JPH08292284A - Pressure pipe type heavy water reactor facility - Google Patents

Pressure pipe type heavy water reactor facility

Info

Publication number
JPH08292284A
JPH08292284A JP7099230A JP9923095A JPH08292284A JP H08292284 A JPH08292284 A JP H08292284A JP 7099230 A JP7099230 A JP 7099230A JP 9923095 A JP9923095 A JP 9923095A JP H08292284 A JPH08292284 A JP H08292284A
Authority
JP
Japan
Prior art keywords
water
type heavy
pressure
heavy water
calandria tank
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
JP7099230A
Other languages
Japanese (ja)
Inventor
Akira Susuki
晃 須々木
Hiroaki Suzuki
洋明 鈴木
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.)
Hitachi Ltd
Original Assignee
Hitachi 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 Hitachi Ltd filed Critical Hitachi Ltd
Priority to JP7099230A priority Critical patent/JPH08292284A/en
Publication of JPH08292284A publication Critical patent/JPH08292284A/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

  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

PURPOSE: To provide a facility for ending an accident even if an imaginary severe accident with extremely small probability where no safety system operates and fuel melts in a pressure pipe type heavy water reactor. CONSTITUTION: Water is poured into a calandria tank 4 using a water-pouring pump 3 which is independent of a safety facility which a prior art pressure type heavy water furnace has and a water-pouring source 2 located outside a storage container, thus cooling a molten fuel remaining in a pressure pipe assembly 7 and a fuel discharged into the calandria tank 4 by pouring water and ending and cooling the molten fuel by the calandria tank 4 which is a reactor core boundary.

Description

【発明の詳細な説明】Detailed Description of the Invention

【0001】[0001]

【産業上の利用分野】本発明は設備に関する。FIELD OF THE INVENTION The present invention relates to equipment.

【0002】[0002]

【従来の技術】原子炉において、核燃料の冷却材が喪失
する事故が発生した場合には、非常用炉心冷却系により
炉心部の燃料が冷却され、その後、余熱除去系により燃
料から発生する崩壊熱を取り除くことによって、事故を
終息させる。圧力管型重水炉では図6に示すように、非
常用炉心冷却系として蓄圧器31にある水を使用する急
速注入系32,復水貯蔵タンク33の水を高圧注水ポン
プ34により蒸気ドラム9に注水を行う高圧注入系3
5,低圧注水ポンプ36により水ドラム10に注水を行
う低圧注入系37,循環ポンプ38と熱交換器39によ
り崩壊熱を冷却する余熱除去系40,同様の目的を隔離
給水ポンプ41による給水で達成する隔離給水系42が
設けられている(全てのドラムに安全設備は接続されて
いるが、図6では1系統のみ示した)。また事故時に格
納容器1内部に放出された蒸気・高温水を蒸気放出プー
ル15,格納容器スプレイ系43を用いて冷却し、蒸気
放出プール15の水を冷却するために蒸気放出プール冷
却ポンプ44と冷却器45がある。以上の安全設備は多
重に設置されており、事故発生時にはこれらの安全系が
作動し燃料が損傷・溶融する事態には至らない。しか
し、これらの安全系が全て作動せず、かつ炉心燃料が溶
融するという確率的に極めて低い仮想的な原子炉の苛酷
事故を想定すると、図7に示す圧力管集合体の構造上、
圧力管46,カランドリア管47の肉厚は、下部遮蔽プ
ラグ48の長手方向寸法よりはるかに小さいために、核
燃料49が溶融した場合、圧力管46及びカランドリア
管47に溶融燃料が接触し、これらを破り、カランドリ
アタンク4内に放出されると予想される。カランドリア
タンク4には通常は重水が満たされているが、このよう
な事故時には燃料からの加熱・重水循環系のポンプ停止
などによりタンク内の重水が減少し溶融した燃料が重水
により充分冷却されず、カランドリアタンク4を侵食し
その健全性を脅かし、溶融燃料が格納容器内に流出する
可能性がある。
2. Description of the Related Art In a nuclear reactor, when an accident occurs in which the coolant for nuclear fuel is lost, the emergency core cooling system cools the fuel in the core, and then the decay heat generated from the fuel by the residual heat removal system. End the accident by removing the. In the pressure tube type heavy water reactor, as shown in FIG. 6, the rapid injection system 32 that uses water in the pressure accumulator 31 as an emergency core cooling system, and the water in the condensate storage tank 33 to the steam drum 9 by the high pressure water injection pump 34. High pressure injection system for water injection 3
5, a low-pressure injection system 37 that injects water into the water drum 10 by the low-pressure water injection pump 36, a residual heat removal system 40 that cools decay heat by the circulation pump 38 and the heat exchanger 39, and the same purpose is achieved by water supply by the isolated water supply pump 41. A separate water supply system 42 is provided (the safety equipment is connected to all the drums, but only one system is shown in FIG. 6). In addition, the steam / high-temperature water discharged into the containment vessel 1 at the time of the accident is cooled by using the steam release pool 15 and the containment vessel spray system 43, and a steam release pool cooling pump 44 is provided to cool the water in the steam release pool 15. There is a cooler 45. The above safety equipment is installed in multiple layers, and in the event of an accident, these safety systems will operate and the fuel will not be damaged or melted. However, assuming a severe accident of a hypothetical reactor in which all of these safety systems do not operate and the core fuel is melted at a probability that is extremely low, due to the structure of the pressure pipe assembly shown in FIG.
Since the thickness of the pressure pipe 46 and the calandria pipe 47 is much smaller than the longitudinal dimension of the lower shield plug 48, when the nuclear fuel 49 is melted, the pressure pipe 46 and the calandria pipe 47 come into contact with the molten fuel, and Expected to be broken and released into Calandria tank 4. Although the calandria tank 4 is usually filled with heavy water, in such an accident, the heavy water in the tank is reduced by heating from the fuel and the pump stop of the heavy water circulation system, etc., and the molten fuel is sufficiently cooled by the heavy water. Otherwise, the calandria tank 4 may be eroded and its soundness may be threatened, and the molten fuel may flow out into the containment vessel.

【0003】このような原子炉炉心の加熱に起因する燃
料が溶融する苛酷事故への対処法として、格納容器内に
ある溶融した燃料に注水するものが、従来技術として存
在する。これらには圧力容器を持つ軽水炉用に、特開平
1−245191 号,特開平2−222872号公報がある。これら
は軽水炉のように炉心バウンダリが圧力バウンダリと等
しい炉において、圧力容器外に放出された燃料に対して
有効であるが、圧力管型重水炉のような炉心バウンダリ
が圧力バウンダリと異なる形態の原子炉に対して、最適
化した代替冷却手段とは言えない。
As a conventional method for coping with a severe accident in which the fuel is melted due to the heating of the reactor core, water is poured into the melted fuel in the containment vessel as a conventional technique. These are for light water reactors that have pressure vessels.
There are 1-245191 and JP-A-2-222872. These are effective for the fuel discharged outside the pressure vessel in a reactor where the core boundary is equal to the pressure boundary such as a light water reactor, but the core boundary such as the pressure tube type heavy water reactor has a different form from the pressure boundary. It is not an optimized alternative cooling method for the furnace.

【0004】[0004]

【発明が解決しようとする課題】本発明の目的は、圧力
管型重水炉において安全系が全て作動しない、確率的に
極めて低い仮想的な原子炉の燃料が溶融する苛酷事故が
起こった時でさえ、発生した溶融燃料をカランドリアタ
ンク内で冷却し、炉心バウンダリであるカランドリアタ
ンク内部で終息させる手段を提供することにある。
SUMMARY OF THE INVENTION An object of the present invention is to prevent a safety accident in a pressure tube type heavy water reactor when a severe accident occurs in which fuel in a hypothetical reactor which is extremely low in probability is melted. Even, it is to provide a means for cooling the generated molten fuel in the calandria tank and terminating it inside the calandria tank, which is the core boundary.

【0005】[0005]

【課題を解決するための手段】上記目的を達成するた
め、本発明の圧力管型重水炉設備は、安全設備が持つ注
水ポンプとは独立した注水ポンプを備え、これにより格
納容器外にある注水源により、カランドリアタンク内に
注水できる構成とする。
In order to achieve the above object, the pressure pipe type heavy water reactor equipment of the present invention is equipped with a water injection pump independent of the water injection pump of the safety equipment, whereby the water injection outside the containment vessel is achieved. The water source will allow water to be poured into the calandria tank.

【0006】この構成に加え、前記注水源から蒸気ドラ
ム,水ドラム,格納容器スプレイヘッダに注水できる構
成とし、かつカランドリアタンク内部で発生した蒸気を
格納容器内にある水プールに導くことによって凝縮でき
る機能を有する構成とする。さらにこの構成に加え、カ
ランドリアタンクの水量減少と連動して、カランドリア
タンクに注水できる設備を有する構成とする。
In addition to this structure, the steam drum, the water drum, and the spray header of the containment vessel spray water can be poured from the above-mentioned water injection source, and the steam generated in the calandria tank is introduced into the water pool in the containment vessel to condense. The configuration has the function that can Furthermore, in addition to this configuration, the facility for pouring water into the calandria tank will be provided in conjunction with the decrease in the amount of water in the calandria tank.

【0007】また、カランドリアタンクへの注水経路と
して制御棒案内管を用いる構成としても良い。
A control rod guide tube may be used as a water injection path to the calandria tank.

【0008】さらに、注水に硼酸を混入することができ
る構成であっても良い。
Further, it may be so constructed that boric acid can be mixed into the water injection.

【0009】[0009]

【作用】本発明によれば、圧力管型重水炉で安全系が全
て作動しない、確率的に極めて低い仮想的な原子炉の苛
酷事故が起こったときでも、安全系とは独立した注水ポ
ンプを用いて、格納容器外からカランドリアタンク内に
注水できるので、炉心バウンダリであるカランドリアタ
ンク内の溶融燃料を冷却することが可能となる。加え
て、蒸気ドラム,水ドラムに注水することにより圧力管
集合体内で発生した蒸気を凝縮でき、さらにカランドリ
アタンク内部で発生した蒸気を格納容器内にある水プー
ルに導くことによって凝縮する機能により、溶融燃料を
冷却することで発生した蒸気を凝縮でき、水プールから
発生する蒸気についても格納容器内への注水によって凝
縮が可能であるので、格納容器内部の圧力が上昇するの
を防ぐことができる。
According to the present invention, even when a severe accident of a hypothetical reactor in which the safety system does not operate at all in the pressure tube type heavy water reactor and the probability is extremely low, a water injection pump independent of the safety system is installed. By using this, water can be injected into the calandria tank from outside the containment vessel, so that the molten fuel in the calandria tank, which is the core boundary, can be cooled. In addition, by pouring water into the steam drum and water drum, the steam generated in the pressure pipe assembly can be condensed, and further the steam generated in the calandria tank can be condensed by being guided to the water pool in the containment vessel. , The steam generated by cooling the molten fuel can be condensed, and the steam generated from the water pool can also be condensed by pouring water into the containment vessel, so it is possible to prevent the pressure inside the containment vessel from rising. it can.

【0010】また、カランドリアタンクへの注水経路と
して制御棒案内管を用いる構成によって既存の圧力管型
重水炉に新規配管を付設することなくカランドリアタン
クへの注水が可能となる。
Further, by using the control rod guide tube as the water injection path to the calandria tank, it is possible to inject water to the calandria tank without attaching new piping to the existing pressure tube type heavy water reactor.

【0011】さらに注水に硼酸を混入することで、溶融
燃料の核反応を抑え、燃料の熱出力を抑制することがで
きる。
Further, by mixing boric acid in the water injection, it is possible to suppress the nuclear reaction of the molten fuel and suppress the heat output of the fuel.

【0012】[0012]

【実施例】以下に本発明の実施例を図を参照しながら説
明する。
Embodiments of the present invention will be described below with reference to the drawings.

【0013】図1に本発明の一実施例を示す。図の圧力
管型重水炉において、格納容器1外にある注水源2及び
従来技術の安全設備とは独立した注水ポンプ3がカラン
ドリアタンク4に弁5を介して注水配管6で接続されて
いる。既存の原子炉設備の中からは注水源2は、純水貯
蔵タンク,濾過水タンクの水をこれに当てることができ
る。同様に注水ポンプとして消火系ポンプを当てること
が可能である。
FIG. 1 shows an embodiment of the present invention. In the pressure pipe type heavy water reactor shown in the figure, a water injection source 2 outside the containment vessel 1 and a water injection pump 3 independent of the safety equipment of the prior art are connected to a calandria tank 4 via a valve 5 by a water injection pipe 6. . From the existing nuclear reactor equipment, the water injection source 2 can apply water from the pure water storage tank or the filtered water tank. Similarly, a fire extinguishing system pump can be applied as the water injection pump.

【0014】通常運転時、および事故時でも緊急炉心冷
却系・余熱除去系が動作するときは、弁5は閉じてお
り、注水源2より注水を行う必要はない。しかし、全て
の安全系が動作しない苛酷事故を想定すると、圧力管集
合体7の内部の核燃料が溶融し、重水を満たしたカラン
ドリアタンク4に燃料が流出する。この時は、炉心冷却
水が減少することによる蒸気ドラム水位の低下を検知す
ることにより弁5を開き、カランドリアタンク4に注水
する。これによりカランドリアタンク4に流出した燃料
は、カランドリアタンク4に直接注水することで冷却さ
れ、溶融燃料はカランドリアタンク4の外部に出ること
なく事故を終息できる。
During normal operation and when the emergency core cooling system / remaining heat removal system operates even during an accident, the valve 5 is closed and it is not necessary to inject water from the water injection source 2. However, assuming a severe accident in which all safety systems do not operate, the nuclear fuel inside the pressure pipe assembly 7 melts and the fuel flows out to the calandria tank 4 filled with heavy water. At this time, the valve 5 is opened and water is poured into the calandria tank 4 by detecting a decrease in the water level of the steam drum due to a decrease in core cooling water. As a result, the fuel flowing out to the calandria tank 4 is cooled by directly pouring water into the calandria tank 4, and the molten fuel can end the accident without going out of the calandria tank 4.

【0015】図2に本発明の第二の実施例を示す。これ
は第一の実施例に加え、注水源2からの注水を格納容器
スプレイヘッダ8,蒸気ドラム9,水ドラム10に配管
11〜13により供給する。さらにカランドリアタンク
4は、カランドリアタンクベント管14によって蒸気放
出プール15とつながっている。カランドリアタンクベ
ント管14の中途にはラプチャディスク16が設けられ
ており、通常時にカランドリアタンク4内の重水に蒸気
放出プール15からの軽水の湿分が混入しないようにな
っている。またラプチャディスク16の破壊開弁圧はカ
ランドリアタンク4内で蒸気が発生することにより速や
かに開くよう、カランドリアタンク内圧よりわずかに高
い圧力に設定しておく。
FIG. 2 shows a second embodiment of the present invention. In this case, in addition to the first embodiment, the water injection from the water injection source 2 is supplied to the containment vessel spray header 8, the steam drum 9, and the water drum 10 through pipes 11 to 13. Further, the calandria tank 4 is connected to the vapor discharge pool 15 by a calandria tank vent pipe 14. A rupture disc 16 is provided in the middle of the calandria tank vent pipe 14 so that the heavy water in the calandria tank 4 does not mix moisture of light water from the steam discharge pool 15 at normal times. Further, the breaking valve opening pressure of the rupture disc 16 is set to a pressure slightly higher than the calandria tank internal pressure so as to open quickly due to the generation of steam in the calandria tank 4.

【0016】これにより圧力管集合体7内部で発生した
蒸気に対し直接冷却を行い、蒸気を凝縮することが可能
となる。また、カランドリアタンクへの注水冷却によ
り、カランドリアタンク4の内部では燃料から水が受熱
するために蒸気が発生する。これによりカランドリアタ
ンク内圧が上昇するので、ラプチャディスク16が破壊
し、カランドリアタンク4内の蒸気は蒸気放出プール1
5に導かれここで凝縮される。蒸気放出プール15から
の蒸発による格納容器1内の圧力上昇は、格納容器スプ
レイヘッダ8からの注水により蒸気が凝縮され、抑制で
きる。これにより格納容器1が加圧により健全性を脅か
されることはない。
As a result, the steam generated inside the pressure pipe assembly 7 can be directly cooled and condensed. Further, when the water is cooled to the calandria tank, water is received from the fuel inside the calandria tank 4, so that steam is generated. As a result, the internal pressure of the calandria tank rises, the rupture disc 16 is destroyed, and the steam in the calandria tank 4 is discharged from the steam discharge pool 1.
It is led to 5 and condensed here. The pressure increase in the containment vessel 1 due to the evaporation from the vapor discharge pool 15 can be suppressed because the water is injected from the containment vessel spray header 8 to condense the vapor. As a result, the containment vessel 1 is not threatened by pressurization.

【0017】図3に本発明の第三の実施例を示す。圧力
管型重水炉では、重水サージタンク17内部に蓄えられ
た重水によって通常運転時に起こるカランドリアタンク
4内の重水の増減を吸収している。本発明では重水サー
ジタンクに水位計18を設け、この水位計からの水位低
信号による弁5の開放と注水ポンプ3の起動によって注
水を行う。本発明で対象としている事故では、溶融して
いる燃料の温度はカランドリアタンク4内重水の沸点よ
りもはるかに高いため、事故発生時には重水が蒸発し重
水サージタンク17の水位が低下する。よってこれを水
位計18によって検知し、制御装置19によって注水操
作を行えば、遅滞なく事故を終息させることができる。
FIG. 3 shows a third embodiment of the present invention. In the pressure tube type heavy water reactor, the heavy water stored in the heavy water surge tank 17 absorbs the increase or decrease in the heavy water in the calandria tank 4 that occurs during normal operation. In the present invention, a water level gauge 18 is provided in the heavy water surge tank, and water is injected by opening the valve 5 and starting the water injection pump 3 in response to a low water level signal from the water level gauge. In the accident targeted by the present invention, the temperature of the molten fuel is much higher than the boiling point of the heavy water in the calandria tank 4, so that when the accident occurs, the heavy water evaporates and the water level in the heavy water surge tank 17 decreases. Therefore, if this is detected by the water level meter 18 and the water injection operation is performed by the control device 19, the accident can be ended without delay.

【0018】図4に本発明の第四の実施例を示す。一般
的に圧力管型重水炉では数百本の圧力管集合体が在り、
カランドリアタンク4は遮蔽構造物内部にあるため、既
存の炉に対して新規にカランドリアタンク4への注水配
管を設置するのは難しい。しかしこの形式の原子炉はカ
ランドリアタンク4の重水を循環させる設備を持ってい
る。通常運転時でもカランドリアタンク内部4の重水は
燃料からの加熱を受けるので、重水循環ポンプ20によ
ってカランドリアタンク4から取り出され、重水冷却器
21によって冷され、制御棒22をカランドリアタンク
4に挿入するガイドとなる制御棒案内管23を通じてカ
ランドリアタンク4内に戻される。よって重水循環系配
管24に本発明の配管6を接続し、弁25によって重水
循環系と本発明を隔離する構成とすれば既存の圧力管型
重水炉にも、本発明を容易かつ少ない工数及び工賃で設
置することができる。弁25を通常運転時には閉じてお
けば、重水循環系の機能を損なうことはなく、本発明で
対象とする事故発生時には弁25を開くことでカランド
リアタンクへの注水が制御棒案内管23を通じて可能と
なる。
FIG. 4 shows a fourth embodiment of the present invention. Generally, in a pressure tube type heavy water reactor, there are several hundred pressure tube assemblies,
Since the calandria tank 4 is inside the shielding structure, it is difficult to newly install a water injection pipe to the calandria tank 4 in the existing furnace. However, this type of reactor has equipment for circulating the heavy water in the calandria tank 4. Since the heavy water inside the calandria tank 4 is heated by the fuel even during normal operation, it is taken out of the calandria tank 4 by the heavy water circulation pump 20, cooled by the heavy water cooler 21, and the control rod 22 is transferred to the calandria tank 4. It is returned to the calandria tank 4 through the control rod guide tube 23 that serves as a guide to be inserted. Therefore, if the pipe 6 of the present invention is connected to the heavy water circulation system pipe 24 and the heavy water circulation system is isolated from the present invention by the valve 25, the present invention can be easily and reduced in the number of man-hours in the existing pressure tube type heavy water reactor. It can be installed at a wage. If the valve 25 is closed during normal operation, the function of the heavy water circulation system is not impaired, and when the accident targeted by the present invention occurs, the valve 25 is opened to inject water into the calandria tank through the control rod guide pipe 23. It will be possible.

【0019】図5に本発明の第五の実施例を示す。これ
は本発明である注水機構に、圧力管型重水炉で既存の設
備である、硼酸供給系の硼酸溶解槽26から硼酸注入ポ
ンプ27を用いて硼酸を混入できるようにしたものであ
る。一般に圧力管型重水炉では、炉心燃焼による余剰反
応度の変化を、重水減速材に液体ポイズン(中性子吸収
材)である硼酸を硼酸溶解槽26から硼酸注入ポンプ2
7によって重水循環系配管24中に混入することで補償
している。よってこの機構を本発明が対象とする事故に
おいて、圧力管集合体7とカランドリアタンク4への注
水に硼酸を混入すれば、単なる水を用いるよりも溶融燃
料の核反応を抑え、燃料の熱出力を抑制することがで
き、より速やかに事故を終息させることができる。これ
は本発明の配管12と13に、硼酸注入系をそれぞれ配
管28,29によって接続し、弁30によって本発明の
配管12と13に硼酸の注入の有無を制御することで達
成できる。通常時は弁30は閉じておくことにより、核
燃料の冷却材に硼酸が混じることはない。また本発明が
対象とする事故が発生したときは、弁30を開き、注水
に硼酸を混入することができる。
FIG. 5 shows a fifth embodiment of the present invention. This is to allow the boric acid to be mixed into the water injection mechanism of the present invention from the boric acid dissolving tank 26 of the boric acid supply system, which is an existing facility in the pressure tube type heavy water reactor, by using the boric acid injection pump 27. Generally, in a pressure tube type heavy water reactor, a change in excess reactivity due to core combustion is caused by a boric acid injection pump 2 from a boric acid dissolving tank 26 for boric acid which is a liquid poison (neutron absorbing material) as a heavy water moderator.
7 is mixed in the heavy water circulation system pipe 24 to compensate. Therefore, in an accident in which the present invention is directed to this mechanism, if boric acid is mixed into the water injected into the pressure pipe assembly 7 and the calandria tank 4, the nuclear reaction of the molten fuel is suppressed and the heat of the fuel is suppressed as compared with the case where only water is used. The output can be suppressed, and the accident can be ended more quickly. This can be achieved by connecting the boric acid injection system to the pipes 12 and 13 of the present invention by pipes 28 and 29, respectively, and controlling the presence or absence of the injection of boric acid into the pipes 12 and 13 of the present invention by the valve 30. Normally, the valve 30 is closed so that the coolant of the nuclear fuel is not mixed with boric acid. When an accident targeted by the present invention occurs, the valve 30 can be opened and boric acid can be mixed into the water injection.

【0020】[0020]

【発明の効果】本発明によれば、起こる可能性の極めて
低い燃料溶融が起こる原子炉の苛酷事故においても、溶
融燃料を冷却し事故を終息できるので、圧力管型重水炉
の安全性が向上する。
EFFECTS OF THE INVENTION According to the present invention, even in a severe accident in a nuclear reactor in which fuel melting is extremely unlikely to occur, the molten fuel can be cooled and the accident can be terminated, so that the safety of the pressure tube type heavy water reactor is improved. To do.

【0021】また、溶融燃料の注水によって発生した蒸
気を凝縮し、格納容器の内圧上昇を抑制できるので、格
納容器の事故に対する安全裕度を向上できる。
Further, since the vapor generated by the injection of the molten fuel can be condensed and the increase in the internal pressure of the containment vessel can be suppressed, the safety margin against the accident of the containment vessel can be improved.

【0022】また、溶融燃料の発生によるカランドリア
タンク内の重水水量の減少を、重水サージタンクの水位
低下により検知し速やかに溶融炉心などに注水を行うこ
とができるので、苛酷事故発生時にも人的操作によらず
速やかに対処でき、圧力管型重水炉の安全性が向上す
る。
Further, since the decrease in the amount of heavy water in the calandria tank due to the generation of molten fuel can be detected by the decrease in the water level in the heavy water surge tank, water can be quickly injected into the melting core, etc. It can be dealt with promptly without any manual operation, and the safety of the pressure tube type heavy water reactor will be improved.

【0023】また、既存の圧力管型重水炉に本発明を取
り付ける場合に、カランドリアタンクに工作をする必要
がなく、少ない工賃と工数で安全性を向上できる機器を
取り付けられる。
Further, when the present invention is attached to an existing pressure tube type heavy water reactor, it is not necessary to work on the calandria tank, and it is possible to attach equipment capable of improving safety with a small labor and man-hour.

【0024】さらに、単なる水を用いるよりも溶融燃料
の核反応を抑え、燃料の熱出力を抑制することができ、
より速やかに事故を終息させることができ、事故に対す
る安全裕度を向上できる。
Further, it is possible to suppress the nuclear reaction of the molten fuel and suppress the heat output of the fuel, as compared with the case of using mere water.
The accident can be ended more quickly, and the safety margin against the accident can be improved.

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

【図1】本発明の圧力管型重水炉を示した一実施例の系
統図。
FIG. 1 is a system diagram of an embodiment showing a pressure tube type heavy water reactor of the present invention.

【図2】本発明の圧力管型重水炉を示した第二実施例の
系統図。
FIG. 2 is a system diagram of a second embodiment showing a pressure tube type heavy water reactor of the present invention.

【図3】本発明の圧力管型重水炉を示した第三実施例の
系統図。
FIG. 3 is a system diagram of a third embodiment showing a pressure tube type heavy water reactor of the present invention.

【図4】本発明の圧力管型重水炉を示した第四実施例の
系統図。
FIG. 4 is a system diagram of a fourth embodiment showing a pressure tube type heavy water reactor of the present invention.

【図5】本発明の圧力管型重水炉を示した第五実施例の
系統図。
FIG. 5 is a system diagram of a fifth embodiment showing a pressure tube type heavy water reactor of the present invention.

【図6】従来の圧力管型重水炉の安全設備を示した系統
図。
FIG. 6 is a system diagram showing safety equipment of a conventional pressure tube type heavy water reactor.

【図7】圧力管型重水炉の一本の圧力管集合体の断面
図。
FIG. 7 is a sectional view of one pressure tube assembly of the pressure tube type heavy water reactor.

【符号の説明】[Explanation of symbols]

1…格納容器、2…注水源、3…注水ポンプ、4…カラ
ンドリアタンク、5…弁、6…注水配管、7…圧力管集
合体。
DESCRIPTION OF SYMBOLS 1 ... Containment container, 2 ... Water injection source, 3 ... Water injection pump, 4 ... Calandria tank, 5 ... Valve, 6 ... Water injection piping, 7 ... Pressure pipe assembly.

Claims (5)

【特許請求の範囲】[Claims] 【請求項1】圧力管内に核燃料及び冷却材を収納し、前
記圧力管を収容するカランドリア管を一単位とした圧力
管集合体と制御棒とを重水減速材を保有するカランドリ
アタンク内に配列し、前記圧力管内の前記核燃料と格納
容器内には原子炉での事故発生時に注水することによっ
て前記圧力管集合体および前記制御棒を冷却する安全設
備を有する圧力管型重水炉において、事故発生時に前記
安全設備が全て動作しない場合に前記安全設備が持つ注
水ポンプから独立した注水ポンプと前記格納容器外にあ
る注水源を用いて、前記カランドリアタンク内に注水で
きる機能を有することを特徴とする圧力管型重水炉。
1. A nuclear fuel and a coolant are contained in a pressure pipe, and a pressure pipe assembly and a control rod, each unit of which is a calandria pipe for accommodating the pressure pipe, are arranged in a calandria tank having a heavy water moderator. However, an accident occurred in a pressure tube type heavy water reactor having safety equipment for cooling the pressure tube assembly and the control rod by injecting water into the nuclear fuel in the pressure tube and the containment vessel at the time of an accident in the reactor. When the safety equipment does not operate at all, it has a function of injecting water into the calandria tank by using a water injection pump independent of the water injection pump of the safety equipment and a water injection source outside the containment vessel. Pressure tube type heavy water reactor.
【請求項2】請求項1において、前記圧力管内および前
記格納容器内に前記注水ポンプと注水源を用いて注水で
き、前記カランドリアタンクの内部で発生した蒸気を、
前記カランドリアタンク内が一定圧力を超えたときに前
記カランドリアタンクと前記格納容器内にある水プール
を連通することによって凝縮できる機能を有する圧力管
型重水炉。
2. The steam according to claim 1, wherein water can be injected into the pressure pipe and the containment vessel by using the water injection pump and a water injection source, and steam generated inside the calandria tank is
A pressure tube-type heavy water reactor having a function of allowing condensation when the inside of the calandria tank exceeds a certain pressure by connecting the calandria tank and a water pool in the storage container.
【請求項3】請求項1または2において、前記カランド
リアタンクの水量減少と連動して、注水できる設備を有
する圧力管型重水炉。
3. The pressure tube type heavy water reactor according to claim 1 or 2, which has a facility for pouring water in association with a decrease in the amount of water in the calandria tank.
【請求項4】請求項1,2または3において、前記カラ
ンドリアタンクへの注水経路として制御棒案内管を用い
る圧力管型重水炉。
4. A pressure tube type heavy water reactor according to claim 1, wherein a control rod guide tube is used as a water injection path to the calandria tank.
【請求項5】請求項1,2,3または4において、注水
に硼酸を混入することができる構成である圧力管型重水
炉。
5. The pressure tube type heavy water reactor according to claim 1, 2, 3 or 4, wherein boric acid can be mixed in the injected water.
JP7099230A 1995-04-25 1995-04-25 Pressure pipe type heavy water reactor facility Pending JPH08292284A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP7099230A JPH08292284A (en) 1995-04-25 1995-04-25 Pressure pipe type heavy water reactor facility

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP7099230A JPH08292284A (en) 1995-04-25 1995-04-25 Pressure pipe type heavy water reactor facility

Publications (1)

Publication Number Publication Date
JPH08292284A true JPH08292284A (en) 1996-11-05

Family

ID=14241882

Family Applications (1)

Application Number Title Priority Date Filing Date
JP7099230A Pending JPH08292284A (en) 1995-04-25 1995-04-25 Pressure pipe type heavy water reactor facility

Country Status (1)

Country Link
JP (1) JPH08292284A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2014029303A (en) * 2012-07-31 2014-02-13 Toshiba Corp Water injection facility and nuclear reactor system
JP2014035297A (en) * 2012-08-09 2014-02-24 Toshiba Corp Thermal neutron absorber coating application device and method, and method for collecting molten core

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2014029303A (en) * 2012-07-31 2014-02-13 Toshiba Corp Water injection facility and nuclear reactor system
JP2014035297A (en) * 2012-08-09 2014-02-24 Toshiba Corp Thermal neutron absorber coating application device and method, and method for collecting molten core

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