Deprecated: The each() function is deprecated. This message will be suppressed on further calls in /home/zhenxiangba/zhenxiangba.com/public_html/phproxy-improved-master/index.php on line 456
JP5773710B2 - Reactor vessel structure and reactor operation method - Google Patents
[go: Go Back, main page]

JP5773710B2 - Reactor vessel structure and reactor operation method - Google Patents

Reactor vessel structure and reactor operation method Download PDF

Info

Publication number
JP5773710B2
JP5773710B2 JP2011081254A JP2011081254A JP5773710B2 JP 5773710 B2 JP5773710 B2 JP 5773710B2 JP 2011081254 A JP2011081254 A JP 2011081254A JP 2011081254 A JP2011081254 A JP 2011081254A JP 5773710 B2 JP5773710 B2 JP 5773710B2
Authority
JP
Japan
Prior art keywords
reactor
space
coolant
liquid
inert gas
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.)
Active
Application number
JP2011081254A
Other languages
Japanese (ja)
Other versions
JP2012215475A (en
Inventor
茂 國嶋
茂 國嶋
清水 亮
亮 清水
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.)
Mitsubishi Heavy Industries Ltd
Original Assignee
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 Mitsubishi Heavy Industries Ltd filed Critical Mitsubishi Heavy Industries Ltd
Priority to JP2011081254A priority Critical patent/JP5773710B2/en
Priority to PCT/JP2011/065652 priority patent/WO2012008369A1/en
Publication of JP2012215475A publication Critical patent/JP2012215475A/en
Application granted granted Critical
Publication of JP5773710B2 publication Critical patent/JP5773710B2/en
Active legal-status Critical Current
Anticipated expiration legal-status Critical

Links

Images

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)

Description

本発明は、たとえば高速増殖炉(Fast Breeder Reactor:FBR)等の高速炉に適用される原子炉容器構造及び原子炉の運転方法に係り、特に、ホットベッセルに好適な原子炉容器構造及び原子炉の運転方法に関する。   The present invention relates to a reactor vessel structure applied to a fast reactor such as a fast breeder reactor (FBR) and a method for operating the reactor, and more particularly to a reactor vessel structure and a reactor suitable for a hot vessel. Relates to the driving method.

従来、高速増殖炉等の高速炉では、たとえば図8に示すように、ホットベッセルと呼ばれる原子炉容器構造がある。この原子炉容器10では、冷却材としてナトリウムのような液体金属が用いられており、冷却系に接続されたコールドレグ配管17Cから原子炉容器10の下部プレナム19に流入した液体ナトリウムNaは、図中に矢印Fで示すように、炉心11を下から上に通過する過程で加熱され、定格運転時には高温(約550℃)で使用される。なお、加熱された液体ナトリウムNaは、上部プレナム14からホットレグ配管17Hを通って冷却系に戻される。   Conventionally, a fast reactor such as a fast breeder reactor has a reactor vessel structure called a hot vessel as shown in FIG. In this reactor vessel 10, a liquid metal such as sodium is used as a coolant, and the liquid sodium Na flowing into the lower plenum 19 of the reactor vessel 10 from the cold leg pipe 17 </ b> C connected to the cooling system is shown in the figure. As shown by an arrow F in FIG. 2, it is heated while passing through the core 11 from the bottom to the top, and is used at a high temperature (about 550 ° C.) during rated operation. The heated liquid sodium Na is returned from the upper plenum 14 to the cooling system through the hot leg piping 17H.

図示の原子炉容器10は、冷却材バウンダリを構成する重要機器であり、冷却材の一例として液体ナトリウムが使用されている。このような原子炉容器10内は、化学的に活性な冷却材であるナトリウムが空気と触れることを防ぐために、液体ナトリウムNaの上部に、たとえばアルゴン(Ar)等の不活性ガスを充填した不活性ガス充填空間Gを設けた有液面構造となっている。なお、図中の符号Lは、液体ナトリウムNaの液位を示している。   The illustrated reactor vessel 10 is an important device that constitutes the coolant boundary, and liquid sodium is used as an example of the coolant. In such a reactor vessel 10, in order to prevent sodium, which is a chemically active coolant, from coming into contact with air, an inert gas such as argon (Ar) is filled on top of liquid sodium Na. It has a liquid surface structure in which an active gas filling space G is provided. In addition, the code | symbol L in a figure has shown the liquid level of liquid sodium Na.

また、上述した原子炉容器10内は、隔壁13によって上下に仕切られ、上部プレナム14及び中間プレナム18を形成している。隔壁13は、炉心11から加熱を受けて上部プレナム14に流入した高温の液体ナトリウムNaが、中間プレナム18へとバイパスすることを防止し、炉心11を支持するスカート部12等の据付部を低温に保つ。
上述した不活性ガスは、上部プレナム14内に充填されている。すなわち、上部プレナム14は、原子炉容器10内における有液面空間となる。
なお、ルーフデッキ15は、原子炉容器10の据付部を低温に保つために冷却されている。
また、図中の符号30は、不活性ガス充填空間Gにアルゴン等の不活性ガスを供給する不活性ガス供給(充填)系である。
Further, the inside of the nuclear reactor vessel 10 described above is partitioned vertically by a partition wall 13 to form an upper plenum 14 and an intermediate plenum 18. The partition wall 13 prevents the high-temperature liquid sodium Na flowing into the upper plenum 14 from being heated from the core 11 from bypassing to the intermediate plenum 18, and lowering the installation part such as the skirt part 12 that supports the core 11 at a low temperature. Keep on.
The above-described inert gas is filled in the upper plenum 14. That is, the upper plenum 14 becomes a liquid surface space in the reactor vessel 10.
The roof deck 15 is cooled in order to keep the installation part of the reactor vessel 10 at a low temperature.
Further, reference numeral 30 in the drawing denotes an inert gas supply (filling) system that supplies an inert gas such as argon to the inert gas filling space G.

このため、原子炉容器10の炉壁10aにおいては、図7の「液位上昇の場合」に示すように、液体ナトリウムNaが存在する冷却材接液部と、不活性ガス充填空間Gとの間において、軸方向に大きな温度勾配を生じ、冷却材の液面近傍部に高い熱応力が発生する。この熱応力は、以下に説明する理由により、特に原子炉の起動時に大きくなる。   For this reason, in the reactor wall 10a of the reactor vessel 10, as shown in “in the case of liquid level rise” in FIG. 7, the coolant wetted part where the liquid sodium Na exists and the inert gas filling space G In the meantime, a large temperature gradient is generated in the axial direction, and a high thermal stress is generated near the liquid surface of the coolant. This thermal stress becomes particularly large at the start-up of the reactor for the reasons explained below.

原子炉の停止時においては、冷却材として使用する液体ナトリウムNaの凍結を防ぐ目的から、液体ナトリウムNaが約200℃に保温されている。
これに対し、原子炉の起動時には、炉心11からの加熱を受けて液体ナトリウムNaの温度が上昇するので、体積膨張に伴って液体ナトリウムNaの液位もL2からL3に上昇する。なお、この場合の液位L3は、原子炉通常(定常)運転時の冷却材液面となる。
When the reactor is shut down, the liquid sodium Na is kept at about 200 ° C. for the purpose of preventing freezing of the liquid sodium Na used as a coolant.
On the other hand, when the nuclear reactor is started up, the temperature of the liquid sodium Na rises due to the heating from the core 11, so that the liquid level of the liquid sodium Na rises from L2 to L3 along with the volume expansion. In this case, the liquid level L3 is the coolant level during normal (steady) operation of the reactor.

しかし、原子炉容器の材料であるオーステナイト系ステンレス鋼は、その熱伝導性が低いため、液体ナトリウムNaの液面より上の領域、すなわち液体ナトリウムNaと接液していない領域では温度の追従が遅くなる。従って、図7の「液位上昇の場合」に実線で示すように、原子炉容器10の炉壁10aには、液面近傍部(液位L3の液面よりやや上の領域)に大きな温度勾配が生じて高い熱応力を発生する。   However, since the austenitic stainless steel, which is the material of the reactor vessel, has low thermal conductivity, the temperature follows in the region above the surface of the liquid sodium Na, that is, the region not in contact with the liquid sodium Na. Become slow. Accordingly, as indicated by the solid line in “in the case of rising of the liquid level” in FIG. 7, the reactor wall 10a of the reactor vessel 10 has a large temperature in the vicinity of the liquid level (a region slightly above the liquid level of the liquid level L3). Gradients create high thermal stresses.

原子炉容器の壁面(上述した炉壁10a)に発生する熱応力を緩和する従来技術としては、たとえば特許文献1に開示されているように、原子炉容器の内側に内筒を設置し、容器と内筒の間に炉心入口側の冷却材を流し、冷却材の通過流量を調節して原子炉容器壁の熱応力を緩和するもの(コールドベッセル)がある。
また、特許文献2には、液面熱ラチェット現象の発生を防止するため、原子炉起動時において、原子炉容器内に設置した電磁ポンプを作動させ、冷却材となる液体金属の液位を変化させる高速炉が開示されている。
As a conventional technique for relaxing the thermal stress generated on the wall surface of the reactor vessel (the reactor wall 10a described above), for example, as disclosed in Patent Document 1, an inner cylinder is installed inside the reactor vessel, and the vessel There is a reactor that cools the thermal stress on the reactor vessel wall (cold vessel) by flowing the coolant on the reactor core side between the inner cylinder and the inner cylinder and adjusting the flow rate of the coolant.
In Patent Document 2, in order to prevent the occurrence of the liquid surface thermal ratchet phenomenon, the electromagnetic pump installed in the reactor vessel is operated at the time of starting the reactor, and the liquid level of the liquid metal serving as the coolant is changed. A fast reactor is disclosed.

また、下記の特許文献3〜5には、原子炉容器の冷却材液面近傍に、冷却材(液体ナトリウム)を貯留する貯留バケットを設けて熱応力を緩和する方式が開示されており、たとえば貯留バケット内に複数の熱抵抗体を収容する構造や、貯留バケットの断面積が上部及び下部で異なる構造もある。   Moreover, the following patent documents 3 to 5 disclose a method of reducing thermal stress by providing a storage bucket for storing coolant (liquid sodium) in the vicinity of the coolant level of the reactor vessel. There are also a structure in which a plurality of thermal resistors are accommodated in the storage bucket and a structure in which the cross-sectional area of the storage bucket is different between the upper part and the lower part.

特開平10−160883号公報JP-A-10-160883 特開平8−15487号公報JP-A-8-15487 特開昭59−163588号公報JP 59-163588 A 特開昭60−247191号公報JP 60-247191 A 特開昭61−47581号公報JP 61-47581 A

上述したように、ホットベッセルの原子炉容器構造においては、原子炉の起動時に液体ナトリウムNaの温度が上昇し、これに伴う熱膨張によって液体ナトリウムNaの液位Lも上昇する。このような原子炉容器10の炉壁10aでは、図7に示す「液位上昇の場合」、液体ナトリウムNaの液面近傍において軸方向に大きな温度勾配が生じるので、液面近傍部の熱応力は大きなものとなる。   As described above, in the reactor vessel structure of the hot vessel, the temperature of the liquid sodium Na rises at the time of startup of the nuclear reactor, and the liquid level L of the liquid sodium Na also rises due to the thermal expansion associated therewith. In such a reactor wall 10a of the nuclear reactor vessel 10, in the case of “increase in liquid level” shown in FIG. 7, a large temperature gradient is generated in the axial direction in the vicinity of the liquid level of liquid sodium Na. Will be big.

このため、原子炉の供用期間中には、起動・停止を繰り返すことにより、原子炉容器10に対して上述した熱応力が繰り返し発生することになる。従って、この熱応力が大きい場合には、起動のたびに原子炉容器10の径が縮む変形(液面ラチェット)や、クリープ疲労による破損の発生が懸念される。
さらに、原子炉容器10の健全性を確保するためには、起動にかける日数を長くし、炉壁10aが緩やかな温度上昇をするように、ゆっくりと起動する必要がある。しかし、原子炉を発電等の商用運転に使用するような場合には、起動に要する時間を短縮して定格運転時間を可能な限り延長することが望ましい。
このような熱応力に起因する懸念は、起動時のみならず、通常停止時、緊急停止時にも生じるものである。
For this reason, during the operation period of the nuclear reactor, the above-described thermal stress is repeatedly generated in the nuclear reactor vessel 10 by repeatedly starting and stopping. Therefore, when this thermal stress is large, there is a concern about the deformation (liquid level ratchet) in which the diameter of the reactor vessel 10 is reduced every time the reactor vessel 10 is started up or the occurrence of breakage due to creep fatigue.
Furthermore, in order to ensure the soundness of the reactor vessel 10, it is necessary to start up slowly so that the number of days required for startup is increased and the reactor wall 10 a gradually increases in temperature. However, when the nuclear reactor is used for commercial operation such as power generation, it is desirable to shorten the time required for startup and extend the rated operation time as much as possible.
Concerns due to such thermal stress occur not only at the time of startup, but also at the time of normal stop and emergency stop.

このような背景から、ホットベッセルの原子炉容器構造においては、原子炉容器の信頼性や運用性をより一層向上させるため、原子炉容器の壁面に発生する熱応力を緩和する方策が必要となる。この方策は、追加設備を最小限に抑え、高い耐熱成立性や安全性を有することが望ましい。
本発明は、上記の事情に鑑みてなされたものであり、その目的とするところは、原子炉の起動時等に発生する原子炉容器壁面の熱応力を緩和できる原子炉容器構造及び原子炉の運転方法を提供することにある。
From such a background, in the reactor vessel structure of a hot vessel, in order to further improve the reliability and operability of the reactor vessel, a measure to alleviate the thermal stress generated on the wall of the reactor vessel is required. . It is desirable that this measure minimizes additional equipment and has high heat resistance and safety.
The present invention has been made in view of the above circumstances, and an object of the present invention is to provide a reactor vessel structure and a reactor that can relieve the thermal stress of the reactor vessel wall surface that is generated when the reactor is started up. It is to provide a driving method.

本発明は、上記の課題を解決するため、下記の手段を採用した。
本発明に係る原子炉容器構造は、炉心を収納した原子炉容器内に、液体金属の冷却材を充填した液面上部に不活性ガス充填空間が形成されている有液面空間を設け、該有液面空間の容器壁面内側に、原子炉定常運転時の冷却材液面より高い位置まで有底内筒を設置して前記容器壁面と前記有底内筒との間に形成された冷却材滞留槽を備えている原子炉容器構造であって、前記有底内筒から前記原子炉容器の軸中心方向へ離間した内側に前記有液面空間の上面を形成するルーフデッキの下面に固定支持される仕切部材を設け、該仕切り部材の下端部を一連の原子炉運転状態における冷却材液位変化で最も低下する前記有液面空間の液面内まで延在させて前記有液面空間の内部を内側空間及び外側空間に分割し、不活性ガス供給系に接続されて前記内側空間に不活性ガスを供給するとともに第1開閉弁を備えた第1ガス配管と、前記第1開閉弁より上流側で前記第1ガス配管から分岐して前記外側空間に不活性ガスを供給するとともに第2開閉弁を備えた第2ガス配管とを設け、原子炉起動準備の充填完了時に、前記液体金属が、前記内側空間及び前記外側空間の不活性ガス充填圧力を相対的に変化させて生じる圧力差を利用して前記冷却材滞留槽に充填されることを特徴とするものである。
In order to solve the above problems, the present invention employs the following means.
The reactor vessel structure according to the present invention is provided with a liquid surface space in which an inert gas filling space is formed in an upper portion of a liquid surface filled with a liquid metal coolant in a reactor vessel containing a reactor core, A coolant formed between the vessel wall surface and the bottomed inner cylinder by installing a bottomed inner tube inside the vessel wall surface of the liquid surface space up to a position higher than the coolant level during steady operation of the reactor A reactor vessel structure having a retention tank, which is fixedly supported on the lower surface of a roof deck that forms the upper surface of the liquid surface space inside the bottomed inner cylinder and spaced apart in the axial center direction of the reactor vessel And a lower end portion of the partition member is extended into the liquid surface of the liquid surface space that is most lowered by a change in the coolant level in a series of reactor operation states. It divides the interior to the inner space and outer space, before being connected to the inert gas supply system An inert gas is supplied to the inner space and a first gas pipe provided with a first on-off valve, and an inert gas is branched from the first gas pipe on the upstream side of the first on-off valve and supplied to the outer space. And a second gas pipe provided with a second on-off valve, and the liquid metal relatively changes the inert gas filling pressure in the inner space and the outer space when filling in preparation for reactor startup is completed. The coolant staying tank is filled using the pressure difference generated by the above.

このような原子炉容器構造によれば、有底内筒から原子炉容器の軸中心方向へ離間した内側に、有液面空間の上面を形成するルーフデッキの下面に固定支持される仕切部材を設け、この仕切り部材の下端部を一連の原子炉運転状態における冷却材液位変化で最も低下する有液面空間の液面内まで延在させて有液面空間の内部を内側空間及び外側空間に分割し、不活性ガス供給系に接続されて内側空間に不活性ガスを供給するとともに第1開閉弁を備えた第1ガス配管と、第1開閉弁より上流側で第1ガス配管から分岐して外側空間に不活性ガスを供給するとともに第2開閉弁を備えた第2ガス配管とを設け、原子炉起動準備の充填完了時に、液体金属が、内側空間及び外側空間の不活性ガス充填圧力を相対的に変化させて生じる圧力差を利用して前記冷却材滞留槽に充填されるので、原子炉容器内の冷却材滞留槽に液体金属を充填するため、液体金属が空気と接触しないよう十分な配慮が必要となる専用の液体金属供給配管を新たに増設する必要はない。 According to such a reactor vessel structure, the partition member fixedly supported on the lower surface of the roof deck that forms the upper surface of the liquid surface space is formed on the inner side spaced from the bottomed inner cylinder in the axial center direction of the reactor vessel. The lower end of the partition member is extended to the liquid level of the liquid level space that is the lowest when the coolant level changes in a series of reactor operation states, and the inside of the liquid level space is defined as the inner space and the outer space. A first gas pipe connected to an inert gas supply system to supply an inert gas to the inner space and having a first on-off valve, and branched from the first gas pipe upstream of the first on-off valve Then, an inert gas is supplied to the outer space and a second gas pipe having a second on-off valve is provided, and when the filling for the reactor start-up preparation is completed, the liquid metal is filled with the inert gas in the inner space and the outer space. Use pressure difference generated by relatively changing pressure Since the coolant retention tank is filled, liquid metal is filled in the coolant retention tank in the reactor vessel, so that special consideration is required so that the liquid metal does not come into contact with air. There is no need to add a new one.

そして、内部空間の不活性ガス充填圧力を外部空間より高い圧力に設定し、この圧力差により内部空間の液面を押し下げるとともに外部空間の液面を上昇させて冷却材滞留槽へ液体金属を充填するので、冷却材滞留槽の上端部まで確実に液体金属を充填することができ、原子炉の起動時においては、温度上昇により膨張した液体ナトリウムNaが冷却材滞留槽から液面の低い上部プレナム内に溢流することによって、原子炉容器の壁面と接する冷却材の液面高さが冷却材滞留槽の上端と一致する一定位置に保たれる。   Then, the inert gas filling pressure in the internal space is set higher than that in the external space, and the liquid level in the internal space is pushed down and the liquid level in the external space is raised by this pressure difference to fill the coolant retention tank with liquid metal. Therefore, the liquid metal can be reliably filled up to the upper end of the coolant retention tank, and at the time of start-up of the nuclear reactor, the liquid sodium Na expanded by the temperature rise is from the coolant retention tank to the upper plenum having a low liquid level. By overflowing into the reactor, the liquid level of the coolant in contact with the wall of the reactor vessel is maintained at a fixed position where it coincides with the upper end of the coolant retention tank.

さらに、上記の原子炉容器構造においては、不活性ガス供給系に接続されて内側空間に不活性ガスを供給するとともに第1開閉弁を備えた第1ガス配管と、第1開閉弁より上流側で第1ガス配管から分岐して外側空間に不活性ガスを供給するとともに第2開閉弁を備えた第2ガス配管とを設け、第1開閉弁及び第2開閉弁の開閉操作により圧力差を生じさせているので、仕切部材の追設及び不活性ガス供給系の変更を行う比較的簡単な構造により、起動準備等において原子炉容器内の冷却材滞留槽に液体金属を容易に充填することができる。 Furthermore, in the above reactor vessel structure, the first gas pipe connected to the inert gas supply system to supply the inert gas to the inner space and provided with the first on-off valve, and the upstream side from the first on-off valve And a second gas pipe provided with a second on-off valve while supplying an inert gas to the outer space by branching from the first gas pipe, and the pressure difference by opening and closing the first on-off valve and the second on-off valve. As a result, it is possible to easily fill the coolant retention tank in the reactor vessel with liquid metal in preparation for start-up, etc. with a relatively simple structure in which a partition member is additionally installed and the inert gas supply system is changed. Can do.

上記の原子炉容器構造においては、前記内側空間内及び外側空間内の液位を検出する液位検出部を備えていることが好ましく、これにより、内側空間内及び外側空間内の液面管理が可能になるので、冷却材滞留槽に液体金属を確実に充填することができる。   In the reactor vessel structure described above, it is preferable to include a liquid level detection unit that detects the liquid level in the inner space and the outer space, thereby controlling the liquid level in the inner space and the outer space. Since it becomes possible, the coolant retention tank can be reliably filled with the liquid metal.

本発明に係る原子炉の運転方法は、上記の原子炉容器構造を備えている原子炉の運転方法であって、前記内部空間の不活性ガス充填圧力を前記外部空間より高い圧力に設定し、前記内部空間の液面を押し下げるとともに前記外部空間の液面を上昇させて前記冷却材滞留槽へ前記液体金属を充填する起動準備工程を備えていることを特徴とするものである。
A nuclear reactor operation method according to the present invention is a nuclear reactor operation method including the above-described nuclear reactor vessel structure , wherein the inert gas filling pressure in the internal space is set to a pressure higher than that in the external space, A starting preparation step is provided in which the liquid level in the internal space is pushed down and the liquid level in the external space is raised to fill the coolant retaining tank with the liquid metal.

このような原子炉の運転方法によれば、内部空間の不活性ガス充填圧力を外部空間より高い圧力に設定し、内部空間の液面を押し下げるとともに外部空間の液面を上昇させて冷却材滞留槽へ液体金属を充填する起動準備工程を備えているので、両空間に生じる圧力差を利用して冷却材滞留槽の上端部まで液体金属を確実に充填した状態での運転開始が可能になる。このため、原子炉の起動時においては、温度上昇により膨張した液体ナトリウムNaが冷却材滞留槽から液面の低い上部プレナム内に溢流することによって、原子炉容器の壁面と接する冷却材の液面高さが冷却材滞留槽の上端と一致する一定位置に保たれる。   According to such a reactor operating method, the inert gas filling pressure in the internal space is set to a pressure higher than that in the external space, the liquid level in the internal space is pushed down and the liquid level in the external space is raised to retain the coolant. Since it has a start-up preparation process that fills the tank with liquid metal, it is possible to start operation in a state in which the liquid metal is reliably filled up to the upper end of the coolant retention tank using the pressure difference generated in both spaces. . For this reason, when the reactor is started up, the liquid sodium Na expanded by the temperature rise overflows from the coolant retention tank into the lower plenum of the liquid level, so that the coolant liquid in contact with the wall of the reactor vessel The surface height is maintained at a fixed position that coincides with the upper end of the coolant retention tank.

上述した本発明によれば、原子炉の起動時において、温度上昇により膨張した液体ナトリウムNaが冷却材滞留槽から液面の低い上部プレナム内に溢流することによって、原子炉容器の壁面と接する冷却材の液面高さが冷却材滞留槽の上端と一致する一定位置に保たれる。この結果、原子炉容器の壁面においては、軸方向の温度勾配が緩和されて発生する熱応力も小さくなるので、原子炉容器の信頼性や運用性がより一層向上するという顕著な効果を得られる。
また、上述した本発明は、有底内筒と仕切部材を追加する容器構造の変更と、不活性ガス供給系の簡単な改造により実施できるため、追加設備を最小限に抑え、しかも、高い耐熱成立性を有している。特に、空気との接触防止対策が必要となるナトリウムのような液体金属(冷却材)配管を増設する必要がないため、プラントの信頼性や耐久性の向上に大きな効果を奏する。
According to the present invention described above, when the reactor is started up, the liquid sodium Na expanded by the temperature rise overflows from the coolant retention tank into the upper plenum having a low liquid level, thereby contacting the wall of the reactor vessel. The liquid level of the coolant is kept at a constant position that coincides with the upper end of the coolant retention tank. As a result, the thermal stress generated by relaxing the temperature gradient in the axial direction is reduced on the wall of the reactor vessel, so that a remarkable effect of further improving the reliability and operability of the reactor vessel can be obtained. .
Further, the present invention described above can be implemented by changing the container structure to which a bottomed inner cylinder and a partition member are added, and by simply remodeling the inert gas supply system, so that additional equipment is minimized and high heat resistance is achieved. Has feasibility. In particular, since there is no need to add a liquid metal (coolant) pipe such as sodium, which requires measures to prevent contact with air, it is highly effective in improving plant reliability and durability.

本発明に係る原子炉容器構造の一実施形態を示す図で、(a)は原子炉容器構造の概要(通常運転時の液位)を示す縦断面図、(b)は(a)のA−A断面図である。BRIEF DESCRIPTION OF THE DRAWINGS It is a figure which shows one Embodiment of the reactor vessel structure which concerns on this invention, (a) is a longitudinal cross-sectional view which shows the outline | summary (liquid level at the time of normal operation) of a reactor vessel structure, (b) is A of (a). It is -A sectional drawing. 図1の原子炉容器構造において、通常停止時の冷却材液位を示す縦断面図である。FIG. 2 is a longitudinal sectional view showing a coolant level at a normal stop in the reactor vessel structure of FIG. 1. 図1の原子炉容器構造において、冷却材滞留槽に対する冷却材の充填開始時の液位を示す縦断面図である。FIG. 2 is a longitudinal sectional view showing a liquid level at the start of filling of a coolant into a coolant retention tank in the reactor vessel structure of FIG. 1. 図1の原子炉容器構造において、冷却材滞留槽に対する冷却材の充填完了時の液位を示す縦断面図である。FIG. 2 is a longitudinal sectional view showing a liquid level at the completion of filling of a coolant into a coolant retention tank in the reactor vessel structure of FIG. 1. 図1の原子炉容器構造において、冷却材滞留槽に対する冷却材の充填が完了し、原子炉が起動準備完了時の状態にある場合の液位を示す縦断面図である。FIG. 2 is a longitudinal sectional view showing a liquid level when filling of a coolant into a coolant retention tank is completed in the reactor vessel structure of FIG. 冷却材滞留槽に対する冷却剤充填において、横軸の原子炉運転状態に対応する不活性ガス圧力を縦軸に示した不活性ガス圧力運用の説明図である。In coolant filling with respect to a coolant retention tank, it is explanatory drawing of the inert gas pressure operation which showed the inert gas pressure corresponding to the reactor operation state of a horizontal axis on the vertical axis | shaft. 原子炉容器内の冷却材液面が「液位上昇の場合」及び「液位一定の場合」について、原子炉容器壁面の温度勾配を示す図である。It is a figure which shows the temperature gradient of a reactor vessel wall surface about the case where the coolant level in a reactor vessel is "a liquid level rise" and "a case where a liquid level is constant." 従来の原子炉容器構造例を示す縦断面図である。It is a longitudinal cross-sectional view which shows the example of the conventional reactor vessel structure.

以下、本発明に係る原子炉容器構造及び原子炉の運転方法について、その一実施形態を図面に基づいて説明する。
図1に示す実施形態の原子炉容器10Aは、高速増殖炉等の高速炉に適用されるホットベッセルと呼ばれるものであり、炉壁10aの内部空間に炉心11を収納している。この炉心11は、原子炉容器10A内でスカート部12等の据付部により支持されている。
In the following, an embodiment of a reactor vessel structure and a reactor operating method according to the present invention will be described with reference to the drawings.
The reactor vessel 10A of the embodiment shown in FIG. 1 is called a hot vessel applied to a fast reactor such as a fast breeder reactor, and stores the core 11 in the internal space of the reactor wall 10a. The core 11 is supported by an installation portion such as a skirt portion 12 in the reactor vessel 10A.

原子炉容器10Aの内部は、炉心11の上端部側に隔壁13を設けて上部プレナム14及び中間プレナム18を形成している。なお、中間プレナム18の下方には、スカート部12によって仕切られた下部プレナム19が形成されている。
上部プレナム14は、液体金属である液体ナトリウムNa等の冷却材が充填されるとともに、液体ナトリウムNaの液面上部にアルゴン等の不活性ガス充填空間Gが形成される空間であり、原子炉容器10A内に設けた有液面構造の空間領域となる。なお、液体ナトリウムNaは、上述した従来構造と同様に、図示を省略したコールドレグ配管から原子炉容器10Aの下部プレナム19に流入し、炉心11を下から上に通過する過程で加熱された後に、上部プレナム14からホットレグ配管を通って冷却系に戻される。
Inside the reactor vessel 10 </ b> A, a partition wall 13 is provided on the upper end side of the core 11 to form an upper plenum 14 and an intermediate plenum 18. A lower plenum 19 partitioned by the skirt portion 12 is formed below the intermediate plenum 18.
The upper plenum 14 is a space in which a coolant such as liquid sodium Na, which is a liquid metal, is filled, and an inert gas filling space G such as argon is formed above the liquid surface of the liquid sodium Na. It becomes the space region of the liquid surface structure provided in 10A. Like the conventional structure described above, liquid sodium Na flows from a cold leg pipe (not shown) into the lower plenum 19 of the reactor vessel 10A and is heated in the process of passing through the core 11 from below to above. The upper plenum 14 is returned to the cooling system through hot leg piping.

原子炉容器10Aの内部には、炉壁10aの内側に取り付けられた内筒20を備えている。この内筒20は、下端部側を炉壁10aに結合して形成された内筒底面21を有している。このように、原子炉容器10Aの内側には、炉壁10aより小径で内筒底面21を有する有底内筒の内筒20が設置されているので、炉壁10aの内側と内筒20の外壁面との間には、冷却材である液体ナトリウムNaを滞留させるための空間である冷却材滞留槽22が形成されている。   An inner cylinder 20 attached inside the reactor wall 10a is provided in the reactor vessel 10A. The inner cylinder 20 has an inner cylinder bottom surface 21 formed by coupling the lower end side to the furnace wall 10a. Thus, since the inner cylinder 20 of the bottomed inner cylinder having the inner cylinder bottom surface 21 having a smaller diameter than the reactor wall 10a is installed inside the reactor vessel 10A, the inner side of the reactor wall 10a and the inner cylinder 20 A coolant retention tank 22 that is a space for retaining liquid sodium Na, which is a coolant, is formed between the outer wall surface.

この内筒20は、上述した有液面空間の上部プレナム14内において、原子炉通常(定常)運転時の冷却材液位L3よりも高い位置まで設けられている。
なお、内筒20の下端部及び内筒底面21は、原子炉トリップ時の熱過渡が厳しい上部プレナム14に隣接することは望ましくないため、隔壁13よりやや下方の中間プレナム18側に設けられている。
The inner cylinder 20 is provided up to a position higher than the coolant level L3 in the normal (steady) operation of the reactor in the upper plenum 14 of the liquid surface space described above.
The lower end portion of the inner cylinder 20 and the inner cylinder bottom surface 21 are not desirably adjacent to the upper plenum 14 where thermal transients during severe reactor trips are severe, and therefore are provided on the intermediate plenum 18 side slightly below the partition wall 13. Yes.

そして、図示の原子炉容器10Aは、冷却材バウンダリを構成する重要機器であり、冷却材の一例として液体ナトリウムNaが使用されている。この場合、液体ナトリウムNaは、凍結防止のため200℃程度以下の低温とならないようにする必要があり、従って、運転状況に応じて加熱及び保温がなされている。また、原子炉容器10Aの内部は、化学的に活性な冷却材であるナトリウムが空気と触れることを防ぐため、液体ナトリウムNaの上部に、たとえばアルゴン(Ar)等の不活性ガスを充填した不活性ガス充填空間Gを設けた有液面構造となっている。
このような原子炉容器10Aの内部に対し、本実施形態では、内筒20から液体ナトリウムNaのスムーズな流通を可能にする程度の隙間を形成するように離間した内側に、内筒20よりも小径の円筒形状を有する仕切部材25が設けられている。この仕切部材25は、上端部側がルーフデッキ15の下面に固定支持され、下端部が後述する充填完了時の冷却材液位L5(図4参照)より下方まで延在するように設けられている。
The illustrated reactor vessel 10A is an important device that constitutes the coolant boundary, and liquid sodium Na is used as an example of the coolant. In this case, it is necessary to prevent the liquid sodium Na from becoming a low temperature of about 200 ° C. or less in order to prevent freezing. Therefore, the liquid sodium Na is heated and kept warm according to the operating conditions. In addition, the inside of the reactor vessel 10A is an inert gas in which an upper part of liquid sodium Na is filled with an inert gas such as argon (Ar) in order to prevent sodium, which is a chemically active coolant, from coming into contact with air. It has a liquid surface structure in which an active gas filling space G is provided.
With respect to the inside of such a nuclear reactor vessel 10A, in the present embodiment, the inner side of the inner cylinder 20 is spaced apart from the inner cylinder 20 so as to form a gap that allows a smooth flow of liquid sodium Na. A partition member 25 having a small-diameter cylindrical shape is provided. The partition member 25 is provided so that the upper end side is fixedly supported on the lower surface of the roof deck 15 and the lower end portion extends below a coolant level L5 (see FIG. 4) at the time of filling described later. .

すなわち、仕切部材25の長さは、後述する一連の原子炉運転状態(通常運転時、通常停止時、充填開始時、充填完了時及び起動準備完了時)において、冷却材液位変化で最も液面が低下する充填完了時に、下端部が必ず液体ナトリウムNaの液面内に入り込むように設定されている。このとき、仕切部材25の下端部は、液体ナトリウムNaの液面内に深く入り込む必要はなく、最も液面が低下する充填完了時においても、上部プレナム14の内部に形成された不活性ガス充填空間Gを内側空間Gi及び外側空間Goに分割できればよい。   That is, the length of the partition member 25 is the most liquid level change in the coolant level change in a series of reactor operation states (normal operation, normal stop, filling start, filling completion, and startup preparation completion) described later. It is set so that the lower end portion always enters the liquid surface of the liquid sodium Na when the filling of the surface is lowered. At this time, the lower end of the partition member 25 does not need to penetrate deeply into the liquid level of the liquid sodium Na, and is filled with the inert gas formed inside the upper plenum 14 even when filling is completed when the liquid level is the lowest. It is only necessary that the space G can be divided into the inner space Gi and the outer space Go.

このような内側空間Gi及び外側空間Goは閉空間であり、従って、両空間の不活性ガス充填圧力を相対的に変化させることにより、両空間に生じる圧力差を利用して冷却材滞留槽22に冷却材(液体金属)の充填が可能になる。すなわち、内側空間Gi及び外側空間Go内の不活性ガス充填圧力を相対的に変化させると、両空間内に生じる圧力差により液体ナトリウムNaの液位が変化するので、この液位変化を利用して冷却材滞留槽22の上端部まで冷却材の液体ナトリウムNaを充填することができる。   Such an inner space Gi and an outer space Go are closed spaces. Therefore, by changing the inert gas filling pressure between the two spaces relatively, a pressure difference generated in the two spaces is used to make the coolant retention tank 22. It is possible to fill the coolant (liquid metal). That is, when the inert gas filling pressure in the inner space Gi and the outer space Go is relatively changed, the liquid level of the liquid sodium Na changes due to the pressure difference generated in both spaces. Thus, the coolant liquid sodium Na can be filled up to the upper end of the coolant retention tank 22.

また、本実施形態では、不活性ガス充填空間Gにアルゴン等の不活性ガスを供給する不活性ガス供給(充填)系30から分岐して、すなわち、内側空間Giに不活性ガスを供給する第1ガス配管31から分岐するようにして、外側空間Goに不活性ガスを供給する第2ガス配管32が追設されている。第1ガス配管31及び第2ガス配管32には、それぞれ単独での不活性ガス供給を可能にするため、第1開閉弁33及び第2開閉弁34が設けられている。
なお、不活性ガス供給系30の適所には、図示省略の不活性ガス昇圧用圧縮機が設けられている。
In this embodiment, the inert gas supply space G branches off from the inert gas supply (filling) system 30 that supplies an inert gas such as argon, that is, the inert gas is supplied to the inner space Gi. A second gas pipe 32 for supplying an inert gas to the outer space Go is additionally provided so as to branch from the first gas pipe 31. The first gas pipe 31 and the second gas pipe 32 are provided with a first on-off valve 33 and a second on-off valve 34 in order to enable independent supply of inert gas.
Note that an inert gas pressurizing compressor (not shown) is provided at an appropriate position of the inert gas supply system 30.

換言すれば、上述した内側空間Gi及び外側空間Goの圧力差は、不活性ガス供給系30に接続されて内側空間Giに不活性ガスを供給するとともに第1開閉弁33を備えた第1ガス配管31と、第1開閉弁33より上流側で第1ガス配管31から分岐して外側空間Goに不活性ガスを供給するとともに第2開閉弁を備えた第2ガス配管32とを設け、第1開閉弁33及び第2開閉弁34の開閉操作により生じさせることができる。
このように、本実施形態の原子炉容器構造は、冷却材滞留槽22を備えた原子炉容器10Aに対して、仕切部材25と、第2ガス配管32と、第1開閉弁33と、第2開閉弁34とを追加したことにより、冷却材の液体金属を冷却材滞留槽22の上端部まで充填可能となる。
In other words, the pressure difference between the inner space Gi and the outer space Go described above is the first gas that is connected to the inert gas supply system 30 to supply the inert gas to the inner space Gi and includes the first on-off valve 33. A pipe 31 and a second gas pipe 32 branched from the first gas pipe 31 upstream of the first on-off valve 33 to supply an inert gas to the outer space Go and provided with a second on-off valve; It can be generated by opening / closing the first opening / closing valve 33 and the second opening / closing valve 34.
Thus, the reactor vessel structure of the present embodiment is different from the reactor vessel 10A provided with the coolant retention tank 22 with respect to the partition member 25, the second gas pipe 32, the first on-off valve 33, and the first By adding the 2 on-off valve 34, the liquid metal of the coolant can be filled up to the upper end of the coolant retention tank 22.

以下、冷却材滞留槽22に液体ナトリウムNaを充填する手順について、一連の原子炉運転状態(通常運転時、通常停止時、充填開始時、充填完了時及び起動準備完了時)とともに説明する。
図1に示す原子炉の通常運転時には、不活性ガス供給系30から圧力Pに設定された不活性ガスが供給されている。このとき、第1開閉弁33及び第2開閉弁34はいずれも開とされ、従って、内側空間Gi及び外側空間Goの内部は、ともに同圧のPに維持されている。なお、通常運転時における液体ナトリウムNaの液位はL3であり、冷却材滞留槽22には、上端部まで液体ナトリウムNaが満たされている。
Hereinafter, the procedure for filling the coolant retention tank 22 with liquid sodium Na will be described together with a series of reactor operation states (normal operation, normal stop, filling start, filling completion, and startup preparation completion).
During normal operation of the nuclear reactor shown in FIG. 1, an inert gas set at a pressure P 0 is supplied from an inert gas supply system 30. In this case, the first on-off valve 33 and the second on-off valve 34 is either opened, therefore, within the inner space Gi and the outer space Go are both maintained at P 0 of the same pressure. Note that the liquid sodium Na level during normal operation is L3, and the coolant retention tank 22 is filled with liquid sodium Na up to the upper end.

このような通常運転時の状態は、原子炉運転状態と不活性ガス圧力との関係を示す不活性ガス圧力運用の説明図(図6参照)において、点Aまで継続されている。
なお、図1から図5において、第1開閉弁33及び第2開閉弁34は、全閉状態が黒塗りで表示されている。
Such a state during normal operation is continued up to point A in the explanatory view of the inert gas pressure operation showing the relationship between the reactor operation state and the inert gas pressure (see FIG. 6).
In FIG. 1 to FIG. 5, the first on-off valve 33 and the second on-off valve 34 are displayed in black in the fully closed state.

図2に示す原子炉の通常停止時には、内側空間Gi、外側空間Go及び冷却材滞留槽22の全てにおいて、温度低下に伴って液体ナトリウムNaの液位が低下する。この液位低下とともに、不活性ガス供給系30の圧力は、保守作業のためPからPに低減される。すなわち、図6の不活性ガス圧力運用において、原子炉運転状態は点Aから点Bに変化している。
この場合、第1開閉弁33及び第2開閉弁34はいずれも開であるから、内側空間Gi及び外側空間Goの内部は同圧のPに維持される。また、内部空間Giの冷却材液位はL2まで低下する。
When the nuclear reactor shown in FIG. 2 is normally shut down, the liquid sodium Na level in the inner space Gi, the outer space Go, and the coolant retention tank 22 decreases as the temperature decreases. Along with the lowering of the liquid level, the pressure of the inert gas supply system 30 is reduced from P 0 to P 1 for maintenance work. That is, in the inert gas pressure operation of FIG. 6, the reactor operating state changes from point A to point B.
In this case, since both the first on-off valve 33 and the second on-off valve 34 are open, the insides of the inner space Gi and the outer space Go are maintained at P 1 having the same pressure. Further, the coolant level in the internal space Gi decreases to L2.

図3に示す原子炉の充填開始時では、通常停止時に液面低下した冷却材滞留槽22の上端部まで液体ナトリウムNaを補充する。すなわち、図6に示す不活性ガス圧力運用において、原子炉運転状態は、保守作業等により点Bから点Cまで、液体ナトリウムNaを保温しながら圧力Pを維持する状態を継続した後、冷却材滞留槽22に対する冷却材充填を開始する。このとき、第2ガス配管32の第2開閉弁34を全閉とし、かつ、不活性ガス供給系の圧力をPからPに上昇させる。 When the filling of the nuclear reactor shown in FIG. 3 is started, liquid sodium Na is replenished up to the upper end portion of the coolant retention tank 22 whose liquid level has been lowered during the normal stop. That is, in the inert gas pressure operation shown in FIG. 6, the reactor operating state is maintained after maintaining the pressure P 1 while keeping the liquid sodium Na from point B to point C by maintenance work or the like, and then cooled. Coolant filling into the material retention tank 22 is started. At this time, the second on-off valve 34 of the second gas pipe 32 is fully closed, and the pressure of the inert gas supply system is increased from P 1 to P 2 .

こうして冷却材充填が開始されると、図6の不活性ガス圧力運用において、不活性ガスの圧力は冷却材充填開始前の点C(図2)から冷却材充填中の領域C′(図3)を経て、冷却材充填完了の点D(図4)に変化する。
この結果、閉空間である内側空間Giと外側空間Goとの間には圧力差が生じ、高圧側(圧力P)の内側空間Giでは液面が冷却材液位L4まで低下し、低圧側(圧力P)の外側空間Goでは液面が上昇する。これは、内側空間Giと外側空間Goとの間が連通しており、液体ナトリウムNaの流通が可能になっているためであり、内側空間Giで液面低下した液体ナトリウムNaの容積分だけ外側空間Goの液面が上昇する。
When the coolant filling is started in this way, in the inert gas pressure operation of FIG. 6, the pressure of the inert gas is changed from the point C (FIG. 2) before the start of the coolant filling to the region C ′ (FIG. 3) during the coolant filling. ) To change to a point D (FIG. 4) of completion of coolant filling.
As a result, a pressure difference is generated between the inner space Gi that is a closed space and the outer space Go, and the liquid level is reduced to the coolant level L4 in the inner space Gi on the high pressure side (pressure P 2 ). The liquid level rises in the outer space Go of (pressure P 1 ). This is because the inner space Gi and the outer space Go communicate with each other, and the flow of the liquid sodium Na is possible, and the outer side is the volume of the liquid sodium Na whose liquid level is reduced in the inner space Gi. The liquid level in the space Go rises.

このような液面変化により、外側空間Go内の液体ナトリウムNaは、液面が冷却材滞留槽22の上端部に到達し、さらに冷却材滞留槽22の内部に流入する。この結果、不活性ガス充填系30の圧力調整により、液面低下した冷却材滞留槽22の内部に液体ナトリウムNaを充填することができ、最終的には図4に示す充填完了時の状態となる。なお、活性ガス充填系30の圧力調整には、不活性ガス供給系30にもともと設けられている不活性ガス昇圧用圧縮機を利用すればよい。   Due to such a change in the liquid level, the liquid sodium Na in the outer space Go reaches the upper end of the coolant retention tank 22 and further flows into the coolant retention tank 22. As a result, by adjusting the pressure of the inert gas filling system 30, the liquid sodium Na can be filled into the coolant retaining tank 22 whose liquid level has been lowered, and finally the state at the completion of filling shown in FIG. Become. For adjusting the pressure of the active gas filling system 30, an inert gas pressurizing compressor originally provided in the inert gas supply system 30 may be used.

図4の充填完了時は、図6の不活性ガス圧力運用における点Dとなり、不活性ガス供給系30の圧力がPに維持されている。
従って、内部空間Giの内部圧力はPとなり、全閉の第2開閉弁34により不活性ガス供給系30と遮断されている外部空間Goの内部圧力は、内部空間Gi側から内部圧力Pの影響を受けることにより、PからP′に上昇する。すなわち、図6の不活性ガス圧力運用図においては、圧力変化が内部空間Giと異なる場合について、外部空間Goの圧力変化は図中に一点鎖線で示されている。
Filling completion time of 4 point D becomes the inert gas pressure operation of FIG. 6, the pressure of the inert gas supply system 30 is maintained at P 2.
Therefore, the internal pressure of the inner space Gi is P 2, and the internal pressure in the external space Go to the second on-off valve 34 fully closed are isolated from the inert gas supply system 30, the internal pressure P 2 from the internal space Gi side by receiving the impact increases from P 1 to P 1 '. That is, in the inert gas pressure operation diagram of FIG. 6, when the pressure change is different from the internal space Gi, the pressure change in the external space Go is indicated by a one-dot chain line in the drawing.

そして、本実施形態の原子炉容器構造を備えた原子炉の運転方法は、内部空間Giの不活性ガス充填圧力を外部空間Goより高い圧力に設定し、内部空間Giの液面を押し下げるとともに外部空間Goの液面を上昇させて冷却材滞留槽22へ液体ナトリウムNaを充填する起動準備工程を備えている。
このような原子炉の運転方法によれば、内部空間Gi及び外部空間Goに生じる圧力差を利用し、冷却材滞留槽22の上端部まで冷却材の液体ナトリウムNaを確実に充填した状態で原子炉の運転開始が可能になる。この結果、原子炉の起動時においては、温度上昇により膨張した液体ナトリウムNaが冷却材滞留槽22から液面の低い上部プレナム14内に溢流することによって、原子炉容器10Aの炉壁10aと接する冷却材の液面高さが冷却材滞留槽22の上端と一致した一定位置に保たれる。
And the operating method of the nuclear reactor provided with the reactor vessel structure of this embodiment sets the inert gas filling pressure of the internal space Gi to a pressure higher than the external space Go, pushes down the liquid level of the internal space Gi and externally A startup preparation step of raising the liquid level of the space Go and filling the coolant retention tank 22 with liquid sodium Na is provided.
According to such a method of operating the nuclear reactor, the pressure difference generated in the internal space Gi and the external space Go is used, and the liquid sodium Na as a coolant is reliably filled up to the upper end portion of the coolant retention tank 22. The furnace can be started. As a result, when the reactor is started up, the liquid sodium Na expanded by the temperature rise overflows from the coolant retention tank 22 into the upper plenum 14 having a low liquid level, and thus the reactor wall 10a of the reactor vessel 10A The liquid level of the coolant in contact with the coolant is kept at a fixed position that coincides with the upper end of the coolant retention tank 22.

こうして冷却材の充填が完了すると、図6の不活性ガス圧力運用における点Dから点Eまで充填完了時の状態が維持される。この後、上述した充填完了時の状態から第2開閉弁34を全開とすると内側空間Gi及び外側空間Goがともに圧力Pとなり、さらに不活性ガス供給系30の圧力をPに上昇させると、図6に点Fで示す起動準備完了時の状態となる。
このとき、液体ナトリウムNaは保温されているため温度変化はなく、冷却材滞留槽22の内部には上端まで液体ナトリウムNaが充填されている。また、冷却材滞留槽22の内部を除く上部プレナム14内の冷却材液位L6は、図4に示す充填完了時の冷却材液位L5よりやや上昇する。
When the filling of the coolant is completed in this way, the state at the time of filling is maintained from point D to point E in the inert gas pressure operation of FIG. Thereafter, the inner space Gi and the outer space Go both pressure P 2 becomes when fully opened the second on-off valve 34 from the filling completion time of state described above, when the further increase the pressure of the inert gas supply system 30 to P 0 FIG. 6 shows a state at the completion of the start-up preparation indicated by a point F.
At this time, since the liquid sodium Na is kept warm, there is no temperature change, and the coolant staying tank 22 is filled with the liquid sodium Na up to the upper end. Moreover, the coolant level L6 in the upper plenum 14 excluding the inside of the coolant retention tank 22 is slightly higher than the coolant level L5 at the completion of filling shown in FIG.

このような本実施形態の原子炉容器構造によれば、有底の内筒20から離間した内側に下端部を充填完了時の冷却材液面内まで延在させた仕切部材25を設けることにより、有液面空間となる不活性ガス充填空間Gの内部を内側空間Gi及び外側空間Goに分割し、冷却材となる液体金属の液体ナトリウムNaを冷却材滞留槽22に充填する際には、内側空間Gi及び外側空間Goの不活性ガス充填圧力を相対的に変化させて生じる圧力差を利用した充填が可能となる。
このため、原子炉の起動準備として、原子炉容器10A内の冷却材滞留槽22に液体ナトリウムNaを容易かつ安全に充填できるようになる。すなわち、液体金属が空気と接触しないよう十分な配慮を必要とする液体ナトリウムNaの液体金属供給配管を新たに増設する必要はなく、仕切部材25の増設と不活性ガス供給系30の簡単な改造とを実施するだけで、特に原子炉の起動時に問題となる炉壁10aの熱応力対策が実現する。
According to the reactor vessel structure of the present embodiment as described above, by providing the partition member 25 with the lower end portion extending to the coolant level at the completion of filling, on the inner side separated from the bottomed inner cylinder 20 When the inside of the inert gas filling space G that becomes the liquid surface space is divided into the inner space Gi and the outer space Go, and the liquid sodium Na, which is the liquid metal serving as the coolant, is filled in the coolant retention tank 22, Filling using a pressure difference generated by relatively changing the inert gas filling pressure in the inner space Gi and the outer space Go becomes possible.
For this reason, liquid sodium Na can be easily and safely filled into the coolant retention tank 22 in the reactor vessel 10A as preparation for starting up the reactor. That is, there is no need to newly add a liquid metal supply pipe of liquid sodium Na that requires sufficient consideration so that the liquid metal does not come into contact with air, and an additional partition member 25 and a simple modification of the inert gas supply system 30 By implementing the above, measures against thermal stress of the reactor wall 10a, which becomes a problem particularly at the time of startup of the reactor, are realized.

この熱応力対策について具体的に説明すると、図5に示す起動準備完了時のように、原子炉の起動前に冷却材滞留槽22の上端まで液体ナトリウムNaを充填しておくと、起動時の温度上昇により膨張した液体ナトリウムNaが冷却材滞留槽22から液面の低い上部プレナム14内に溢流する。従って、原子炉の起動時には、原子炉容器10Aの壁面と接する液体ナトリウムNaの液面高さが冷却材滞留槽22の上端と一致し、通常運転まで変動することなく一定に保たれる。   This thermal stress countermeasure will be described in detail. When the start-up preparation shown in FIG. 5 is completed, if liquid sodium Na is filled up to the upper end of the coolant retention tank 22 before the start-up of the nuclear reactor, Liquid sodium Na expanded by the temperature rise overflows from the coolant retention tank 22 into the upper plenum 14 having a low liquid level. Therefore, when the nuclear reactor is started up, the liquid level of liquid sodium Na in contact with the wall surface of the reactor vessel 10A coincides with the upper end of the coolant retention tank 22, and is kept constant without fluctuation until normal operation.

ところで、上述した原子炉容器10Aは、内側空間Gi内及び外側空間Go内の液位を検出する液位検出部(不図示)を備えていることが望ましい。すなわち、内部空間G内で変化する液体ナトリウムNaの液位を検出するため、たとえば仕切部材25や内筒20の壁面に液面センサを設置して不活性ガス供給系30の圧力調整に利用すればよい。
具体的に説明すると、内部空間G内で変化する液体ナトリウムNaの液位を段階的または連続的に検出し、上述した原子炉運転状態に対応する所定の液位まで液面変化したことを確認すれば、不活性ガス昇圧用圧縮機の運転制御を確実に行うことができる。すなわち、内側空間G内の正確な液面管理が可能になるので、冷却材滞留槽22に対して冷却材の液体ナトリウムNaを確実に充填することができる。
By the way, it is desirable that the reactor vessel 10A described above includes a liquid level detection unit (not shown) that detects the liquid level in the inner space Gi and the outer space Go. That is, in order to detect the liquid level of the liquid sodium Na that changes in the internal space G, for example, a liquid level sensor is installed on the wall surface of the partition member 25 or the inner cylinder 20 and used to adjust the pressure of the inert gas supply system 30. That's fine.
Specifically, the liquid level of the liquid sodium Na that changes in the internal space G is detected stepwise or continuously, and it is confirmed that the liquid level has changed to the predetermined liquid level corresponding to the above-described reactor operating state. Then, the operation control of the inert gas pressurizing compressor can be reliably performed. That is, since the liquid level in the inner space G can be accurately managed, the coolant staying tank 22 can be reliably filled with the liquid sodium Na as the coolant.

このようにして、原子炉起動時に炉壁10aと接する液体ナトリウムNaの液位を一定に保つことができると、図7に示す「液位一定の場合」のように、液体ナトリウムNaの液面近傍において軸方向に生じていた大きな温度勾配を低減でき、この結果、液面近傍部の熱応力も小さくなる。
このため、原子炉の供用期間中に起動・停止を繰り返しても、原子炉容器10Aに対して繰り返し発生する熱応力を低減できるので、起動のたびに原子炉容器10Aの径が縮む変形(液面ラチェット)やクリープ疲労による破損の問題を低減または解消することができる。
また、冷却材滞留槽22を設けることにより、上述した起動時のみならず、液体ナトリウムNaの体積が収縮する通常停止時や緊急停止時においても、炉壁10aと接する液体ナトリウムNaの液面の下がり幅を小さくすることができ、液面近傍部の熱応力か小さくなるなど、熱応力に起因する懸念を軽減することができる。
In this way, when the liquid sodium Na level in contact with the reactor wall 10a can be kept constant at the time of starting the reactor, the liquid level of the liquid sodium Na can be obtained as shown in FIG. A large temperature gradient generated in the axial direction in the vicinity can be reduced, and as a result, the thermal stress in the vicinity of the liquid surface is also reduced.
For this reason, even if the start / stop is repeated during the operation period of the reactor, the thermal stress repeatedly generated on the reactor vessel 10A can be reduced. Therefore, the deformation (liquid) The problem of breakage due to surface ratchet) or creep fatigue can be reduced or eliminated.
Further, by providing the coolant retention tank 22, not only at the time of start-up described above but also at the time of normal stop or emergency stop when the volume of liquid sodium Na contracts, the liquid sodium Na level in contact with the furnace wall 10a is reduced. The drop width can be reduced, and the concern due to thermal stress such as the thermal stress in the vicinity of the liquid level can be reduced.

また、上述した実施形態は、図8に示した従来例に対する追加設備として、内筒底面21を有する内筒20及び仕切部材25の追設と、上部プレナム14に不活性ガスを供給する不活性ガス充填系30の改造のみである。すなわち、原子炉容器10A内は単純な構造の円筒20及び仕切部材25を追加するだけでよく、しかも、不活性ガス充填系30の改造も単純な構成で大がかりなものではないから、比較的低コストで容易に実施することが可能である。   Further, in the embodiment described above, as an additional facility with respect to the conventional example shown in FIG. 8, the inner cylinder 20 having the inner cylinder bottom surface 21 and the partition member 25 are additionally provided, and the inert gas for supplying the inert gas to the upper plenum 14 is provided. Only the gas filling system 30 is modified. That is, it is only necessary to add the cylinder 20 and the partition member 25 having a simple structure in the reactor vessel 10A, and the modification of the inert gas filling system 30 is not a large-scale structure with a simple configuration. It can be easily implemented at a low cost.

上述した本実施形態の原子炉容器構造によれば、原子炉の起動時において、原子炉容器10Aの炉壁10aと接する液体ナトリウムNaの液面高さは、常に冷却材滞留槽22の上端と一致する一定位置に保たれる。この結果、原子炉容器10Aの壁面においては、軸方向の温度勾配が緩和されて発生する熱応力も小さくなるので、原子炉容器の信頼性や運用性がより一層向上するという顕著な効果を得られる。   According to the reactor vessel structure of the present embodiment described above, the liquid level height of the liquid sodium Na in contact with the reactor wall 10a of the reactor vessel 10A is always the upper end of the coolant retention tank 22 when the reactor is started. It is kept in a constant position that matches. As a result, on the wall surface of the reactor vessel 10A, the thermal stress generated due to the relaxation of the temperature gradient in the axial direction is reduced, so that a remarkable effect of further improving the reliability and operability of the reactor vessel is obtained. It is done.

また、上述した本実施形態は、有底内筒に仕切部材を追加する容器構造の変更と、不活性ガス供給系の簡単な改造により実施できるため、追加設備を最小限に抑え、しかも、高い耐熱成立性を有している。特に、空気との接触防止対策が必要となるナトリウムのような液体金属(冷却材)配管を増設する必要がないため、プラントの信頼性や耐久性の向上に大きな効果を奏する。   Moreover, since this embodiment mentioned above can be implemented by the change of the container structure which adds a partition member to a bottomed inner cylinder, and simple modification of an inert gas supply system, additional equipment is minimized and high Has heat resistance. In particular, since there is no need to add a liquid metal (coolant) pipe such as sodium, which requires measures to prevent contact with air, it is highly effective in improving plant reliability and durability.

また、内側空間Gi及び外側空間Goの不活性ガス充填圧力を相対的に変化させて生じる圧力差を利用して冷却材滞留槽22に冷却材の液体金属を充填する場合、圧力差の形成が内側空間Gi側の昇圧に限定されることはなく、たとえば外側空間Go側の圧力を低下させるように逆の圧力調整を行ってもよい。   In addition, when the coolant retention tank 22 is filled with the liquid metal of the coolant using the pressure difference generated by relatively changing the inert gas filling pressure in the inner space Gi and the outer space Go, the pressure difference is formed. The pressure increase is not limited to the inner space Gi side, and for example, reverse pressure adjustment may be performed so as to reduce the pressure on the outer space Go side.

また、上述した本実施形態は、たとえば特許文献3〜5に記載されているような貯留バケット内に冷却材を充填する場合にも適用可能である。
なお、本発明は上述した実施形態に限定されることはなく、たとえば冷却材や不活性ガスの種類、冷却材充填系の構成や充填・回収手順など、その要旨を逸脱しない範囲内において適宜変更することができる。
Moreover, this embodiment mentioned above is applicable also when filling a coolant in the storage bucket as described in patent documents 3-5, for example.
Note that the present invention is not limited to the above-described embodiment, and may be appropriately changed within a range not departing from the gist thereof, such as the type of coolant and inert gas, the configuration of the coolant filling system, and the filling / recovery procedure. can do.

10A 原子炉容器
10a 炉壁
11 炉心
12 スカート部
13 隔壁
14 上部プレナム
15 ルーフデッキ
20 内筒
21 内筒底面
22 冷却材滞留槽
25 仕切部材
30 不活性ガス充填系
31 第1ガス配管
32 第2ガス配管
33 第1開閉弁
34 第2開閉弁
G 不活性ガス充填空間
Gi 内部空間
Go 外部空間
10A Reactor vessel 10a Reactor wall 11 Core 12 Skirt part 13 Bulkhead 14 Upper plenum 15 Roof deck 20 Inner cylinder 21 Inner cylinder bottom 22 Coolant retention tank 25 Partition member 30 Inert gas filling system 31 First gas piping 32 Second gas Piping 33 First open / close valve 34 Second open / close valve G Inert gas filling space Gi Internal space Go External space

Claims (3)

炉心を収納した原子炉容器内に、液体金属の冷却材を充填した液面上部に不活性ガス充填空間が形成されている有液面空間を設け、該有液面空間の容器壁面内側に、原子炉定常運転時の冷却材液面より高い位置まで有底内筒を設置して前記容器壁面と前記有底内筒との間に形成された冷却材滞留槽を備えている原子炉容器構造であって、
前記有底内筒から前記原子炉容器の軸中心方向へ離間した内側に前記有液面空間の上面を形成するルーフデッキの下面に固定支持される仕切部材を設け、該仕切り部材の下端部を一連の原子炉運転状態における冷却材液位変化で最も低下する前記有液面空間の液面内まで延在させて前記有液面空間の内部を内側空間及び外側空間に分割し、
不活性ガス供給系に接続されて前記内側空間に不活性ガスを供給するとともに第1開閉弁を備えた第1ガス配管と、前記第1開閉弁より上流側で前記第1ガス配管から分岐して前記外側空間に不活性ガスを供給するとともに第2開閉弁を備えた第2ガス配管とを設け、
原子炉起動準備の充填完了時に、前記液体金属が、前記内側空間及び前記外側空間の不活性ガス充填圧力を相対的に変化させて生じる圧力差を利用して前記冷却材滞留槽に充填されることを特徴とする原子炉容器構造。
In the reactor vessel containing the reactor core, a liquid surface space in which an inert gas filling space is formed at the upper part of the liquid surface filled with the liquid metal coolant is provided, and inside the vessel wall surface of the liquid surface space, Reactor vessel structure having a bottomed inner cylinder installed up to a position higher than the coolant level during steady-state operation of the reactor and provided with a coolant retention tank formed between the vessel wall surface and the bottomed inner cylinder Because
A partition member fixed and supported on the lower surface of the roof deck that forms the upper surface of the liquid surface space is provided inside the bottomed inner cylinder in the axial center direction of the reactor vessel, and a lower end portion of the partition member is provided. The inside of the liquid surface space is divided into an inner space and an outer space by extending into the liquid surface of the liquid surface space that is the lowest when the coolant level changes in a series of reactor operation states ,
A first gas pipe connected to an inert gas supply system to supply an inert gas to the inner space and having a first on-off valve, and branched from the first gas pipe upstream of the first on-off valve. Providing an inert gas to the outer space and a second gas pipe provided with a second on-off valve,
Upon completion of preparation for reactor start-up, the liquid metal is filled into the coolant retention tank using a pressure difference generated by relatively changing the inert gas filling pressure in the inner space and the outer space. A reactor vessel structure characterized by that.
前記内側空間内の液位を検出する液位検出部を備えていることを特徴とする請求項1に記載の原子炉容器構造。 The reactor vessel structure according to claim 1 , further comprising a liquid level detection unit that detects a liquid level in the inner space. 請求項1または2に記載の原子炉容器構造を備えている原子炉の運転方法であって、
前記内側空間の不活性ガス充填圧力を前記外側空間より高い圧力に設定し、前記内側空間の液面を押し下げるとともに前記外側空間の液面を上昇させて前記冷却材滞留槽へ前記液体金属を充填する起動準備工程を備えていることを特徴とする原子炉の運転方法。
A method of operating a nuclear reactor comprising the reactor vessel structure according to claim 1 or 2 ,
Set the inert gas filling pressure in the inner space at a higher pressure than the outer space, filling the liquid metal the raises the liquid surface of the outer space with push down the liquid surface of the inner space to the coolant residence tank A reactor operating method comprising a startup preparation step.
JP2011081254A 2010-07-14 2011-03-31 Reactor vessel structure and reactor operation method Active JP5773710B2 (en)

Priority Applications (2)

Application Number Priority Date Filing Date Title
JP2011081254A JP5773710B2 (en) 2011-03-31 2011-03-31 Reactor vessel structure and reactor operation method
PCT/JP2011/065652 WO2012008369A1 (en) 2010-07-14 2011-07-08 Nuclear reactor containment structure and nuclear reactor operation method

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP2011081254A JP5773710B2 (en) 2011-03-31 2011-03-31 Reactor vessel structure and reactor operation method

Publications (2)

Publication Number Publication Date
JP2012215475A JP2012215475A (en) 2012-11-08
JP5773710B2 true JP5773710B2 (en) 2015-09-02

Family

ID=47268361

Family Applications (1)

Application Number Title Priority Date Filing Date
JP2011081254A Active JP5773710B2 (en) 2010-07-14 2011-03-31 Reactor vessel structure and reactor operation method

Country Status (1)

Country Link
JP (1) JP5773710B2 (en)

Family Cites Families (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2248583B1 (en) * 1973-10-18 1976-10-01 Commissariat Energie Atomique
JPS6246290A (en) * 1985-08-26 1987-02-28 株式会社東芝 Upper core mechanism
JPH04188095A (en) * 1990-11-22 1992-07-06 Mitsubishi Heavy Ind Ltd Vessel wall cooling device for reactor vessel
JP2972162B2 (en) * 1997-04-17 1999-11-08 核燃料サイクル開発機構 Furnace wall cooling protection structure of fast reactor

Also Published As

Publication number Publication date
JP2012215475A (en) 2012-11-08

Similar Documents

Publication Publication Date Title
JP4148417B2 (en) Stable passive residual heat removal system for liquid metal furnace
KR100966854B1 (en) Fully passive decay heat removal system for sodium cooled fast reactor with a partially-immersed decay heat exchanger
JP5606466B2 (en) Gas supply device
KR101752717B1 (en) Reactor system with a lead-cooled fast reactor
EP2676277B1 (en) Nuclear reactor and method of removing heat from the nuclear reactor
US11031146B2 (en) Method for heating a primary coolant in a nuclear steam supply system
KR101255588B1 (en) Device for residual heat removal of reactor and its method
US10115487B2 (en) Shutdown system for a nuclear steam supply system
KR101789135B1 (en) Safety injection system and nuclear power plant having the same
US10629312B2 (en) Light water reactor with condensing steam generator
JP5773710B2 (en) Reactor vessel structure and reactor operation method
CN210087405U (en) Closed cooling water system with high-level arranged steam turbine
WO2012008369A1 (en) Nuclear reactor containment structure and nuclear reactor operation method
CA3070834C (en) Method for establishing the natural circulation of liquid metal coolant of a fast neutron nuclear chain reactor
JP2004101492A (en) Natural circulation reactor and its starting method
WO2015089665A1 (en) Nuclear reactor shutdown system
JP5766414B2 (en) Reactor vessel structure and reactor operation method
JP2007232529A (en) Core melt cooling device, reactor containment vessel, and method of installing core melt cooling device
JPH06265665A (en) Natural circulation type boiling water reactor
JP2011099772A (en) Natural circulation boiling water reactor and method of starting the same
KR20140109164A (en) In vessel boron injection system
JP2009029658A (en) Single crystal pulling device and method
US8514998B2 (en) Induction heating stress improvement
JP6942583B2 (en) How to set the cooling temperature of the metal wall and how to cool the metal wall
JP4489046B2 (en) How to start a natural circulation furnace

Legal Events

Date Code Title Description
A621 Written request for application examination

Free format text: JAPANESE INTERMEDIATE CODE: A621

Effective date: 20140219

A131 Notification of reasons for refusal

Free format text: JAPANESE INTERMEDIATE CODE: A131

Effective date: 20141111

A521 Written amendment

Free format text: JAPANESE INTERMEDIATE CODE: A523

Effective date: 20150113

TRDD Decision of grant or rejection written
A01 Written decision to grant a patent or to grant a registration (utility model)

Free format text: JAPANESE INTERMEDIATE CODE: A01

Effective date: 20150602

A61 First payment of annual fees (during grant procedure)

Free format text: JAPANESE INTERMEDIATE CODE: A61

Effective date: 20150630

R151 Written notification of patent or utility model registration

Ref document number: 5773710

Country of ref document: JP

Free format text: JAPANESE INTERMEDIATE CODE: R151