JPS62269090A - Nuclear reactor - Google Patents

Nuclear reactor

Info

Publication number
JPS62269090A
JPS62269090A JP61112691A JP11269186A JPS62269090A JP S62269090 A JPS62269090 A JP S62269090A JP 61112691 A JP61112691 A JP 61112691A JP 11269186 A JP11269186 A JP 11269186A JP S62269090 A JPS62269090 A JP S62269090A
Authority
JP
Japan
Prior art keywords
reactor
temperature coolant
core
guide member
low
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
JP61112691A
Other languages
Japanese (ja)
Inventor
義人 阿部
上田 三男
舞田 靖司
浜田 勝彦
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.)
Central Research Institute of Electric Power Industry
Mitsubishi Heavy Industries Ltd
Original Assignee
Central Research Institute of Electric Power Industry
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 Central Research Institute of Electric Power Industry, Mitsubishi Heavy Industries Ltd filed Critical Central Research Institute of Electric Power Industry
Priority to JP61112691A priority Critical patent/JPS62269090A/en
Publication of JPS62269090A publication Critical patent/JPS62269090A/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

  • Analysing Materials By The Use Of Radiation (AREA)
  • Treatment Of Water By Oxidation Or Reduction (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】 (産業上の利用分野) 本発明は原子炉に関するものである。[Detailed description of the invention] (Industrial application field) The present invention relates to nuclear reactors.

(従来の技術) 従来の高速増殖炉を第7図により説明すると。(Conventional technology) A conventional fast breeder reactor will be explained with reference to FIG.

(1)が原子炉容器、(2)が同原子炉容器(1)内を
上部プレナムと下部プレナムとに仕切る仕切板、(3)
が炉心1(4)が上記原子炉容器(1)の下部に設けた
入口ノズル、(5)が上記炉心(3)の上面上方に位置
する原子炉上部機構、(6)が同原子炉上部機構(5)
の下端部に取付けたフローガイド部材、(7)が上記原
子炉容器(1)の中間部に設けた出口ノズルで、冷却材
が入口ノズル(4)から原子炉容器(1)の下部プレナ
ムへ流入して、炉心(3)内に入り。
(1) is a reactor vessel, (2) is a partition plate that partitions the inside of the reactor vessel (1) into an upper plenum and a lower plenum, (3)
The reactor core 1 (4) is an inlet nozzle provided at the lower part of the reactor vessel (1), (5) is the upper reactor mechanism located above the upper surface of the reactor core (3), and (6) is the upper part of the reactor. Mechanism (5)
The flow guide member (7) installed at the lower end of the reactor vessel (1) is the outlet nozzle installed in the middle of the reactor vessel (1), and the coolant flows from the inlet nozzle (4) to the lower plenum of the reactor vessel (1). It flows into the reactor core (3).

ここで加熱されて、上部プレナムへ流出し、フローガイ
ド部材(6)に当たって、横方向に流動した後、上昇に
転じて、上部プレナム内の冷却材と混合しながら上昇を
続け、上部プレナムの上部から反転、下降して、出口ノ
ズル(7)から原子炉容器(1)外へ流出するようにな
っている。なお原子炉の定格運転時、炉心(3)から上
部プレナムへ流出する高温冷却材の勢いは強い。この高
温冷却材を上部プレナムへ上向きに流出させると、高温
冷却材の流れが炉内液面に達し、液面が乱れて、気泡が
冷却材中へ巻き込まれる等の問題が生じる。フローガイ
ド部材(6)を炉心(3)の上面上方に配設して、炉心
(3)からの高温冷却材を一旦横向きに流動させるのは
、上記気泡の巻き込み等を防止するためである。
It is heated here, flows out to the upper plenum, hits the flow guide member (6), flows laterally, turns upward, continues to rise while mixing with the coolant in the upper plenum, and flows to the upper part of the upper plenum. From there, it turns around, descends, and flows out of the reactor vessel (1) from the outlet nozzle (7). Note that during rated operation of the reactor, the force of high-temperature coolant flowing out from the reactor core (3) to the upper plenum is strong. If this high-temperature coolant flows upward into the upper plenum, the flow of high-temperature coolant will reach the liquid level in the furnace, causing problems such as turbulence of the liquid level and entrainment of air bubbles into the coolant. The reason why the flow guide member (6) is disposed above the upper surface of the reactor core (3) to once flow the high temperature coolant from the reactor core (3) sideways is to prevent the entrainment of air bubbles and the like.

(発明が解決しようとする問題点) 高速増殖炉の運転中、何らかの原因で急に運転を停止す
る場合、制御棒を炉内へ挿入して、核反応を止めるので
、炉心(3)から上部プレナムへ低温の冷却材が流出し
て、原子炉容器(1)壁等に熱衝撃を与える。このとき
の熱衝撃を軽減するために、原子炉の停止と同時に人口
ノズル(4)から原子炉容器(1)内へ流入する冷却材
の流量を減少するような運転方法が採られている。この
とき、第7図に示す従来の高速増殖炉では1次の問題を
生じている。即ち、入口ノズル(4)から原子炉容器(
1)内へ流入する冷却材の流量を減少すると、炉心(3
)から上部プレナムへ流出する低温冷却材の勢いが弱く
なる。その際、低温冷却材の流れが上向きであれば、低
温冷却材が原子炉の停止前、上部プレナム内にあった高
温の冷却材へ充分に混合して、上部プレナムの上部に高
温冷却材層が、下部に低温冷却材層が、形成されるよう
なことはないが、前記第7図に示す高速増殖炉では、原
子炉上部機構(5)の下端部に取付けたフローガイド部
材(7)が水平の板状であり、勢いの弱い低温冷却材が
横方向に向きを変えるので、低温冷却材が原子炉の停止
前、上部プレナム内にあった高温の冷却材へ混合してゆ
かず1上部ブレナムの上部に高温冷却材層が、下部に低
温冷却材層が、形成されて、原子炉容器(1)壁等に熱
衝撃を与えるという問題があった。
(Problem to be solved by the invention) During operation of a fast breeder reactor, if the operation is suddenly stopped for some reason, control rods are inserted into the reactor to stop the nuclear reaction. Low-temperature coolant flows into the plenum and gives a thermal shock to the walls of the reactor vessel (1). In order to reduce the thermal shock at this time, an operating method is adopted in which the flow rate of the coolant flowing into the reactor vessel (1) from the artificial nozzle (4) is reduced at the same time as the reactor is stopped. At this time, the conventional fast breeder reactor shown in FIG. 7 has a first-order problem. That is, from the inlet nozzle (4) to the reactor vessel (
1) Reducing the flow rate of coolant flowing into the reactor core (3
) to the upper plenum becomes weaker. At that time, if the flow of low-temperature coolant is upward, the low-temperature coolant will sufficiently mix with the high-temperature coolant that was in the upper plenum before the reactor shutdown, and a layer of high-temperature coolant will form at the top of the upper plenum. However, in the fast breeder reactor shown in FIG. 7, the flow guide member (7) attached to the lower end of the upper reactor mechanism (5) does not form a low-temperature coolant layer at the bottom. is a horizontal plate shape, and the low-temperature coolant with low momentum changes its direction laterally, so the low-temperature coolant does not mix with the high-temperature coolant that was in the upper plenum before the reactor was shut down.1 There was a problem in that a high-temperature coolant layer was formed in the upper part of the upper brenum and a low-temperature coolant layer was formed in the lower part, giving a thermal shock to the reactor vessel (1) wall and the like.

(問題点を解決するための手段) 本発明は前記の問題点に対処するもので、炉心の上面上
方に位置する原子炉上部機構の下端部に開口部を有する
フローガイド部材を取付け、上記炉心から出る冷却材の
温度変化により形状が変化して低温冷却材の流出時に上
記開口部を開(形状記憶合金製ガイド板を上記フローガ
イド部材に取付けたことを特徴とする原子炉に係わり、
その目的とする処は、炉心から高温冷却材が流出する定
格運転時にも、炉心から低温冷却材が流出する原子炉の
急停止時にも、炉心からの冷却材を上部プレナム内の高
温冷却材に充分に混合させることができる改良された原
子炉を供する点にある。
(Means for Solving the Problems) The present invention addresses the above-mentioned problems by attaching a flow guide member having an opening to the lower end of the reactor upper mechanism located above the upper surface of the reactor core. Relating to a nuclear reactor characterized in that a shape memory alloy guide plate is attached to the flow guide member;
The purpose of this is to transfer coolant from the core to high-temperature coolant in the upper plenum, both during rated operation when high-temperature coolant flows out from the core, and during sudden reactor shutdowns when low-temperature coolant flows out from the core. The object of the present invention is to provide an improved nuclear reactor that is capable of sufficient mixing.

(作用) 本発明の原子炉は前記のように構成されており。(effect) The nuclear reactor of the present invention is constructed as described above.

炉心から高温冷却材が流出する定格運転時には。During rated operation when high temperature coolant flows out of the core.

形状記憶合金製ガイド板がフローガイド部材に設けた開
口部を閉じている。そのため1炉心から流出する勢いの
強い高温冷却材がフローガイド部材及び形状記憶合金製
ガイド板に当たって、横方向に流動した後、上昇に転じ
て、上部プレナム内の冷却材と混合しながら上昇を続け
る。また炉心から低温冷却材が流出する原子炉の急停止
時には。
A shape memory alloy guide plate closes the opening provided in the flow guide member. As a result, the powerful high-temperature coolant flowing out from the first reactor hits the flow guide member and the shape memory alloy guide plate, flows laterally, and then begins to rise, mixing with the coolant in the upper plenum as it continues to rise. . Also, during a sudden shutdown of a nuclear reactor where low-temperature coolant flows out from the core.

形状記憶合金製ガイド板の形状が低温冷却材により変化
して、フローガイド部材に設けた開口部が開かれる。そ
のため、炉心から流出する勢いの弱い低温冷却材がフロ
ーガイド部材に設けた開口部内をそのまま上向きに流れ
て、低温冷却材が上部プレナム内の高温冷却材に充分に
混合する。
The shape of the shape memory alloy guide plate is changed by the low temperature coolant to open an opening provided in the flow guide member. Therefore, the low-temperature coolant flowing out from the reactor core flows upward through the opening provided in the flow guide member, and the low-temperature coolant sufficiently mixes with the high-temperature coolant in the upper plenum.

(実施例) 次に本発明の原子炉を第1図乃至第4図に示す一実施例
により説明すると、(3)が原子炉容器内に設けた炉心
1(5)が同炉心(3)の上面上方に位置した原子炉上
部機構、(6)が同原子炉上部機構(5)の下端部に取
付けたフローガイド部材、 (6a)が同フローガイド
部材(6)の外周部に放射状に設けた複数個の開口部、
(8)が同フローガイド部材(6)に−側縁を固定した
形状記憶合金製ガイド板で、同格形状記憶合金製ガイド
板(8)は、上記炉心(3)から出る冷却材の温度変化
により形状が変化して。
(Example) Next, the nuclear reactor of the present invention will be explained with reference to an example shown in FIGS. The reactor upper mechanism (6) is located above the upper surface of the reactor upper mechanism, the flow guide member (6) is attached to the lower end of the reactor upper mechanism (5), and (6a) is radially attached to the outer periphery of the flow guide member (6). multiple openings provided,
(8) is a shape memory alloy guide plate whose negative side edge is fixed to the same flow guide member (6), and the same shape memory alloy guide plate (8) changes the temperature of the coolant coming out of the core (3). The shape changes due to

低温冷却材(300〜400”程度の低温冷却材)の流
出時に上記各開口部(6a)を開くようになっている。
Each opening (6a) is opened when low temperature coolant (low temperature coolant of about 300 to 400'') flows out.

次に前記第1図乃至第4図に示す原子炉の作用を第5.
6図により具体的に説明する。第5図に示すように炉心
(3)から高温冷却材が流出する定格運転時には、形状
記憶合金製ガイド板(8)がフローガイド部材(6)に
設けた開口部(6a)を閉じている。そのため、炉心(
3)から流出する勢いの強い高温冷却材がフローガイド
部材(6)及び形状記憶合金製ガイド板(8)に当たっ
て、横方向に流動した後、上昇に転じて、上部プレナム
内の冷却材と混合しながら上昇を続ける。
Next, the operation of the nuclear reactor shown in FIGS. 1 to 4 will be described in Section 5.
This will be explained in detail with reference to FIG. As shown in Figure 5, during rated operation when high-temperature coolant flows out from the core (3), the shape memory alloy guide plate (8) closes the opening (6a) provided in the flow guide member (6). . Therefore, the reactor core (
The strong high-temperature coolant flowing out from 3) hits the flow guide member (6) and the shape memory alloy guide plate (8) and flows laterally, then turns upward and mixes with the coolant in the upper plenum. continue to rise.

また第6図に示すように炉心(3)から低温冷却材が流
出する原子炉の急停止時には、形状記憶合金製ガイド板
(8)の形状が低温冷却材により変化して、フローガイ
ド部材(6)に設けた開口部(6a)が開かれる。その
ため、炉心(3)から流出する勢いの弱い低温冷却材が
フローガイド部材(6)に設けた開口部(6a)内をそ
のまま上向きに流れて、低温冷却材が上部ブレナム内の
高温冷却材に充分に混合する。
Furthermore, as shown in Fig. 6, during sudden shutdown of the reactor when low-temperature coolant flows out from the reactor core (3), the shape of the shape memory alloy guide plate (8) changes due to the low-temperature coolant, and the flow guide member ( The opening (6a) provided in 6) is opened. Therefore, the low-temperature coolant flowing out from the core (3) flows upward through the opening (6a) provided in the flow guide member (6), and the low-temperature coolant flows into the high-temperature coolant in the upper brenum. Mix thoroughly.

(発明の効果) 本発明の原子炉は前記のように炉心から高温冷却材が流
出する定格運転時には、形状記憶合金製ガイド板がフロ
ーガイド部材に設けた開口部を閉じ、炉心から流出する
勢いの強い高温冷却材がフローガイド部材及び形状記憶
合金製ガイド板に当たって、横方向に流動した後、上昇
に転じて、上部ブレナム内の冷却材と混合しながら上昇
を続ける。また炉心から低温冷却材が流出する原子炉の
急停止時には、形状記憶合金製ガイド板の形状が低温冷
却材により変化して、フローガイド部材に設けた開口部
が開かれ、炉心から流出する勢いの弱い低温冷却材がフ
ローガイド部材に設けた開口部内をそのまま上向きに流
れて、低温冷却材が上部ブレナム内の高温冷却材に充分
に混合するので。
(Effects of the Invention) As described above, in the nuclear reactor of the present invention, during rated operation in which high-temperature coolant flows out from the core, the shape memory alloy guide plate closes the opening provided in the flow guide member, and the flow of high-temperature coolant from the core is accelerated. After the strong high temperature coolant hits the flow guide member and the shape memory alloy guide plate and flows laterally, it begins to rise and continues to rise while mixing with the coolant in the upper brenum. In addition, during a sudden shutdown of a nuclear reactor when low-temperature coolant flows out from the core, the shape of the shape memory alloy guide plate changes due to the low-temperature coolant, openings in the flow guide member are opened, and the flow of low-temperature coolant from the core is accelerated. The weaker low temperature coolant flows upwardly through the openings provided in the flow guide member, and the low temperature coolant mixes well with the high temperature coolant in the upper brenum.

炉心から高温冷却材が流出する定格運転時にも。Even during rated operation when high temperature coolant flows out of the core.

炉心から低温冷却材が流出する原子炉の急停止時にも、
炉心からの冷却材を上部ブレナム内の高温冷却材に充分
に混合させることができる効果がある。
Even in the event of a sudden shutdown of a nuclear reactor where low-temperature coolant flows out from the core,
This has the effect of sufficiently mixing the coolant from the core with the high-temperature coolant in the upper brenum.

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

第1図は本発明に係わる原子炉の一実施例を示す側面図
、第2図は形状記憶合金製ガイド板の開位置を示す縦断
側面図、第3図はフローガイド部材及び形状記憶合金製
ガイド板の平面図、第4図は形状記憶合金製ガイド板の
開位置を示す平面図。 第5図は定格運転時の高温冷却材の流れを示す説明図、
第6図は原子炉の急停止時の低温冷却材の流れを示す説
明図、第7図は従来の原子炉を示す縦断側面図である。 (3)・・・炉心、(5)・・・原子炉上部機構、(6
)・・・フローガイド部材、 (6a)  ・・・開口
部、(8)・・・形状記憶合金製ガイド板。 復代理人弁理士岡本重文外2名 第5図
Fig. 1 is a side view showing an embodiment of the nuclear reactor according to the present invention, Fig. 2 is a longitudinal side view showing the open position of the guide plate made of shape memory alloy, and Fig. 3 is a flow guide member and the shape memory alloy made guide plate. FIG. 4 is a plan view of the guide plate, and FIG. 4 is a plan view showing the shape memory alloy guide plate in the open position. Figure 5 is an explanatory diagram showing the flow of high temperature coolant during rated operation;
FIG. 6 is an explanatory diagram showing the flow of low-temperature coolant during sudden shutdown of a nuclear reactor, and FIG. 7 is a longitudinal side view showing a conventional nuclear reactor. (3)...Reactor core, (5)...Reactor upper mechanism, (6
)...flow guide member, (6a)...opening, (8)...shape memory alloy guide plate. Sub-agent Patent Attorney Shigefumi Okamoto and two others Figure 5

Claims (1)

【特許請求の範囲】[Claims] 炉心の上面上方に位置する原子炉上部機構の下端部に開
口部を有するフローガイド部材を取付け、上記炉心から
出る冷却材の温度変化により形状が変化して低温冷却材
の流出時に上記開口部を開く形状記憶合金製ガイド板を
上記フローガイド部材に取付けたことを特徴とする原子
炉。
A flow guide member having an opening is attached to the lower end of the reactor upper mechanism located above the upper surface of the reactor core, and its shape changes due to temperature changes of the coolant coming out of the core, and the opening is closed when low temperature coolant flows out. A nuclear reactor characterized in that an openable guide plate made of a shape memory alloy is attached to the flow guide member.
JP61112691A 1986-05-19 1986-05-19 Nuclear reactor Pending JPS62269090A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP61112691A JPS62269090A (en) 1986-05-19 1986-05-19 Nuclear reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP61112691A JPS62269090A (en) 1986-05-19 1986-05-19 Nuclear reactor

Publications (1)

Publication Number Publication Date
JPS62269090A true JPS62269090A (en) 1987-11-21

Family

ID=14593071

Family Applications (1)

Application Number Title Priority Date Filing Date
JP61112691A Pending JPS62269090A (en) 1986-05-19 1986-05-19 Nuclear reactor

Country Status (1)

Country Link
JP (1) JPS62269090A (en)

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