country Status (1)

Country Link
JP (1) JPS6288992A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH0443300U (en) * 1990-08-13 1992-04-13

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH0443300U (en) * 1990-08-13 1992-04-13

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