JPS6182193A - Automatic reactor stop aggregate - Google Patents

Automatic reactor stop aggregate

Info

Publication number
JPS6182193A
JPS6182193A JP59203864A JP20386484A JPS6182193A JP S6182193 A JPS6182193 A JP S6182193A JP 59203864 A JP59203864 A JP 59203864A JP 20386484 A JP20386484 A JP 20386484A JP S6182193 A JPS6182193 A JP S6182193A
Authority
JP
Japan
Prior art keywords
reactor
absorber
partition plate
capsule
guide tube
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
JP59203864A
Other languages
Japanese (ja)
Inventor
憲一 鈴木
宮木 和美
弘 松本
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
Nippon Atomic Industry Group Co Ltd
Original Assignee
Toshiba Corp
Nippon Atomic Industry Group 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 Toshiba Corp, Nippon Atomic Industry Group Co Ltd filed Critical Toshiba Corp
Priority to JP59203864A priority Critical patent/JPS6182193A/en
Publication of JPS6182193A publication Critical patent/JPS6182193A/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

  • Physical Or Chemical Processes And Apparatus (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】 [発明の技術分野j 本発明は高速増殖炉において、炉心事故の拡大を防1ト
するため11故を自動的に迅速に検出し、炉心をスクラ
ムする自動炉停止集合体にIllする。
Detailed Description of the Invention [Technical Field of the Invention] The present invention provides an automatic reactor shutdown system that automatically and quickly detects 11 failures and scrams the core in order to prevent the spread of core accidents in fast breeder reactors. Ill do it to my body.

し発明の技術的背景とその問題点1 一般に、高速増殖炉では、炉心内に制御棒を挿入するこ
とにより炉心内の反応度の制御が行われている。そして
原子炉の異常時には、この制御棒が炉心内に急速挿入さ
れスクラムが行なわれる。
Technical Background of the Invention and Problem 1 Generally, in fast breeder reactors, the reactivity within the reactor core is controlled by inserting control rods into the reactor core. When an abnormality occurs in the reactor, these control rods are quickly inserted into the reactor core and a scram is performed.

しかしながら、このような制御棒を用いてスクラムを行
なう場合には、炉心内の異常事態を検出し、この検出1
g弓に基づいて制御棒の操作を行なう必要がある。従っ
て、炉心内の異常を検出する検出器等が故障した場合に
は、迅速かつ確実なスクラム動作が行われないおそれが
ある。
However, when performing scram using such control rods, abnormal situations within the reactor core are detected and this detection 1
It is necessary to operate the control rod based on the g-bow. Therefore, if a detector or the like that detects an abnormality in the reactor core fails, there is a risk that a quick and reliable scram operation may not be performed.

[発明の目的] 本発明はかかる従来の事情に対処してなされたもので、
事故を自動的にかつ迅速に検出し、原子炉をスクラムす
ることのでさる自動炉停止集合体を促供しようとするも
のである。
[Object of the invention] The present invention has been made in response to such conventional circumstances,
It seeks to facilitate automatic reactor shutdown assembly by automatically and quickly detecting accidents and scramming the reactor.

[発明の概要] すなわら本発明は、下端に冷lJI材流入口を、上端に
冷却材流出口を備えた中空状の案内管と、この案内管内
に収容され前記冷lJ目A流入口から流入する冷却材の
流量の低下に伴い下方に落下する中性子吸収体と、前記
案内管内に配置され前記中性子吸収体の上方および下方
への移動をそれぞれ阻IFする上部仕切板および下部仕
切板とを備えたことを特慝とする自動炉停止集合体であ
る。
[Summary of the Invention] In other words, the present invention provides a hollow guide tube having a cold lJI material inlet at the lower end and a coolant outlet at the upper end, and the cold IJI material inlet housed in the guide tube. a neutron absorber that falls downward as the flow rate of the coolant flowing in from the neutron absorber decreases, and an upper partition plate and a lower partition plate that are arranged in the guide tube and block the upward and downward movement of the neutron absorber, respectively. This is an automatic reactor shutdown assembly that is specially designed to be equipped with:

[発明の実施例] 以下本発明の詳細を図面に示す一実施例について説明す
る。
[Embodiment of the Invention] The details of the present invention will be described below with reference to an embodiment shown in the drawings.

第1図および第2図は本発明の一実施例の自動炉停止集
合体を示すもので、図において符号1は下端に冷IJI
材流入口2を、上端に冷却材流出口3を備えた六角中空
状の案内管を示している。
Figures 1 and 2 show an automatic reactor shutdown assembly according to an embodiment of the present invention.
A hexagonal hollow guide tube is shown with a coolant inlet 2 and a coolant outlet 3 at its upper end.

この案内管1内には、例えばボロンからなる中性子吸収
体4を多数収容する吸収体カプセル5が収容されている
。吸収体カプセル5の上部には、この吸収体カプセル5
の上方への移動を阻止する上部仕切板6が配置され、ま
た吸収体カプセル5の下部には、この吸収体カプセル5
のF方への移動を阻止づ゛る下部仕切板7が配設されて
いる。
This guide tube 1 accommodates an absorber capsule 5 that accommodates a large number of neutron absorbers 4 made of, for example, boron. This absorbent capsule 5 is placed on the upper part of the absorbent capsule 5.
An upper partition plate 6 is disposed to prevent upward movement of the absorbent capsule 5.
A lower partition plate 7 is disposed to prevent the movement of the frame in the F direction.

しかして、吸収体ノツプセル5の密度は冷JJI祠流入
口2から流入する冷却材8の流量が一定値より高いとき
に吸収体カブヒル5の上端が上部仕切板6に接触し、一
方、前)ホした一定値より低いときに吸収体カブピル5
の下端が下部仕切板7に接触するJ−うな密度とされて
いる。
Therefore, the density of the absorber top cell 5 is such that when the flow rate of the coolant 8 flowing in from the cold JJI shrine inlet 2 is higher than a certain value, the upper end of the absorber dip cell 5 comes into contact with the upper partition plate 6; Absorber Kabu Pill 5 when it is lower than a certain value
The lower end of the lower end contacts the lower partition plate 7, which has a J-shaped density.

すなわち、第3図の曲線aに示すように、横軸に時間を
縦軸に冷却材の流量をとって示すと、冷却材流mが定格
時のWOから部分口荷時最低流聞のWeの間においては
、吸収体カプセル5は上部仕切板6に当接し、冷却材流
量がWC以下となる時間TcとTbの間において、吸収
体カプセル5が下降し下部仕切板7に当接するような密
度とされている。
That is, as shown in curve a in Fig. 3, when the horizontal axis represents time and the vertical axis represents the coolant flow rate, the coolant flow m varies from WO at the rated time to We at the lowest flow rate at partial loading. During this period, the absorber capsule 5 contacts the upper partition plate 6, and between the time Tc and Tb when the coolant flow rate becomes equal to or less than WC, the absorber capsule 5 descends and contacts the lower partition plate 7. It is considered to be the density.

以上のように構成された自動炉停止集合体では、第3図
の曲線aに示すように、何らかの異常事態により、例え
ば液体金属ナトリウムからなる冷却材の流量が徐々に低
下し、部分負荷時の最低流量WCより低下すると、時刻
下Cから、例えば数秒〜数10秒後には吸収体カプセル
5が下方に落下し下部仕切板7に接触することとなる。
In the automatic reactor shutdown assembly configured as described above, as shown by curve a in Figure 3, due to some abnormal situation, the flow rate of the coolant made of liquid metal sodium, for example, gradually decreases, and the When the flow rate falls below the minimum flow rate WC, the absorbent capsule 5 falls downward and comes into contact with the lower partition plate 7, for example, several seconds to several tens of seconds after the time C.

これにより吸収体カプセル5は、高速増殖炉の燃料部の
ほぼ中心位置に、その中心を位置することとなり、炉心
内に負の反応度が印加されることとなる。この結果、炉
は自動的に停止し、炉心溶融に至るような大事故を未然
に防止することができる。
As a result, the center of the absorber capsule 5 is located approximately at the center of the fuel section of the fast breeder reactor, and negative reactivity is applied within the reactor core. As a result, the reactor will automatically stop, making it possible to prevent a major accident that could lead to a core meltdown.

Jなわら、以上のように(t1成された自動炉停止集合
体では、冷却材の流量の低下、炉心流量の低下により外
部からの瞭vトを行なうことなく自動的に、かつ迅速に
スクラムを行なうことができる1゜第4図J3よび第5
図は本発明の他の実施例を示づもので、この実施例では
案内管1を囲繞して燃料部9が配置されている。
However, as mentioned above, in the automatic reactor shutdown assembly that has been completed (t1), due to the decrease in the coolant flow rate and the decrease in the core flow rate, the scram can be automatically and quickly performed without any external monitoring. 1゜Figure 4 J3 and 5
The figure shows another embodiment of the present invention, in which a fuel section 9 is arranged surrounding the guide tube 1.

寸なわら、この実施例の自動炉停止集合体は、ラッパ管
10内に案内管1を挿通しIζ形状をしている。案内管
1とラッパ笥10との間には軸プランケラ[・部11、
燃料部12が形成されている。
The automatic furnace shutdown assembly of this embodiment has a guide tube 1 inserted into a wrapper tube 10 and has an Iζ shape. Between the guide tube 1 and the trumpet tray 10, there is a shaft plancher [・part 11,
A fuel section 12 is formed.

また、本実施例では、吸収体カブ亡ル5の上部および下
部にlよりブUルの密度調整のためのへりラムガスを収
容する部分13が形成されている。
Further, in this embodiment, portions 13 are formed at the upper and lower portions of the absorber cover 5 to accommodate hem ram gas for adjusting the density of the bubble.

以上のように構成された自動炉停止集合体では、原子炉
の通常運転時、すなわち、炉心流量が一定値以上のとき
には吸収体カプセル5の上端は上部仕切板6に当接し、
吸収体カブLル5は軸ブランケツト部11に位置してい
る。
In the automatic reactor shutdown assembly configured as described above, during normal operation of the reactor, that is, when the core flow rate is above a certain value, the upper end of the absorber capsule 5 comes into contact with the upper partition plate 6,
The absorber cover L5 is located in the shaft blanket part 11.

一方、炉心流量が一定1に+より低下した場合には、第
6図に示″tjJ:うに、吸収体カブヒル5は降下し、
その中央部を燃料部12の中央部に位置するJ、うな状
態におかれる。これにより炉は自動的に停止し炉心溶融
に至るような大事故を防止することができる。
On the other hand, when the core flow rate decreases to a constant value of 1, the absorber Cub Hill 5 descends as shown in FIG.
The central part is placed in an upright position J located at the central part of the fuel part 12. This allows the reactor to automatically shut down and prevent a major accident that could lead to a core meltdown.

第7図および第8図は内部ブランケット部14を有する
炉心に好適する本発明の自動炉停止集合体の一実施例を
示すもので、この実施例では吸収体カプセル15には、
中央部に冷却材を流入する冷fJ1材流入口16を備え
たカプセル密度調整部17が配置され、この両側に中性
子吸収体4が収容される吸収体部5が形成されている。
7 and 8 show an embodiment of the automatic reactor shutdown assembly of the present invention suitable for a reactor core having an internal blanket section 14. In this embodiment, the absorber capsule 15 includes:
A capsule density adjusting section 17 having a cold fJ1 material inlet 16 through which a coolant flows is arranged in the center, and absorber sections 5 in which neutron absorbers 4 are accommodated are formed on both sides of the capsule density adjusting section 17 .

以上のように構成された自動炉停止集合体では、原子炉
の通常運転時には吸収体カプセル15は、第7図に承り
ように、軸ブランケツト11側方に位置している。
In the automatic reactor shutdown assembly constructed as described above, the absorber capsule 15 is located on the side of the shaft blanket 11, as shown in FIG. 7, during normal operation of the nuclear reactor.

一方、炉心流量の低下時には、第8図に示すように、吸
収体カプセル15は落下しカプセル密度調整部17が内
部ブランケット14の側方に位置する状態とされる。こ
れにより炉は自動的に停止し、炉心溶融に至るような大
事故を防止づ゛ることができる。
On the other hand, when the core flow rate decreases, as shown in FIG. 8, the absorber capsule 15 falls and the capsule density adjustment section 17 is placed on the side of the internal blanket 14. This will automatically shut down the reactor and prevent a major accident that could lead to a core meltdown.

第9図および第10図は、本発明のさらに他の実施例を
示ずもので、この実施例では案内管1の下部仕切板7の
下方に燃料部9が配置されている。
9 and 10 do not show yet another embodiment of the present invention, in which a fuel section 9 is disposed below the lower partition plate 7 of the guide tube 1.

また、吸収体カプセル18は吸収体カプセル18の上下
にヘリウムガスを収容するガス収納部19が形成されて
いる。
Further, the absorbent capsule 18 has gas storage portions 19 formed above and below the absorbent capsule 18 for storing helium gas.

以上のように構成されlζ自動炉ヒ;5北東合体では、
原子炉の通常運転時には吸収体カプセル18は軸ブラン
ケツト部11の側方に配置される。
In the above-mentioned configuration, the automatic furnace is
During normal operation of the nuclear reactor, the absorber capsule 18 is placed on the side of the shaft blanket section 11.

一方 炉心流…が低下すると、吸収体カプセル18は第
10図に示すように、その下端を下部仕切板7に当接し
、下方の燃料部9から上方へ漏れ出る中性子を吸収する
。さらに第9図に示す燃料部12からの中性子も吸収す
る。これにより炉は自動的に停止し、炉心溶融に至るよ
うな大事故を防止することができる。
On the other hand, when the core flow decreases, the lower end of the absorber capsule 18 comes into contact with the lower partition plate 7, as shown in FIG. 10, and absorbs the neutrons leaking upward from the fuel section 9 below. Furthermore, neutrons from the fuel section 12 shown in FIG. 9 are also absorbed. This will automatically shut down the reactor and prevent a major accident that could lead to a core meltdown.

[発明の効果] 以上述べたように本発明の自動炉停止集合体によれば、
自動炉停止集合体自体に冷却材流量の減少事故を自動的
にかつ迅速に検出する橢能を持だせたので、どのような
事態が生じても炉を自動的に停止することができ、炉心
溶融に至るような大事故を確実に防止することができる
[Effect of the invention] As described above, according to the automatic reactor shutdown assembly of the present invention,
Because the automatic reactor shutdown assembly itself has the ability to automatically and quickly detect a coolant flow rate reduction accident, it is possible to automatically shut down the reactor no matter what situation occurs, and the reactor core Major accidents that may lead to melting can be reliably prevented.

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

第1図は本発明の自動炉停止集合体の一実施例を示す縦
断面図、第2図は第1図の上面図、第3図は炉心流量の
減少を示づ”グラフ、第4図は本発明の自動炉停止集合
体の他の実施例を示す縦断面図、第5図は第4図の上面
図、第6図は第4図に    ・おいて炉心流量が低下
したときの吸収体カプセルの状態を示す縦断面図、第7
図は本発明の自動炉停北東81ホのさらに他の実施例を
示す1lJlvi面図、第8図は第7図におい【炉心流
6足が低下した。ときの状態をテリー縦断面図、第9図
は本発明の自動炉停止集合体の他の実施例を示す縦断面
図、第10図は第9図にa3いて炉心流量が低下したと
きの吸収体カプセルの状態を示す縦断面図である。 1・・・・・・・・・・・・案内管 2・・・・・・・・・・・・冷却材流入口3・・・・・
・・・・・・・冷ノ」1材流出口4・・・・・・・・・
・・・中性子吸収体5・・・・・・・・・・・・吸収体
カブじル6・・・・・・・・・・・・、F部(シ:切板
7・・・・・・・・・・・・下部仕切板9・・・・・・
・・・・・・燃利部 代理人弁即士   煩 山 (11− 第1図 第3図
FIG. 1 is a vertical cross-sectional view showing an embodiment of the automatic reactor shutdown assembly of the present invention, FIG. 2 is a top view of FIG. 1, and FIG. 3 is a graph showing a decrease in core flow rate. 5 is a vertical cross-sectional view showing another embodiment of the automatic reactor shutdown assembly of the present invention, FIG. 5 is a top view of FIG. 4, and FIG. Longitudinal cross-sectional view showing the state of the body capsule, No. 7
The figure is a 11Jlvi plane view showing still another embodiment of the automatic reactor shutdown northeast 81 of the present invention, and FIG. 8 is the same as that in FIG. 7. FIG. 9 is a vertical cross-sectional view showing another embodiment of the automatic reactor shutdown assembly of the present invention, and FIG. FIG. 3 is a longitudinal cross-sectional view showing the state of the body capsule. 1...Guide pipe 2...Coolant inlet 3...
......Cold material 1 material outlet 4...
...Neutron absorber 5...Absorber cover 6...F section (C: Cutting plate 7...・・・・・・Lower partition plate 9・・・・・・
・・・・・・Fuel Dept. Agent, Bentoyama (11- Fig. 1 Fig. 3)

Claims (3)

【特許請求の範囲】[Claims] (1)下端に冷却材流入口を、上端に冷却材流出口を備
えた中空状の案内管と、この案内管内に収容され前記冷
却材流入口から流入する冷却材の流量の低下に伴い下方
に落下する中性子吸収体と、前記案内管内に配置され前
記中性子吸収体の上方および下方への移動をそれぞれ阻
止する上部仕切板および下部仕切板とを備えたことを特
徴とする自動炉停止集合体。
(1) A hollow guide tube with a coolant inlet at the lower end and a coolant outlet at the upper end; An automatic reactor shutdown assembly characterized by comprising a neutron absorber that falls into the guide tube, and an upper partition plate and a lower partition plate that are arranged in the guide tube and prevent upward and downward movement of the neutron absorber, respectively. .
(2)案内管を囲繞して燃料部を配置してなる特許請求
の範囲第1項記載の自動炉停止集合体。
(2) The automatic reactor shutdown assembly according to claim 1, wherein the fuel section is arranged to surround the guide pipe.
(3)案内管の下部仕切板の下方に燃料部を配置してな
る特許請求の範囲第1項記載の自動炉停止集合体。
(3) The automatic reactor shutdown assembly according to claim 1, wherein the fuel section is disposed below the lower partition plate of the guide tube.
JP59203864A 1984-09-28 1984-09-28 Automatic reactor stop aggregate Pending JPS6182193A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP59203864A JPS6182193A (en) 1984-09-28 1984-09-28 Automatic reactor stop aggregate

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP59203864A JPS6182193A (en) 1984-09-28 1984-09-28 Automatic reactor stop aggregate

Publications (1)

Publication Number Publication Date
JPS6182193A true JPS6182193A (en) 1986-04-25

Family

ID=16480964

Family Applications (1)

Application Number Title Priority Date Filing Date
JP59203864A Pending JPS6182193A (en) 1984-09-28 1984-09-28 Automatic reactor stop aggregate

Country Status (1)

Country Link
JP (1) JPS6182193A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US6804320B2 (en) * 2002-04-12 2004-10-12 Bechtel Bwxt Idaho, Llc Automatically scramming nuclear reactor system

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US6804320B2 (en) * 2002-04-12 2004-10-12 Bechtel Bwxt Idaho, Llc Automatically scramming nuclear reactor system

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