JPH0385496A - fast breeder reactor - Google Patents

fast breeder reactor

Info

Publication number
JPH0385496A
JPH0385496A JP1223710A JP22371089A JPH0385496A JP H0385496 A JPH0385496 A JP H0385496A JP 1223710 A JP1223710 A JP 1223710A JP 22371089 A JP22371089 A JP 22371089A JP H0385496 A JPH0385496 A JP H0385496A
Authority
JP
Japan
Prior art keywords
heat exchangers
core
reactor
intermediate heat
reactor core
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
JP1223710A
Other languages
Japanese (ja)
Inventor
Junko Matsuda
淳子 松田
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
Toshiba Corp
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 filed Critical Toshiba Corp
Priority to JP1223710A priority Critical patent/JPH0385496A/en
Publication of JPH0385496A publication Critical patent/JPH0385496A/en
Pending legal-status Critical Current

Links

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

  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

PURPOSE:To enable detection of delayed neutrons within a predetermined time interval at any place by providing delayed neutron detection (a DN method) units of a single point sampling method, placed at a periphery of a reactor core side coolant inlet window of an intermediate heat exchanger and between the most departed heat exchangers. CONSTITUTION:In case that reactor core fuels are damaged at parts facing intermediate heat exchangers 3a to 3d, precursor nucleons of discharged delayed neutrons can be detected by DN method units 21a to 21d provided at a periphery of a reactor core 5 side coolant inlet window 7 of each heat exchanger 3a to 3d. Also, in case that the reactor core fuels located at parts between the most departed heat exchangers 3a and 3b, and 3c and 3d, are damaged, the precursor of delayed neutrons in the coolant, can be detected by the DN method units 21e and 21f provided between the heat exchangers 3a and 3b, and, 3c and 3d. Accordingly, for fuel damages in any place in the reactor core 5, the precursor of discharged delayed neutrons can be detected within a predetermined time interval and a trip signal is generated and therefore safety and reliability are much improved. Furthermore, as the units 21a to 21f are made to be of a single point sampling type, they can be withdrawn from the reactor core, and maintainability is also much improved.

Description

【発明の詳細な説明】 [発明の目的] (産業上の利用分野) 本発明は高速増殖炉に係り、特に破損燃料の検出手段に
関するものである。
DETAILED DESCRIPTION OF THE INVENTION [Object of the Invention] (Industrial Field of Application) The present invention relates to fast breeder reactors, and particularly to means for detecting damaged fuel.

(従来の技術) 冷却材として液体ナトリウム等の液体金属を用いるタン
ク型高速増殖炉は、第5図および第6図に示すように原
子炉容器1の上部開口を閉塞するルーフスラブ2上に複
数台の中間熱交換器3a。
(Prior Art) A tank-type fast breeder reactor that uses liquid metal such as liquid sodium as a coolant has a plurality of holes on a roof slab 2 that closes the upper opening of a reactor vessel 1, as shown in FIGS. 5 and 6. Intermediate heat exchanger 3a.

3b、3c、3dと冷却材循環ポンプ4a、4b。3b, 3c, 3d and coolant circulation pumps 4a, 4b.

4c、4dを同一円周上に交互に搭載した構造となって
おり、原子炉容器1内に収納された炉心5の上方には制
御棒駆動機構等を内包した炉心上部機構6が設けられて
いる。そして、上記中間熱交換器3a、3b+ 3c、
3dには冷却材が流入する冷却材入口窓7が設けられ、
この冷却材入口窓7から中間熱交換器3a、3b、3c
、3d内に流入した冷却材は伝熱管を介して2次冷却材
と熱交換され、低温となってコールドプレナム8に流出
するようになっている。一方、コールドブレナム8内の
冷却材は冷却材循環ポンプ4a、4b。
4c and 4d are mounted alternately on the same circumference, and above the reactor core 5 housed in the reactor vessel 1 is a core upper mechanism 6 containing a control rod drive mechanism, etc. There is. and the intermediate heat exchangers 3a, 3b+3c,
3d is provided with a coolant inlet window 7 through which the coolant flows;
From this coolant inlet window 7 to intermediate heat exchangers 3a, 3b, 3c.
, 3d is heat-exchanged with the secondary coolant through the heat transfer tube, and flows out into the cold plenum 8 at a low temperature. On the other hand, the coolant inside the cold brenum 8 is supplied by coolant circulation pumps 4a and 4b.

4C* 4dに吸い込まれ、炉内配管9および高圧ブレ
ナム10を通って炉心5内に流入し、炉心5内を上昇す
る間に高温に加熱されてホットブレナム11に流出する
。そして、炉心5からホットブレナム11に流出した冷
却材は再び冷却材人口窓7から中間熱交換器3a、3b
、3c、3d内に流入し、上述した流路を循環するよう
になっている。
4C* is sucked into 4d, flows into the reactor core 5 through the in-furnace piping 9 and the high-pressure blemish 10, is heated to a high temperature while rising in the reactor core 5, and flows out into the hot blemish 11. Then, the coolant flowing out from the core 5 to the hot blemish 11 is returned to the intermediate heat exchangers 3a and 3b through the coolant artificial window 7.
, 3c, and 3d, and circulate through the above-mentioned channels.

また、このように構成される高速増殖炉は炉心燃料の破
損を検知するために破損燃料から放出される遅発中性子
先行核を検出する遅発中性子検出ユニット(以下DN法
ユニツトという)12が各中間熱交換器3a、3b、3
c、3dの近傍に設けられている。このDN法ユニット
12は冷却材人口窓7の周囲に配設されたリング状のサ
ンプリング管13と、このサンプリング管13でサンプ
リングされた冷却材を分析するユニット本体14とから
構成され、例えば第7図に示すように炉内の冷却材を電
磁ポンプ15によりサンプリング管13を通してサンプ
リングチェンバー16内に導入し、このサンプリングチ
ェンバー16内に導入された冷却材中の遅発中性子先行
核を中性子検出器17で検出するように構成されている
(発明が解決しようとする課題) ところで、このような高速増殖炉の炉心5から流出する
冷却材のうち中間熱交換器3 a r  3 b r3
c、3dと対向する部分から流出する冷却材は中間熱交
換器3a、3b、3c、3dの冷却材人口窓7に直接流
入するが、それ以外の部分から流出する冷却材は原子炉
容器壁に向かって流れた後、原子炉容器壁に沿って冷却
材液面近傍まで上昇し、さらに原子炉容器壁から中間熱
交換器3a、3b。
In addition, in the fast breeder reactor configured in this way, each unit is equipped with a delayed neutron detection unit (hereinafter referred to as a DN method unit) 12 that detects delayed neutron leading nuclei emitted from the damaged fuel in order to detect damage to the core fuel. Intermediate heat exchanger 3a, 3b, 3
It is provided near c and 3d. This DN method unit 12 is composed of a ring-shaped sampling tube 13 disposed around the coolant population window 7, and a unit body 14 that analyzes the coolant sampled by the sampling tube 13. As shown in the figure, the coolant in the reactor is introduced into the sampling chamber 16 through the sampling tube 13 by the electromagnetic pump 15, and the delayed neutron leading nuclei in the coolant introduced into the sampling chamber 16 are detected by the neutron detector 17. By the way, among the coolant flowing out from the core 5 of such a fast breeder reactor, the intermediate heat exchanger 3 a r 3 b r3
The coolant flowing out from the portions facing c and 3d directly flows into the coolant artificial windows 7 of the intermediate heat exchangers 3a, 3b, 3c, and 3d, but the coolant flowing out from other portions flows into the reactor vessel wall. After flowing toward the reactor vessel wall, it rises to near the coolant liquid level, and then flows from the reactor vessel wall to the intermediate heat exchangers 3a and 3b.

3c、3dに向かう水平流となる。このため、たとえば
最も間隔の離れている中間熱交換器3aと3b及び3c
と3dの間に位置する炉心燃料が破損した場合には破損
部分から流出した冷却材が中間熱交換器3a、3b、3
c、3dに到達するまでの時間が長く、DN法の要求機
能から冷却材中の遅発中性子先行核を所定時間内に検出
して原子炉トリップ信号を発することが困難となる問題
があった。
The flow becomes horizontal toward 3c and 3d. For this reason, for example, the intermediate heat exchangers 3a, 3b, and 3c that are farthest apart
If the core fuel located between
There was a problem that it took a long time to reach neutrons c and 3d, and it was difficult to detect delayed neutron leading nuclei in the coolant and issue a reactor trip signal within a predetermined time due to the functions required by the DN method. .

また、従来のDN法ユニット12は中間熱交換器3a、
3b、3c、3dの周囲にリング状のサンプリング管1
3を設置していたため、万−DN法ユニット12が故障
した場合には炉内から引き抜くことができなかった。
Further, the conventional DN method unit 12 includes an intermediate heat exchanger 3a,
Ring-shaped sampling tube 1 around 3b, 3c, 3d
3 was installed, so if the 10,000-DN method unit 12 failed, it could not be removed from the furnace.

本発明はこのような事情に鑑みてなされたもので、炉心
のどの位置で燃料破損が生じても破損燃料から放出され
る遅発中性子先行核を所定時間内に検出でき、かつDN
法ユニットを炉内から引き抜くことのできる高速増殖炉
を提供することを目的とする。
The present invention has been developed in view of these circumstances, and is capable of detecting delayed neutron leading nuclei emitted from the damaged fuel within a predetermined time no matter where fuel damage occurs in the reactor core.
An object of the present invention is to provide a fast breeder reactor in which a method unit can be pulled out from inside the reactor.

[発明の構成] (課題を解決するための手段) 上記目的を達成するために本発明は、原子炉と、この原
子炉容器内に収納された炉心の周囲に配設された複数台
の中間熱交換器と、これらの中間熱交換器の間に配設さ
れた複数台の冷却材循環ポンプと、前記炉心の上方に設
けられた炉心上部機構とを有する高速増殖炉において、
前記炉心の破損燃料から放出される遅発中性子先行核を
検出するDN法ユニットを1点サンプリング方式とし、
この1点サンプリング方式のDN法ユニットを前記各中
間熱交換器の炉心側の冷却材入口窓近傍および最も間隔
の離れた2台の中間熱交換器の間に設置したものである
。
[Structure of the Invention] (Means for Solving the Problem) In order to achieve the above object, the present invention provides a nuclear reactor and a plurality of intermediate units disposed around the reactor core housed in the reactor vessel. In a fast breeder reactor having a heat exchanger, a plurality of coolant circulation pumps arranged between these intermediate heat exchangers, and a core upper mechanism provided above the reactor core,
A DN method unit for detecting delayed neutron leading nuclei released from the damaged fuel of the reactor core is a one-point sampling method,
This one-point sampling type DN method unit is installed near the coolant inlet window on the core side of each intermediate heat exchanger and between the two intermediate heat exchangers that are farthest apart.

(作 用) すなわち、本発明はDN法ユニットを1点サンプリング
方式とすることにより、万−DN法ユニットが故障した
場合でも炉内から引き抜くことができ、DN法ユニット
の保守性を高めることができる。また、1点サンプリン
グ方式のDN法ユニットを各中間熱交換器の炉心側の冷
却材入口窓近傍および最も間隔の離れた2台の中間熱交
換器の間に設置することにより、炉心のどの位置で燃料
破損が生じても破損燃料から放出される遅発中性子先行
核を所定時間内に検出することができ、原子炉の安全性
および信頼性を高めることができる。
(Function) That is, in the present invention, by making the DN method unit a one-point sampling method, even if the DN method unit breaks down, it can be pulled out from the furnace, and the maintainability of the DN method unit can be improved. can. In addition, by installing a single-point sampling DN method unit near the coolant inlet window on the core side of each intermediate heat exchanger and between the two intermediate heat exchangers that are farthest apart, it is possible to Even if a fuel failure occurs in a nuclear reactor, delayed neutron precursor nuclei emitted from the damaged fuel can be detected within a predetermined time, thereby increasing the safety and reliability of the nuclear reactor.

(実施例) 以下、図面を参照して本発明の詳細な説明する。(Example) Hereinafter, the present invention will be described in detail with reference to the drawings.

第1図および第2図は本発明の一実施例を示し、この実
施例ではルーフスラブ2上に搭載された各中間熱交換器
3a、3b、3c、3dの炉心5側の冷却材人口窓7の
近傍に1点サンプリング方式%式% 21dを設置し、さらに最も間隔の離れている2台の中
間熱交換器3aと3b及び3Cと3dとの間に1点サン
プリング方式のDN法ユニット21e、21fを設置し
て燃料破損を検知する構造となっている。
FIG. 1 and FIG. 2 show an embodiment of the present invention, and in this embodiment, coolant artificial windows on the core 5 side of each intermediate heat exchanger 3a, 3b, 3c, 3d mounted on the roof slab 2 are shown. A one-point sampling type DN method unit 21d is installed near 7, and a one-point sampling type DN method unit 21e is installed between the two intermediate heat exchangers 3a and 3b and 3C and 3d that are the most distant from each other. , 21f are installed to detect fuel damage.

このような構成によると、炉心5から流出する冷却材の
うち中間熱交換器3 a、 3 b、 3 C*3dと
対向する部分から流出する冷却材は第3図および第4図
に示すように中間熱交換器3a。
According to such a configuration, among the coolant flowing out from the core 5, the coolant flowing out from the portions facing the intermediate heat exchangers 3a, 3b, 3C*3d is as shown in FIGS. 3 and 4. and an intermediate heat exchanger 3a.

3b、3c、3dの冷却材入口窓7に直接吸い込まれる
ので、中間熱交換器3a、3b、3c。
Intermediate heat exchangers 3a, 3b, 3c because the coolant is directly sucked into the inlet windows 7 of 3b, 3c, 3d.

3dと対向する部分で炉心燃料が破損した場合には破損
燃料から放出される遅発中性子先行核を各中間熱交換器
3a、3b、3c、3dの炉心5側の冷却材入口窓7の
近傍に設置されたDN法ユニット21a、21b、21
c、21dで検出することができる。また、最も間隔の
離れている2台の中間熱交換器3aと3b及び3cと3
dとの間に位置する部分の炉心燃料が破損した場合には
中間熱交換器3aと3bおよび3cと3dの間に設置さ
れたDN法ユニット21e、21fによって冷却材中の
遅発中性子先行核を検出することができる。
When the reactor core fuel is damaged in the part opposite to the reactor core 3d, the delayed neutron leading nuclei released from the damaged fuel are transferred to the vicinity of the coolant inlet window 7 on the core 5 side of each intermediate heat exchanger 3a, 3b, 3c, and 3d. DN method units 21a, 21b, 21 installed in
c, 21d. In addition, the two intermediate heat exchangers 3a and 3b and 3c and 3 that are the most distant from each other are
If the core fuel located between can be detected.

したがってく本実施例では炉心5のどの位置で燃料破損
が生じても破損燃料から放出される遅発中性子先行核を
所定時間内に検出して原子炉トリップ信号を発すること
が可能となるので、原子炉の安全性および信頼性を高め
ることができる。また、本実施例ではDN法ユニット2
1&、21b。
Therefore, in this embodiment, even if fuel failure occurs at any position in the reactor core 5, it is possible to detect delayed neutron leading nuclei emitted from the damaged fuel within a predetermined time and issue a reactor trip signal. The safety and reliability of nuclear reactors can be improved. In addition, in this embodiment, the DN method unit 2
1&, 21b.

21c、21d、21e、21fを1点サンプリング方
式としたので、DN法ユニット21a。
Since 21c, 21d, 21e, and 21f are of the one-point sampling method, the DN method unit 21a.

21b、21c、21d、21e、21fを炉内から引
き抜くことができ、DN法ユニット21a。
21b, 21c, 21d, 21e, and 21f can be pulled out from inside the furnace, and the DN method unit 21a.

21b、21c、21d、21e、21 fの保守性の
向上を図ることができる。
The maintainability of 21b, 21c, 21d, 21e, and 21f can be improved.

[発明の効果] 以上説明したように本発明によれば、炉心のどの位置で
燃料破損が生じても破損燃料から放出される連発中性子
を所定時間内に検出でき、しかもDN法ユニットを炉内
から引き抜くことのできるので、原子炉の安全性および
信頼性を高めることができると共にDN法ユニットの保
守性の向上を図ることができる。
[Effects of the Invention] As explained above, according to the present invention, continuous neutrons emitted from the damaged fuel can be detected within a predetermined time no matter where fuel damage occurs in the reactor core. Since it can be extracted from the reactor, the safety and reliability of the nuclear reactor can be improved, and the maintainability of the DN method unit can be improved.

【図面の簡単な説明】 第1図は本発明の一実施例を示す高速増殖炉の縦断面図
、第2図はその平面図、第3図および第4図は同実施例
の作用説明図、第5図は従来の高速増殖炉の縦断面図、
第6図は −MI4=DN法ユニットの構成図である。 1・・・原子炉容器、2・・・ルーフスラブ、3a〜3
d・・・中間熱交換器、4a〜4d・・・冷却材循環ポ
ンプ、5・・・炉心、6・・・炉心上部機構、7・・・
冷却材入口窓、8・・・コールドブレナム、9・・・炉
内配管、10・・・高圧ブレナム、11・・・ホットブ
レナム、21a〜21f・・・DN法ユニット。
[Brief Description of the Drawings] Fig. 1 is a longitudinal sectional view of a fast breeder reactor showing an embodiment of the present invention, Fig. 2 is a plan view thereof, and Figs. 3 and 4 are explanatory diagrams of the operation of the same embodiment. , Figure 5 is a vertical cross-sectional view of a conventional fast breeder reactor.
FIG. 6 is a configuration diagram of the -MI4=DN method unit. 1... Reactor vessel, 2... Roof slab, 3a-3
d... Intermediate heat exchanger, 4a to 4d... Coolant circulation pump, 5... Core, 6... Core upper mechanism, 7...
Coolant inlet window, 8...Cold blennium, 9...In-furnace piping, 10...High pressure blennium, 11...Hot blennium, 21a to 21f...DN method unit.

Claims (1)

【特許請求の範囲】[Claims] 原子炉容器と、この原子炉容器内に収納された炉心と、
上記原子炉容器の上部開口を閉塞するルーフスラブと、
このルーフスラブ上に搭載され前記炉心の周囲に配設さ
れた複数台の中間熱交換器と、これらの中間熱交換器の
間に配設された複数台の冷却材循環ポンプと、前記炉心
の上方に設けられた炉心上部機構とを有する高速増殖炉
において、前記炉心の破損燃料から放出される遅発中性
子先行核を検出するDN法ユニットを1点サンプリング
方式とし、この1点サンプリング方式のDN法ユニット
を前記各中間熱交換器の炉心側の冷却材入口窓近傍およ
び最も間隔の離れた2台の中間熱交換器の間に設置した
ことを特徴とする高速増殖炉。
A reactor vessel, a reactor core housed within the reactor vessel,
a roof slab that closes the upper opening of the reactor vessel;
A plurality of intermediate heat exchangers mounted on the roof slab and disposed around the core, a plurality of coolant circulation pumps disposed between these intermediate heat exchangers, and a plurality of coolant circulation pumps disposed around the core. In a fast breeder reactor having an upper core mechanism installed above, the DN method unit for detecting delayed neutron leading nuclei emitted from the damaged fuel in the core is of a one-point sampling method, and the DN of this one-point sampling method is A fast breeder reactor, characterized in that a method unit is installed near the coolant inlet window on the core side of each of the intermediate heat exchangers and between the two intermediate heat exchangers that are farthest apart.
JP1223710A 1989-08-30 1989-08-30 fast breeder reactor Pending JPH0385496A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP1223710A JPH0385496A (en) 1989-08-30 1989-08-30 fast breeder reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP1223710A JPH0385496A (en) 1989-08-30 1989-08-30 fast breeder reactor

Publications (1)

Publication Number Publication Date
JPH0385496A true JPH0385496A (en) 1991-04-10

Family

ID=16802454

Family Applications (1)

Application Number Title Priority Date Filing Date
JP1223710A Pending JPH0385496A (en) 1989-08-30 1989-08-30 fast breeder reactor

Country Status (1)

Country Link
JP (1) JPH0385496A (en)

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