JPS5855890A - Vessel of fast breeder - Google Patents

Vessel of fast breeder

Info

Publication number
JPS5855890A
JPS5855890A JP56155113A JP15511381A JPS5855890A JP S5855890 A JPS5855890 A JP S5855890A JP 56155113 A JP56155113 A JP 56155113A JP 15511381 A JP15511381 A JP 15511381A JP S5855890 A JPS5855890 A JP S5855890A
Authority
JP
Japan
Prior art keywords
reactor
liquid level
vessel
temperature
coolant
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.)
Granted
Application number
JP56155113A
Other languages
Japanese (ja)
Other versions
JPS623392B2 (en
Inventor
横山 武芳
節雄 山本
磯部 賢司
桜井 義行
吉沢 弘泰
芳郎 宮崎
安永 壽夫
富也 佐々木
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.)
Toshiba Corp
Original Assignee
Tokyo Shibaura Electric Co 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 Tokyo Shibaura Electric Co Ltd filed Critical Tokyo Shibaura Electric Co Ltd
Priority to JP56155113A priority Critical patent/JPS5855890A/en
Publication of JPS5855890A publication Critical patent/JPS5855890A/en
Publication of JPS623392B2 publication Critical patent/JPS623392B2/ja
Granted 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

  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Secondary Cells (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】 本発明は、高速増殖炉用原子炉容器に係り。[Detailed description of the invention] The present invention relates to a reactor vessel for a fast breeder reactor.

特に容器壁≦二加わる熱応力を軽減させることができる
ようにした原子炉容器に関する。
In particular, the present invention relates to a nuclear reactor vessel that can reduce the thermal stress applied to the vessel wall≦2.

高速増殖炉(二おいては、冷却材として、一般に液体力
) IJウムで代表される液体金属が用いられている。
Fast breeder reactors (in general, liquid power) liquid metals, typified by IJum, are used as the coolant.

セして、このような液体金属冷却材は原子炉容器内を第
1図【二示すよう+: 1llH流する。すなわち1図
中1は内部に炉心2を収容してなる炉容器であり、この
炉容器りの容器壁3に設けられた入口ノズル4より流入
した冷却材pは炉心2内を導びかれ、炉心2がら熱を噂
って加熱された後、自由な液面5を形成【7ながら容器
壁3の上部(二設けられた出口ノズル6を通な高速増殖
炉にあって冷却材aSは1通常運転時には、炉心入口で
300C〜4ooIIC1炉心炉運転停止状態Cおいて
は、入口、出口共約2000に保たれる。そして、原子
炉運転開始時には、冷却材の出口ノズル6の温度が、第
2図6二示すように、停止温度T1より通常運転温度T
マまで、ある一定の昇温率で上昇するように炉心反応が
制卸される。この昇温率はプラントの運転上−■能な限
り大きくすることが効率ならびに稼動率を高めるうえで
望ましい。
As a result, such liquid metal coolant flows through the reactor vessel at a rate of 1llH as shown in FIG. That is, 1 in Figure 1 is a reactor vessel which houses a reactor core 2 therein, and the coolant p that flows in through the inlet nozzle 4 provided on the vessel wall 3 of this reactor vessel is guided into the reactor core 2. After the reactor core 2 is heated up, a free liquid level 5 is formed (7) while the coolant aS in the fast breeder reactor passes through the outlet nozzle 6 provided at the top of the vessel wall 3 (2). During normal operation, the core inlet is 300C to 4ooIIC1. In the reactor shutdown state C, both the inlet and the outlet are maintained at approximately 2000C. At the start of reactor operation, the temperature of the coolant outlet nozzle 6 is 2 As shown in Figure 62, the normal operating temperature T is lower than the stop temperature T1.
The core reaction is controlled so that the temperature rises at a certain rate until It is desirable to make this temperature increase rate as large as possible in terms of plant operation in order to increase efficiency and operation rate.

ところで、高速増殖炉にあっては、冷却材として腐食性
の商いアルカリ金属液体を用いる関係上5通常、炉容器
をステンレス鋼で製作するようC二している。ステンレ
ス鋼は周知のよう【二温曵伝導率が非常に小さい。この
ために、上述の如く、運転開始時に絆温率を大きくする
と。
By the way, in fast breeder reactors, because a corrosive alkali metal liquid is used as a coolant, the reactor vessel is usually made of stainless steel. As is well known, stainless steel has very low two-temperature conductivity. For this reason, as mentioned above, the bond temperature rate is increased at the start of operation.

第3図(a) に対応させて、第3図(b)に示すよう
に、容器壁3の各熱温度は図中8aで示すようになり、
液面近傍に大きな温度勾配が発生し、このしたがって、
運転開始時における昇温率を大きくするも二は、上記の
熱応力を何らかの手段で軽と1二は変りない。
Corresponding to FIG. 3(a), as shown in FIG. 3(b), each thermal temperature of the container wall 3 is as shown by 8a in the figure,
A large temperature gradient occurs near the liquid surface, and therefore,
Although the temperature increase rate at the start of operation is increased, the above-mentioned thermal stress is reduced by some means.

本発明は、このような事情に鑑みてなされたもので、七
の目的とするところは、原子炉運転開始1および運転停
止時に炉容器壁のh部材の液面近傍に発生する熱応力を
簡単な構成で軽減させることができ、もって安全性の向
上化と。
The present invention has been made in view of the above circumstances, and the seventh object is to easily reduce the thermal stress generated near the liquid level of the H member on the wall of the reactor vessel at the time of starting and stopping the reactor operation. This can be reduced with a suitable configuration, thereby improving safety.

原子炉プラントの効率ならびL:稼動率の向上化とに寄
与できる高速増殖炉用原子炉容器を提供することC:あ
る。
C: To provide a reactor vessel for a fast breeder reactor that can contribute to improving the efficiency of a nuclear reactor plant and L: operation rate.

すなわち1本発明は、原子炉容器本体の側壁外面C:、
それぞれが冷却材の液面とほぼ自交する向きで、一端が
上記液面より上部に、他端が液面より下部の炉心の低部
近傍1:位置するようfニヒートパイプを少くとも周方
向に複数1阪し。
That is, 1 the present invention provides the side wall outer surface C of the reactor vessel main body:
At least the heat pipes should be installed at least in the circumferential direction so that each of them is oriented almost perpendicular to the liquid level of the coolant, and one end is located above the liquid level and the other end is located near the lower part of the core below the liquid level. Multiple times.

容器壁、特に液面近傍の、温度勾配を緩和させることに
よって1紀目的を達成したものである。
The primary objective was achieved by alleviating the temperature gradient on the container wall, especially near the liquid surface.

以下本発明の¥誰例を図面を参照しながら説明する。Hereinafter, an example of the present invention will be explained with reference to the drawings.

第4図(a)は本発明に係る炉容器りの中心線から右半
分を切断して示すもので、elflNと同一部分は同一
符号で示し1ある。しだかって賑復する部分の説明は省
略する。
FIG. 4(a) shows the right half cut away from the center line of the furnace vessel according to the present invention, and the same parts as elflN are designated by the same reference numerals 1. However, the explanation of the part that is prosperous will be omitted.

この実施例では、容器壁Sの側壁部外向C二。In this embodiment, the side wall portion of the container wall S is outwardly directed C2.

それぞれが炉容器内の冷却材の液面5とほぼI交する向
きで、上端が上記液面5より上方の液面近傍に位置し、
下端が液面6より下方の炉心2の低部近傍に位置する関
係(=複数本のパイプ伏の毛細管圧力を利用した無方向
性ヒートパイプ9aを周方向に等間隔C二装置固定した
ものとなっている。
Each is oriented in a direction that substantially intersects with the liquid level 5 of the coolant in the furnace vessel, and the upper end is located near the liquid level above the liquid level 5,
A relationship in which the lower end is located near the lower part of the core 2 below the liquid level 6 (= non-directional heat pipes 9a that utilize the capillary pressure of multiple pipes are fixed at equal intervals in the circumferential direction) It has become.

このような構成である−と、原子炉運転開始時において
は、ヒートパイプ9aの良好な伝熱作用により、容5壁
3の炉心2の低部近傍I:位置rる部分の熱が、ヒート
パイプ9&を通って容器壁3の冷却材の#、向5より1
部の低温部分へ伝えられることになる。したがって、容
器壁3の液…15より上刃に位置する部分は、上記ヒー
トパイプ9aの存在−二よって、’J容器壁の側面から
も、つまり十分広い熱供給路で熱供給を受けること(二
なるので、たとえ容器11j、sが温度伝へ率の低い材
料で形成されている場合であっても、短時間に昇温し、
この結果、上記部分の温度勾配を十分緩やか(二するこ
とができる。
With such a configuration, at the start of reactor operation, due to the good heat transfer effect of the heat pipes 9a, the heat of the portion of the vessel 5 wall 3 near the lower part of the core 2 is transferred to the heat source. # of coolant in vessel wall 3 through pipe 9 & 1 from direction 5
This will be transmitted to the low-temperature parts of the body. Therefore, due to the presence of the heat pipe 9a, the portion of the container wall 3 located above the liquid 15 receives heat from the side of the container wall, that is, through a sufficiently wide heat supply path. Therefore, even if the containers 11j and s are made of a material with low thermal conductivity, the temperature will rise in a short time,
As a result, the temperature gradient in the above portion can be made sufficiently gentle.

したがって、原子炉の運転開始時6二拌温率を坊・11
にか 高くしても熱応力I:よって容器壁b”*−壊jれるよ
うなことがなく、結局、安全性の向上化と原子炉プラン
トの効率および稼動率の向上化に寄与することができる
。そして、ヒートパイプの付加という簡単な構成で、か
つ、動力や制御の全く必要としない手段で、液面近傍の
容器壁の温度勾配を緩和させることができるので、設備
全体が高価格化したり、制御が複雑化したりするおそれ
がない。
Therefore, at the start of operation of the reactor, the stirring temperature should be lowered to 62° and 11°.
Even if the thermal stress I is increased, the vessel wall will not break, and this will ultimately contribute to improving safety and improving the efficiency and operating rate of the reactor plant. Moreover, the temperature gradient on the container wall near the liquid surface can be alleviated with a simple configuration of adding a heat pipe, and with a means that does not require any power or control, so the overall cost of the equipment can be reduced. There is no risk that the control will become complicated.

そして、この場合には、特に、ヒートパイプ9aの下部
を容器壁3の炉心2の低部近傍c二位置させているので
、液面5近傍の冷却材温度。
In this case, in particular, since the lower part of the heat pipe 9a is located near the lower part of the reactor core 2 on the vessel wall 3, the temperature of the coolant near the liquid level 5.

つまり中間熱交換器C二流入する冷却材温度を上げるこ
となく、容器壁3の液面5より上部部分の温度を上げて
、液面近傍の温度勾配を緩和させることができるので、
運転開始時ζ二おける炉心発生熱も有効f二利用するこ
とができる。
In other words, without increasing the temperature of the coolant flowing into the intermediate heat exchanger C2, it is possible to raise the temperature of the portion of the container wall 3 above the liquid level 5 and to alleviate the temperature gradient near the liquid level.
The heat generated in the core at the start of operation can also be effectively utilized f2.

すなわち、このようにヒートパイプ9aを設けることに
二よって運転開始時には、第4図(υ(二対応させて示
す第4図(b)に実線Ibで示すように容器壁の冷却材
の液面5近傍の温度勾配を従来の場合の温度分布8&の
温度勾配に比較させて緩和させることができる。運転停
止時にも、上記ヒートパイプにより逆の温度勾配を緩和
させることができる。
That is, by providing the heat pipe 9a in this way, at the start of operation, the liquid level of the coolant on the container wall will be lowered as shown by the solid line Ib in FIG. The temperature gradient near 5 can be relaxed compared to the temperature gradient of temperature distribution 8& in the conventional case.Even when the operation is stopped, the opposite temperature gradient can be relaxed by the heat pipe.

なお1本発明は上述した実施例L:限定されるものでは
ない。すなわち、上述した実施例では、ヒートパイプ9
aを冷却材の液面と直交した軸C二沿って、1ケ所のみ
配置させているが、たとえば、wJ5図に示すように、
長さの異る二種類のヒー トパイグ9a 、 9bを上
記軸方向に分散させて配置してもよい。上述のように軸
方向に複数のヒートパイプを設置すると前記の温度勾配
をさらに緩和させることができる。また、ヒートパイプ
の種類も限定されるものではない。
Note that the present invention is not limited to the above-mentioned Example L. That is, in the embodiment described above, the heat pipe 9
A is placed only at one location along the axis C2 perpendicular to the liquid level of the coolant, but for example, as shown in Figure wJ5,
Two types of heat pipes 9a and 9b having different lengths may be distributed and arranged in the axial direction. By installing a plurality of heat pipes in the axial direction as described above, the temperature gradient described above can be further alleviated. Furthermore, the type of heat pipe is not limited.

実施例では運転開始時および運転停止時共にヒートパイ
プを動作させるために、方向性を有さない毛細管圧力を
利用したヒートパイプを用いているが、運転開始時のみ
温度勾配を緩和させればよい場合;二は、敵方型ヒート
パイプを用いてもよい。さらに、ヒートパイプの形状、
大きさ、使用する個数も限定されるものではない。
In the example, a heat pipe that utilizes non-directional capillary pressure is used in order to operate the heat pipe both at the start of operation and at the time of stop, but it is only necessary to relax the temperature gradient at the time of start of operation. Case: Second, an enemy type heat pipe may be used. Furthermore, the shape of the heat pipe,
The size and the number of pieces used are not limited either.

以上述べたよう(二本発明によれば、複雑な構造や制御
Vステム、余分な動力を用いることなく、運転開始時や
運転停止時に炉容器壁に加わる熱応力を軽減させること
ができ、もって、安全性の向を化ならび(二稼勢率の向
上化に寄与できる高速増殖炉用原子炉容器を提供できる
As mentioned above (2) According to the present invention, it is possible to reduce the thermal stress applied to the reactor vessel wall at the time of starting and stopping the operation without using a complicated structure, a control V-stem, or extra power. Therefore, it is possible to provide a reactor vessel for a fast breeder reactor that can contribute to improving safety and improving the operating rate.

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

第1図は高速増殖炉用原子炉容器を模式的;二示す図、
第2図は原子炉の運転開始時および運転停止時における
冷却材温度の変化の一例を示す図、第3図α)は第1図
の拡大図、同図(b)は運転開始時における第3図(a
)に対応する容器壁の温度分布を示す図、第4図に)は
本発明の一実施例に係る原子炉容器を一部切欠して示す
側面図。 同図(鴨は同実施例における容器壁の温度分布を説明す
るための図、第5図は本発明の別の実施例に係る原子炉
容器の縦断面図である。 7)、 1 b ・・−炉容器、2・・・炉IC,−,
,9・・・容器壁。 出願人代遅人  弁理士 鈴 江 武 彦第1図 第2図 時間 第3図 (b) ;; 度 1頁の続き 0発 明 者 宮崎刃部 川崎市幸区小向東芝町1番地東 京芝浦電気株式会社総合研究所 内 0発 明 者 安永壽夫 川崎市幸区小向東芝町1番地東 京芝浦電気株式会社総合研究所 内 0発 明 者 佐々木富也 川崎市幸区小向東芝町1番地東 京芝浦電気株式会社総合研究所 491−
Figure 1 schematically shows the reactor vessel for a fast breeder reactor;
Figure 2 is a diagram showing an example of changes in coolant temperature at the start and shutdown of a nuclear reactor, Figure 3 α) is an enlarged view of Figure 1, and Figure 3 (b) is a diagram showing an example of changes in coolant temperature at the start of operation and at the time of shutdown of a nuclear reactor. Figure 3 (a
FIG. 4) is a partially cutaway side view of a reactor vessel according to an embodiment of the present invention. The same figure (the duck is a diagram for explaining the temperature distribution of the vessel wall in the same embodiment, and FIG. 5 is a longitudinal cross-sectional view of a reactor vessel according to another embodiment of the present invention. 7), 1 b ・・-furnace vessel, 2...furnace IC,-,
, 9... Container wall. Late Applicant Patent Attorney Takehiko Suzue Figure 1 Figure 2 Time Figure 3 (b) Inventor: Hisao Yasunaga, 1 Komukai Toshiba-cho, Saiwai-ku, Kawasaki City, Tokyo Shibaura Electric Co., Ltd. Research Institute, Tokyo Shibaura Electric Co., Ltd. Inventor: Tomiya Sasaki, Tokyo Shibaura Electric Co., Ltd., 1 Komukai Toshiba-cho, Saiwai-ku, Kawasaki City General Research Institute Co., Ltd. 491-

Claims (1)

【特許請求の範囲】[Claims] 液体金属冷却材の循環路I:介在して設けられ内部を上
記液体金属冷却材が自由液面をもって通流する原子炉容
器本体と、この原子炉容器本体の側壁外面に、それぞれ
が上記自由液面とほぼ直交する向きで、一端が上記自由
液面より″上部位置に固定され、他端が上記自由液面よ
り下部の炉心低部近傍位li+=固定され、少くとも周
方向に複数配置固定されたヒートパイプとを具備してな
ることを特徴とする高速増殖炉用原子炉容器。
Circulation path I for liquid metal coolant: A reactor vessel body that is interposed and through which the liquid metal coolant flows with a free liquid level, and a side wall outer surface of the reactor vessel body that has the free liquid level, respectively. In a direction substantially perpendicular to the surface, one end is fixed at a position above the free liquid level, and the other end is fixed at a position below the free liquid level near the lower part of the core, and at least a plurality of them are arranged and fixed in the circumferential direction. A nuclear reactor vessel for a fast breeder reactor, characterized in that it is equipped with a heat pipe.
JP56155113A 1981-09-30 1981-09-30 Vessel of fast breeder Granted JPS5855890A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP56155113A JPS5855890A (en) 1981-09-30 1981-09-30 Vessel of fast breeder

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP56155113A JPS5855890A (en) 1981-09-30 1981-09-30 Vessel of fast breeder

Publications (2)

Publication Number Publication Date
JPS5855890A true JPS5855890A (en) 1983-04-02
JPS623392B2 JPS623392B2 (en) 1987-01-24

Family

ID=15598869

Family Applications (1)

Application Number Title Priority Date Filing Date
JP56155113A Granted JPS5855890A (en) 1981-09-30 1981-09-30 Vessel of fast breeder

Country Status (1)

Country Link
JP (1) JPS5855890A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS6369602A (en) * 1986-09-10 1988-03-29 積水化学工業株式会社 Manufacture of concrete material
JP2012154644A (en) * 2011-01-21 2012-08-16 Toshiba Corp Heat transportation device of reactor container and method of the same

Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5674694A (en) * 1979-11-22 1981-06-20 Tokyo Shibaura Electric Co Nuclear reactor container

Patent Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5674694A (en) * 1979-11-22 1981-06-20 Tokyo Shibaura Electric Co Nuclear reactor container

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS6369602A (en) * 1986-09-10 1988-03-29 積水化学工業株式会社 Manufacture of concrete material
JP2012154644A (en) * 2011-01-21 2012-08-16 Toshiba Corp Heat transportation device of reactor container and method of the same

Also Published As

Publication number Publication date
JPS623392B2 (en) 1987-01-24

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