JPS6130237B2 - - Google Patents
Info
- Publication number
- JPS6130237B2 JPS6130237B2 JP56051510A JP5151081A JPS6130237B2 JP S6130237 B2 JPS6130237 B2 JP S6130237B2 JP 56051510 A JP56051510 A JP 56051510A JP 5151081 A JP5151081 A JP 5151081A JP S6130237 B2 JPS6130237 B2 JP S6130237B2
- Authority
- JP
- Japan
- Prior art keywords
- reactor
- vessel
- nuclear reactor
- guard
- closed space
- 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.)
- Expired
Links
- 239000002826 coolant Substances 0.000 claims description 15
- 238000001816 cooling Methods 0.000 claims description 14
- 239000000126 substance Substances 0.000 claims description 9
- 229910001338 liquidmetal Inorganic materials 0.000 claims description 4
- 239000011261 inert gas Substances 0.000 claims description 3
- 239000012768 molten material Substances 0.000 description 13
- 238000002844 melting Methods 0.000 description 5
- 239000007788 liquid Substances 0.000 description 4
- 230000008018 melting Effects 0.000 description 4
- 239000006185 dispersion Substances 0.000 description 2
- 238000005516 engineering process Methods 0.000 description 2
- 239000000155 melt Substances 0.000 description 2
- 229910001220 stainless steel Inorganic materials 0.000 description 2
- 239000010935 stainless steel Substances 0.000 description 2
- 229910018072 Al 2 O 3 Inorganic materials 0.000 description 1
- DGAQECJNVWCQMB-PUAWFVPOSA-M Ilexoside XXIX Chemical compound C[C@@H]1CC[C@@]2(CC[C@@]3(C(=CC[C@H]4[C@]3(CC[C@@H]5[C@@]4(CC[C@@H](C5(C)C)OS(=O)(=O)[O-])C)C)[C@@H]2[C@]1(C)O)C)C(=O)O[C@H]6[C@@H]([C@H]([C@@H]([C@H](O6)CO)O)O)O.[Na+] DGAQECJNVWCQMB-PUAWFVPOSA-M 0.000 description 1
- 229910004298 SiO 2 Inorganic materials 0.000 description 1
- 230000003213 activating effect Effects 0.000 description 1
- 239000011449 brick Substances 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 230000004927 fusion Effects 0.000 description 1
- 239000000383 hazardous chemical Substances 0.000 description 1
- 239000001307 helium Substances 0.000 description 1
- 229910052734 helium Inorganic materials 0.000 description 1
- SWQJXJOGLNCZEY-UHFFFAOYSA-N helium atom Chemical compound [He] SWQJXJOGLNCZEY-UHFFFAOYSA-N 0.000 description 1
- 229910001026 inconel Inorganic materials 0.000 description 1
- 238000007689 inspection Methods 0.000 description 1
- 238000012423 maintenance Methods 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 229910052751 metal Inorganic materials 0.000 description 1
- 239000002184 metal Substances 0.000 description 1
- 238000013508 migration Methods 0.000 description 1
- 230000005012 migration Effects 0.000 description 1
- 229910052708 sodium Inorganic materials 0.000 description 1
- 239000011734 sodium Substances 0.000 description 1
- 229910052715 tantalum Inorganic materials 0.000 description 1
- GUVRBAGPIYLISA-UHFFFAOYSA-N tantalum atom Chemical compound [Ta] GUVRBAGPIYLISA-UHFFFAOYSA-N 0.000 description 1
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 1
- 238000003466 welding Methods 0.000 description 1
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
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Description
【発明の詳細な説明】
本発明は、原子炉内の構造物の一部が溶融した
場合、溶融物を保持する装置を有する原子炉に関
するものである。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a nuclear reactor having a device for retaining molten material when a part of a structure within the reactor melts.
この溶融物質保持装置（一般にコアキヤツチヤ
ーと呼ばれているので以下単に「コアキヤツチヤ
ー」という。）を原子炉に配置するという技術思
想は従来から存在するものの、従来技術によれば
コアキヤツチヤーを設置する場所はすべて原子炉
容器内またはガードベツセルの外側のいずれかに
限られていた。 Although the technical concept of placing this molten material holding device (generally called a core catcher, hereinafter simply referred to as "core catcher") in a nuclear reactor has existed for a long time, according to the conventional technology, core catchers can be installed in all locations. It was confined either within the reactor vessel or outside the guard vessel.
すなわち、炉容器内に設けるコアキヤツチヤー
の場合は、ステンレス鋼、タンタル、インコネル
等で作られている多数の区分された受け皿からな
り、溶融物質は各受け皿にうすい厚さで分かれて
保持されるようになつており、これにより二次臨
界を阻止すると共に、受け皿周囲に存在する冷却
材の自然循環によつて冷却するようになつてい
る。しかし、このような原子炉の場合には、炉容
器内の構造が複雑になると共に、冷却能力に限度
があつて保持可能な溶融物質量が少ないという制
約があつた。 In other words, in the case of a core catcher installed in a furnace vessel, it consists of a number of divided trays made of stainless steel, tantalum, Inconel, etc., and the molten material is held in each tray in a thinly divided manner. This prevents secondary criticality and allows cooling by natural circulation of the coolant existing around the tray. However, in the case of such a nuclear reactor, the structure inside the reactor vessel is complicated, and there are limitations in that the cooling capacity is limited and the amount of molten material that can be held is small.
他方、ガードベツセル外に設けるコアキヤツチ
ヤーの場合は、UO2，ThO2，MgO，CaO，
Al2O3，SiO2、耐火レンガ等の高融点物質を用い
て受け皿を作り、溶融物質をを二次臨界をおこさ
ないようにうすい厚さで保持するように配慮し、
高融点物質の融解潜熱を利用して溶融物質の崩壊
熱の一部を吸収し、また溶融物質を稀釈すると共
に、適宜の冷却装置を用いて冷却するようになつ
ている。しかし、このような原子炉の場合には、
たとえ溶融物の移動を阻止しえたとしても、冷却
材の大量流出および有害な物質の原子炉容器室空
間への放出が起こりうる。 On the other hand, in the case of a core catcher installed outside the guard vessel, UO 2 , ThO 2 , MgO, CaO,
A saucer was made using a high-melting point material such as Al 2 O 3 , SiO 2 , and refractory brick, and care was taken to hold the molten material in a thin layer to prevent secondary criticality.
A part of the decay heat of the molten substance is absorbed using the latent heat of fusion of the high melting point substance, and the molten substance is diluted and cooled using an appropriate cooling device. However, in the case of such a reactor,
Even if the migration of melt could be prevented, large leaks of coolant and release of hazardous substances into the reactor vessel space can occur.
本発明の目的は、このような従来技術の制約を
解消し、有害な物質をガードベツセルから外部に
放出する可能性がないような原子炉を提供するこ
とにある。 An object of the present invention is to eliminate such limitations of the prior art and to provide a nuclear reactor in which there is no possibility of releasing harmful substances from the guard vessel to the outside.
すなわち本発明の原子炉は、原子炉容器とガー
ドベツセルとの間の空間を密閉空間となし、その
密閉空間内でしかも原子炉容器の直下位置にコア
キヤツチヤーを設け、さらにこのコアキヤツチヤ
ーを冷却するための冷却装置を有するものであ
る。コアキヤツチヤーを前記密閉空間内に設けた
点に本発明に特徴があり、そのことによつて上記
目的を達成できるものである。原子炉容器とガー
ドベツセルとの間の空間を密閉空間とするには、
単純には溶接によつて両者間を接合すればよいの
であるが、本発明者の一人が先に提案した「原子
炉」の発明（特願昭56−7336号）の技術を採用
し、マノメータ構造を利用した液封により密閉空
間を形成すれば炉容器とガードベツセルとの間に
信頼性の高い密閉空間を形成することができる。
以下、そのような密閉空間構造の場合の一例を図
示すると共にそれに基づいて詳細に説明する。な
お、本発明は、原子炉の形式には特に限定されず
に適用しうるものである。 That is, in the nuclear reactor of the present invention, the space between the reactor vessel and the guard vessel is a closed space, a core catcher is provided within the closed space and directly below the reactor vessel, and a core catcher is provided for cooling the core catcher. It has a cooling device. The present invention is characterized in that the core catcher is provided within the closed space, thereby achieving the above object. To make the space between the reactor vessel and the guard cell a sealed space,
Simply, it would be sufficient to join the two by welding, but by adopting the technology of the "nuclear reactor" invention proposed earlier by one of the present inventors (Japanese Patent Application No. 7336-1982), we have developed a manometer. If a sealed space is formed by a liquid seal utilizing the structure, a highly reliable sealed space can be formed between the furnace vessel and the guard vessel.
Hereinafter, an example of such a closed space structure will be illustrated and explained in detail based on it. Note that the present invention is applicable to any type of nuclear reactor without particular limitation.
炉心１を収容している炉容器２と、それを囲繞
しているガードベツセル３との間を、液体が満た
されているマノメータ構造体４を介して結合する
ことによつてそこに密閉空間５を形成する。ガー
ドベツセル３は、原子炉冷却材の入口配管部６及
び出口配管部７の近傍も覆うが、それらの延長部
にベロー８等を設けることによつて密閉される。
この密閉空間には通常ヘリウムなどの不活性ガス
を封入しておけばよいが、原子炉容器２内に存在
している冷却材と同じ冷却材、例えば液体金属冷
却型高速増殖炉の場合には液体ナトリウム等の液
体金属を封入しておくのが好ましい。 By connecting the reactor vessel 2 housing the reactor core 1 and the guard vessel 3 surrounding it via a liquid-filled manometer structure 4, a closed space 5 is created therein. form. The guard vessel 3 also covers the vicinity of the reactor coolant inlet piping section 6 and outlet piping section 7, which are sealed by providing bellows 8 or the like on their extensions.
This closed space can normally be filled with an inert gas such as helium, but if the same coolant as that present in the reactor vessel 2 is used, for example in the case of a liquid metal cooled fast breeder reactor, Preferably, a liquid metal such as liquid sodium is sealed.
本発明によれば、上記密閉空間５内でしかも原
子炉容器２の直下位置にコアキヤツチヤー９が設
けられる。このコアキヤツチヤー９としては従来
知られているものから適宜選択できるが、密閉空
間内に不活性ガスが封入されている場合は従来の
ガードベツセル外に設けるタイプのコアキヤツチ
ヤーが好ましく、密閉空間内に液体金属を封入す
る場合には従来の炉容器内に設けるタイプのコア
キヤツチヤーが好ましい。しかしながら、本発明
のコアキヤツチヤーとしては、ステンレス鋼のよ
うな金属製の受皿に前記したような高融点物質を
敷詰めたものがさらに好ましく使用できる。ま
た、コアキヤツチヤーには、図示していないが、
落下してくる溶融物質を分散して保持させるよう
にした分散装置を設けておくのが好ましい。この
種の分散装置としては、例えば、炉容器から溶融
物質が落下してくると予想される位置に突起伏物
を配設して、溶融物質を衝突させて分散させるも
のがある。 According to the present invention, a core catcher 9 is provided within the closed space 5 and directly below the reactor vessel 2. This core catcher 9 can be appropriately selected from conventionally known ones, but if the sealed space is filled with inert gas, a core catcher of the type installed outside the conventional guard vessel is preferred; A core catcher of the type installed within a conventional furnace vessel is preferred. However, as the core catcher of the present invention, it is more preferable to use a tray made of metal such as stainless steel and filled with the above-mentioned high melting point substance. In addition, although not shown in the figure, the core catcher has
It is preferable to provide a dispersion device for dispersing and retaining the falling molten material. As this type of dispersion device, for example, there is one in which a protrusion is disposed at a position where the molten material is expected to fall from the furnace vessel, and the molten material is dispersed by colliding with it.
更に本発明の原子炉では、コアキヤツチヤー９
を積極的に冷却するための冷却装置が設けられ
る。この冷却装置としては各種のものを採用で
き、必要によりその中から一つまたはそれ以上の
装置の組合わせを選択すればよい。冷却装置とし
てはガードベツセルの外側に冷却器を設けるもの
や、密閉空間内にある冷却材を冷却器を介して循
環させるものがある。各冷却器は空冷のものでも
液冷のものでもよいが、いずれにせよその駆動源
は通常の駆動源とは別の系統のものとしておくの
が肝要である。例えば図示されているように、冷
却器１０をガードベツセル３の外側底部でコアキ
ヤツチヤー９と対応する位置に設け、コアキヤツ
チヤー９を直接冷却するようにするのが最も現実
的であるが、ガードベツセル３の外側の任意の個
所に設けることができ、その場合はその付近の冷
却材を冷却して沈降する冷却材によつてコアキヤ
ツチヤーを直接冷却することになる。また図示さ
れているように、炉容器２に接続されている一次
冷却用の入口配管部６と出口配管部７に対応して
ガードベツセルの筒状部が形成されていて、内部
に冷却材が封入されている場合、ガードヘツセル
によつて形成される密閉空間５のこの入口配管部
分と出口配管部分とをポンプ１１を介して、また
は介することなく連結して循環路を形成し、その
循環路に冷却器１２ａ，１２ｂを設けることによ
り効率的な冷却を行なうことができる。なおその
場合、ポンプ１１や冷却器１２ａ，１２ｂを生体
遮蔽体１３の外側に設置すれば、保守点検も可能
となり好ましい。更に別の構成として、図示する
を省略するが、冷却材の吸引用配管と吐出用配管
とを原子炉容器内または密閉空間内に開口させ、
それらの配管を外部で冷却器を介して結合してル
ープを形成し、このループを作動せしめることに
よつて炉心を冷却することもできる。 Furthermore, in the nuclear reactor of the present invention, the core catcher 9
A cooling device is provided to actively cool the. Various types of cooling devices can be employed, and a combination of one or more of them may be selected as necessary. As a cooling device, there are those that provide a cooler outside the guard vessel, and those that circulate a coolant in a closed space through a cooler. Each cooler may be air-cooled or liquid-cooled, but in any case, it is important that its drive source be a separate system from the normal drive source. For example, as shown in the figure, it is most practical to provide a cooler 10 at the outer bottom of the guard vessel 3 at a position corresponding to the core catcher 9 so that the core catcher 9 is directly cooled. It can be provided at any location on the outside, in which case the core catcher will be directly cooled by the coolant that cools the coolant in the vicinity and settles. Further, as shown in the figure, a cylindrical part of the guard vessel is formed corresponding to an inlet piping part 6 and an outlet piping part 7 for primary cooling that are connected to the furnace vessel 2, and a coolant is contained inside. If it is enclosed, the inlet piping portion and the outlet piping portion of the sealed space 5 formed by the guard hex cell are connected with or without the pump 11 to form a circulation path, and the circulation path is By providing coolers 12a and 12b, efficient cooling can be achieved. In that case, it is preferable to install the pump 11 and the coolers 12a, 12b outside the biological shield 13, since maintenance and inspection can also be performed. As another configuration, although not shown, the coolant suction pipe and the coolant discharge pipe are opened into the reactor vessel or the closed space,
The core can also be cooled by connecting these pipes externally via a cooler to form a loop and activating this loop.
次に、本発明の原子炉について、原子炉内構造
物の一部が溶融した場合を想定して、そのときの
状態並びに動作について説明する。炉心１が何等
かの原因により溶融したとすると、それによつて
生じた高温の溶融物質は、炉容器２の底部を損傷
し、炉内の冷却材や溶融物質がガードベツセル３
で囲まれている密閉空間５内に流入する懸念があ
る。もし流入したときは溶融物質はそこに配置し
てあるコアキヤツチヤー９により受けとめられ、
そこに保持された状態で冷却器１０で冷却され
る。炉容器内から密閉空間５内に流入してそこを
満たした冷却材は必要により設けてある冷却器１
２ａ，１２ｂ等によつて冷却され、コアキヤツチ
ヤー９及びそこに保持された溶融物質を間接的に
冷却する。このようなコアキヤツチヤー９と各種
冷却器の動作により、溶融物質による損傷の拡大
はこの段階で停止する。そして、前述のように炉
容器２とガードベツセル３との間の空間５は密閉
状態であるため、冷却材や有害な物質はそこに閉
じ込められ一切外部に放出されることはない。ま
た、密閉空間５内に予め液体冷却材が封入されて
いる場合には、原子炉内構造物の溶融を検知した
とき、前記各種冷却装置を作動させれば、溶融物
が炉容器の底部を損傷する以前から、炉容器を外
面から冷却することができるので原子炉の損傷を
最小限にとどめることができる。 Next, regarding the nuclear reactor of the present invention, assuming a case where a part of the reactor internal structure melts, the state and operation at that time will be described. If the reactor core 1 were to melt for some reason, the resulting high-temperature molten material would damage the bottom of the reactor vessel 2, and the coolant and molten material inside the reactor would leak into the guard vessel 3.
There is a concern that the water may flow into the closed space 5 surrounded by. If the molten material flows in, it is received by the core catcher 9 located there,
While being held there, it is cooled by a cooler 10. The coolant that flows into the closed space 5 from inside the furnace vessel and fills the space is passed through a cooler 1 provided as necessary.
2a, 12b, etc., thereby indirectly cooling the core catcher 9 and the molten material held therein. Due to the operation of the core catcher 9 and various coolers, the expansion of damage caused by the molten substance is stopped at this stage. As described above, since the space 5 between the furnace vessel 2 and the guard cell 3 is sealed, the coolant and harmful substances are confined there and are never released to the outside. Furthermore, if a liquid coolant is sealed in the sealed space 5 in advance, when the melting of the reactor internals is detected, the various cooling devices described above can be activated, causing the molten material to reach the bottom of the reactor vessel. Since the reactor vessel can be cooled from the outside even before damage occurs, damage to the reactor can be kept to a minimum.
本発明は上記のように構成されているため、比
較的簡単な構造でありながら原子炉内構造物の溶
融に対して確実に対応でき、しかも有害な物質が
ガードベツセルの外部に漏洩する可能性がないと
いつた優れた効果を有し、利用価値は極めて高い
ものである。 Since the present invention is configured as described above, it can reliably cope with the melting of reactor internal structures even though it has a relatively simple structure, and it is possible to prevent harmful substances from leaking to the outside of the guard cell. It has excellent effects and has extremely high utility value.
図面は本発明の一実施例を示す説明図である。
１……炉心、２……炉容器、３……ガードベツ
セル、５……密閉空間、９……コアキヤツチヤ
ー、１０，１２ａ，１２ｂ……冷却器。
The drawings are explanatory diagrams showing one embodiment of the present invention. DESCRIPTION OF SYMBOLS 1... Reactor core, 2... Reactor vessel, 3... Guard vessel, 5... Closed space, 9... Core catcher, 10, 12a, 12b... Cooler.
Claims (1)
れるように炉容器を囲繞するガードベツセルと、
前記密閉空間内で原子炉容器の直下位置に設置さ
れた溶融物質の保持装置、および該保持装置の冷
却装置を有することを特徴とする原子炉。 ２ 冷却装置がガードベツセルの底部外側に設け
られている特許請求の範囲第１項記載の原子炉。 ３ 密閉空間内に不活性ガスが封入されている特
許請求の範囲第１項または第２項記載の原子炉。 ４ 原子炉が液体金属冷却材を用いた高速増殖炉
である特許請求の範囲第１項、第２項、または第
３項記載の原子炉。 ５ 密閉空間内に液体金属が封入されている特許
請求の範囲第４項記載の原子炉。[Claims] 1. A reactor vessel, a guard cell surrounding the reactor vessel so that a sealed space is formed outside the reactor vessel,
A nuclear reactor comprising: a molten substance holding device installed directly below a reactor vessel in the closed space; and a cooling device for the holding device. 2. The nuclear reactor according to claim 1, wherein the cooling device is provided outside the bottom of the guard vessel. 3. The nuclear reactor according to claim 1 or 2, wherein an inert gas is sealed in the closed space. 4. The nuclear reactor according to claim 1, 2, or 3, wherein the nuclear reactor is a fast breeder reactor using a liquid metal coolant. 5. The nuclear reactor according to claim 4, wherein liquid metal is sealed in a closed space.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP56051510A JPS57165790A (en) | 1981-04-06 | 1981-04-06 | Nuclear reactor with core catcher |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP56051510A JPS57165790A (en) | 1981-04-06 | 1981-04-06 | Nuclear reactor with core catcher |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS57165790A JPS57165790A (en) | 1982-10-12 |
| JPS6130237B2 true JPS6130237B2 (en) | 1986-07-11 |
Family
ID=12888992
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP56051510A Granted JPS57165790A (en) | 1981-04-06 | 1981-04-06 | Nuclear reactor with core catcher |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS57165790A (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS6381933A (en) * | 1986-09-26 | 1988-04-12 | Hitachi Electronics Eng Co Ltd | Formation of single thin-film |
| JPH05506543A (en) * | 1990-05-21 | 1993-09-22 | ハンプシャー インスツルメンツ，インコーポレイテッド | Mask tray and method for mounting a mask on a lithography apparatus |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS6089799A (en) * | 1983-10-24 | 1985-05-20 | 財団法人電力中央研究所 | Nuclear reactor |
-
1981
- 1981-04-06 JP JP56051510A patent/JPS57165790A/en active Granted
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS6381933A (en) * | 1986-09-26 | 1988-04-12 | Hitachi Electronics Eng Co Ltd | Formation of single thin-film |
| JPH05506543A (en) * | 1990-05-21 | 1993-09-22 | ハンプシャー インスツルメンツ，インコーポレイテッド | Mask tray and method for mounting a mask on a lithography apparatus |
Also Published As
| Publication number | Publication date |
|---|---|
| JPS57165790A (en) | 1982-10-12 |
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