JPH0224480B2 - - Google Patents
Info
- Publication number
- JPH0224480B2 JPH0224480B2 JP60057725A JP5772585A JPH0224480B2 JP H0224480 B2 JPH0224480 B2 JP H0224480B2 JP 60057725 A JP60057725 A JP 60057725A JP 5772585 A JP5772585 A JP 5772585A JP H0224480 B2 JPH0224480 B2 JP H0224480B2
- Authority
- JP
- Japan
- Prior art keywords
- coolant
- reactor vessel
- reactor
- wall
- temperature
- 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 - Lifetime
Links
Classifications
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Description
【発明の詳細な説明】
〔発明の技術分野〕
本発明は、高速増殖炉の炉壁保護装置に関す
る。DETAILED DESCRIPTION OF THE INVENTION [Technical Field of the Invention] The present invention relates to a reactor wall protection device for a fast breeder reactor.
一般に、高速増殖炉は液体ナトリウム等の液体
金属を冷却材として使用しており、原子炉容器内
にその冷却材を充填し、その自由液面上とルーフ
スラブとの間の上部空間に不活性ガスからなるカ
バーガスを充填して形成されている。
Generally, fast breeder reactors use liquid metal such as liquid sodium as a coolant, and the reactor vessel is filled with the coolant, and the upper space between the free liquid level and the roof slab is inert. It is formed by filling a cover gas made of gas.
一方、この液体金属からなる冷却材は熱伝達能
力が極めて大きいため、この冷却材に接している
原子炉容器の壁部の温度はこの冷却材の温度変化
に対して極めて速く追従する。しかしながら、原
子炉容器のうち冷却材の液面より上方の部分の壁
部の温度は、冷却材の温度変化には追従しない。 On the other hand, since the coolant made of liquid metal has an extremely high heat transfer ability, the temperature of the wall of the reactor vessel that is in contact with the coolant follows the temperature change of the coolant extremely quickly. However, the temperature of the wall portion of the reactor vessel above the liquid level of the coolant does not follow the temperature change of the coolant.
このため、原子炉の運転開始、停止の場合のよ
うに冷却材の温度が変化すると、原子炉容器のう
ち冷却材の液面下の部分と液面上の部分との間に
大きな温度差を生じてしまう。これに伴つて、こ
の冷却材の液面近傍の原子炉容器壁には大きな温
度勾配が生じ、過大な熱応力が発生し、原子炉容
器の健全性を損なう可能性があつた。 For this reason, when the temperature of the coolant changes, such as when starting or shutting down a nuclear reactor, a large temperature difference occurs between the part of the reactor vessel below the coolant liquid level and the part above the liquid level. It will happen. As a result, a large temperature gradient occurred on the reactor vessel wall near the coolant liquid level, generating excessive thermal stress and possibly impairing the integrity of the reactor vessel.
そこで、従来は原子炉容器の内側に断熱壁を添
設し、この断熱壁と原子炉容器内面との間に低温
の冷却材を流通させ、炉心の上面から流出した高
温の冷却材が原子炉容器に直接接触しないように
して、原子炉容器の健全性の確保を行なつてい
る。すなわち、原子炉容器内に設けられた循環ポ
ンプから炉心部に向けて送出される原子炉容器内
の低温な冷却材の一部を、前記断熱壁と原子炉容
器内面との間を流通せしめる冷却材流路を設けて
形成している。 Therefore, in the past, an insulating wall was attached to the inside of the reactor vessel, and low-temperature coolant was passed between this insulating wall and the inner surface of the reactor vessel, and the high-temperature coolant flowing out from the top of the reactor core was The integrity of the reactor vessel is ensured by preventing direct contact with the vessel. In other words, cooling is performed by circulating a portion of the low-temperature coolant inside the reactor vessel, which is sent toward the reactor core from a circulation pump provided inside the reactor vessel, between the heat insulating wall and the inner surface of the reactor vessel. It is formed by providing a material flow path.
しかし、この方式には循環ポンプがトリツプし
た時に断熱効果が低下する等の問題があつた。 However, this system had problems such as a reduction in the insulation effect when the circulation pump tripped.
そのほかに、原子炉容器内壁の液面近傍に、全
周に亘つてガス空間であるガスダムを形成する内
壁ライナを設けて、高温の冷却材と原子炉容器内
壁との直接接触を防止して、液面近傍の冷却材の
温度変化が直接原子炉容器に伝わるのを防止する
ことが行なわれている。 In addition, an inner wall liner is installed near the liquid level on the inner wall of the reactor vessel to form a gas dam, which is a gas space around the entire circumference, to prevent direct contact between the high-temperature coolant and the inner wall of the reactor vessel. Measures are being taken to prevent temperature changes in the coolant near the liquid surface from being transmitted directly to the reactor vessel.
しかしこの構造では、自由液面から蒸発した冷
却材のうち自由液面よりも温度の低い上部ガス空
間の原子炉容器内壁やルーフスラブの下面で凝縮
した冷却材が原子炉容器と円筒内壁ライナとの間
のガスダム内に流入して溜つた場合には断熱効果
が著しく低下する問題があつた。 However, in this structure, the coolant that evaporated from the free liquid surface and condensed on the inner wall of the reactor vessel in the upper gas space, which has a lower temperature than the free liquid level, and the lower surface of the roof slab, is transferred to the reactor vessel and the cylindrical inner wall liner. There was a problem that if the gas flowed into the gas dam and accumulated there, the insulation effect would be significantly reduced.
つまり、このガスダム内に溜つた冷却材の熱伝
導率は極めて高いので、この冷却材の保有する熱
が原子炉容器に伝達され、ガスダムを設けたこと
による断熱効果が損なわれる問題がある。 In other words, since the heat conductivity of the coolant accumulated in this gas dam is extremely high, there is a problem in that the heat held by this coolant is transferred to the reactor vessel, impairing the insulation effect achieved by providing the gas dam.
そのため従来は、このガスダム内に溜つた冷却
材を電磁ポンプにより汲出すことが提案されてい
た。しかしながら、この原子炉容器内は常に500
℃以上の冷却材で覆われており、しかも原子炉の
寿命が数10年と長く、この間常に確実に作動する
電磁ポンプを製作することは困難であつた。 Therefore, it has been proposed in the past to use an electromagnetic pump to pump out the coolant accumulated in the gas dam. However, inside this reactor vessel there are always 500
It was difficult to create an electromagnetic pump that would operate reliably during this long period of time, as the reactor was covered with coolant at a temperature of over 30°F and had a long lifespan of several 10 years.
このように従来の炉壁保護装置では熱遮蔽効果
が十分でなく原子炉容器の健全性を損なう不具合
や原子炉容器の構造が複雑となる問題点があつ
た。 As described above, conventional reactor wall protection devices do not have a sufficient heat shielding effect, resulting in problems that impair the integrity of the reactor vessel and complicate the structure of the reactor vessel.
以下第1図を参照してタンク型高速増殖炉の従
来例を説明する。 A conventional example of a tank-type fast breeder reactor will be described below with reference to FIG.
タンク型の原子炉容器1は、その外側を安全容
器2によつて保護されており、この安全容器2を
コンクリート製の格納容器3内に吊下することに
より支承されている。この原子炉容器1は、その
上端開口部をルーフスラブ4により閉塞されて密
閉容器とされ、内部に液体ナトリウム等の液体金
属からなる冷却材5が充填されており、その冷却
材5の自由液面5aとルーフスラブ4の下面との
間のカバーガス空間6内にアルゴンガスやヘリウ
ムガス等の不活性ガスからなるカバーガスが充填
されている。また、原子炉容器1の中央底部には
高圧プレナム7を介して炉心8が設けられてお
り、この炉心8の上方にはルーフスラブ4に大回
転プラグ9および小回転プラグ10を介して炉心
上部機構11が設けられている。 A tank-shaped reactor vessel 1 is protected on the outside by a safety vessel 2, and this safety vessel 2 is suspended and supported within a concrete containment vessel 3. This reactor vessel 1 has its upper end opening closed with a roof slab 4 to form a closed vessel, and the inside is filled with a coolant 5 made of liquid metal such as liquid sodium, and the free liquid of the coolant 5 is A cover gas space 6 between the surface 5a and the lower surface of the roof slab 4 is filled with a cover gas made of an inert gas such as argon gas or helium gas. Further, a reactor core 8 is provided at the center bottom of the reactor vessel 1 via a high-pressure plenum 7, and above the reactor core 8, a large-rotary plug 9 and a small-rotary plug 10 are connected to the roof slab 4 to provide an upper core mechanism. 11 are provided.
ルーフスラブ4には冷却材5を強制循環させる
循環ポンプ12と、一次冷却材と二次冷却材との
熱交換を行なわせる中間熱交換器13が垂下支持
されている。原子炉容器1内は中性子遮蔽体14
により上方の高温域14aと下方の低温域14b
とに隔離されている。 A circulation pump 12 for forcibly circulating the coolant 5 and an intermediate heat exchanger 13 for exchanging heat between the primary coolant and the secondary coolant are suspended and supported on the roof slab 4. Inside the reactor vessel 1 is a neutron shield 14
The upper high temperature area 14a and the lower low temperature area 14b are
It is isolated.
このタンク型高速増殖炉の運転は次のようにし
て行なわれる。 This tank type fast breeder reactor is operated as follows.
すなわち、循環ポンプ12を嫁動させて、入口
12aから低温域14b内の低温の冷却材を吸込
み、そして高圧配管15を通して冷却材を高圧プ
レナム7内に送給する。冷却材は高圧プレナム7
を経て炉心8内を上昇する間に昇温されて高温の
冷却材5となつて高温域14a内に流出する。こ
の高温域14a内の冷却材5は中間熱交換器13
内へ入口13aから流入し、その中間熱交換器1
3内を流れる2次冷却材と熱交換して冷却され、
出口13bから低温域14b内に流出され、再び
循環ポンプ12内へ流入する。 That is, the circulation pump 12 is operated to suck in low-temperature coolant in the low-temperature region 14b from the inlet 12a, and then feed the coolant into the high-pressure plenum 7 through the high-pressure piping 15. Coolant is in high pressure plenum 7
While rising in the core 8, the coolant is heated up and becomes a high-temperature coolant 5, which flows out into the high-temperature region 14a. The coolant 5 in this high temperature region 14a is transferred to the intermediate heat exchanger 13
into the intermediate heat exchanger 1 from the inlet 13a.
It is cooled by exchanging heat with the secondary coolant flowing inside 3,
It flows out from the outlet 13b into the low temperature region 14b and flows into the circulation pump 12 again.
そして、この運転の際に、カバーガス空間6内
にあるカバーガスは、冷却材がその温度変化に伴
つてその体積を膨縮された場合の原子炉容器1内
の内圧変化を吸収緩和させて、原子炉構成機器に
及ぼす悪影響の発生を防止する。更にルーフスラ
ブ4や回転プラグ9,10に取付けられている原
子炉上部機器の熱的トラブル発生を防止し、ま
た、冷却材5自身が直接接触または付着すること
によつて生じる断熱性低下等のトラブルの発生を
防止している。 During this operation, the cover gas in the cover gas space 6 absorbs and alleviates internal pressure changes in the reactor vessel 1 when the coolant expands and contracts in volume due to temperature changes. , prevent the occurrence of adverse effects on reactor components. Furthermore, it prevents thermal troubles in the upper reactor equipment attached to the roof slab 4 and rotating plugs 9 and 10, and also prevents thermal insulation from decreasing due to direct contact or adhesion of the coolant 5 itself. Preventing trouble from occurring.
原子炉容器1の内方に、冷却材5の自由液面5
aの上方からその下方部分までの間に断面L字形
で全周に渡る内壁ライナ16を固着して、原子炉
容器1と内壁ライナ16との間にカバーガス空間
6と連通するガスダム17が形成されている。 A free liquid level 5 of the coolant 5 is located inside the reactor vessel 1.
A gas dam 17 that communicates with the cover gas space 6 is formed between the reactor vessel 1 and the inner wall liner 16 by fixing an inner wall liner 16 with an L-shaped cross section and extending all the way between the upper part of the reactor vessel 1 and the lower part thereof. has been done.
高温域14a内の冷却材5は炉心8を通過する
間に約500℃以上に加熱され、その自由液面5a
からカバーガス空間6内へ蒸発する。一方、ルー
フスラブ4はその上面は常温に近く低温であり、
そのためカバーガス空間6に面する下面の温度も
冷却材5の温度より低い。そこで、カバーガス空
間6内へ蒸発した冷却材5の蒸気がルーフスラブ
4の下面に凝縮する。また、原子炉容器1の壁面
も安全容器2を通して外部へ熱が放散されて冷却
される。この原子炉容器1のカバーガス空間6内
にある内壁部分の温度は冷却材5の液温よりも低
く、そのため冷却材5の蒸気が凝縮する。この冷
却材5の凝縮は原子炉運転中または冷却材5が原
子炉容器1の内壁温度よりも高温に保たれている
間は常に進行する。 The coolant 5 in the high temperature region 14a is heated to approximately 500°C or more while passing through the core 8, and its free liquid level 5a
evaporates into the cover gas space 6. On the other hand, the top surface of the roof slab 4 is at a low temperature close to room temperature.
Therefore, the temperature of the lower surface facing the cover gas space 6 is also lower than the temperature of the coolant 5. There, the vapor of the coolant 5 evaporated into the cover gas space 6 condenses on the lower surface of the roof slab 4. Further, the wall surface of the reactor vessel 1 is also cooled by dissipating heat to the outside through the safety vessel 2. The temperature of the inner wall portion of the reactor vessel 1 in the cover gas space 6 is lower than the liquid temperature of the coolant 5, so that the vapor of the coolant 5 condenses. This condensation of the coolant 5 always proceeds during reactor operation or while the coolant 5 is maintained at a higher temperature than the inner wall temperature of the reactor vessel 1.
従つて、原子炉容器1の内壁温度が、冷却材5
である液体金属ナトリウムの凝固温度(約98℃)
以上に保たれていると、原子炉容器1の内壁面に
凝縮したナトリウムが常に液体状態に保たれるた
めに、液滴として流下し、ガスダム17の底部に
溜る。このガスダム17内に溜つた液体金属ナト
リウムの熱伝導率は極めて高いので、内壁ライナ
16内の冷却材5の保有する熱が原子炉容器1に
伝達されてしまう。 Therefore, the temperature of the inner wall of the reactor vessel 1 is lower than that of the coolant 5.
The solidification temperature of liquid metal sodium is (approximately 98℃)
If the temperature is maintained above, the sodium condensed on the inner wall surface of the reactor vessel 1 is always kept in a liquid state, so that it flows down as droplets and accumulates at the bottom of the gas dam 17. Since the thermal conductivity of the liquid metal sodium accumulated in the gas dam 17 is extremely high, the heat held by the coolant 5 in the inner wall liner 16 is transferred to the reactor vessel 1.
本発明はこれらの点に鑑みてなされたものであ
り、冷却材の液面近傍の原子炉容器内壁と高温冷
却材をガス空間を持つて区画する円筒壁構造の炉
壁保護装置において、高温冷却材から原子炉容器
への伝熱量を低減させて原子炉容器の熱応力を減
少させ、ガスダム内に移行する冷却材を抑制して
ガスダムの断熱効果を維持し炉容器の健全性を確
保できる信頼性の高い高速増殖炉の炉壁保護装置
を提供することにある。
The present invention has been made in view of these points, and is a reactor wall protection device having a cylindrical wall structure that partitions the reactor vessel inner wall near the liquid surface of the coolant and the high-temperature coolant with a gas space. Reliable technology that reduces the amount of heat transferred from the reactor material to the reactor vessel, reduces the thermal stress of the reactor vessel, suppresses the transfer of coolant into the gas dam, maintains the insulation effect of the gas dam, and ensures the integrity of the reactor vessel. An object of the present invention is to provide a reactor wall protection device for a fast breeder reactor with high durability.
本発明は上記目的を達成するために、原子炉容
器の内側に上方が開口し下方が閉塞された環状空
間を形成する円筒ライナを冷却材の液面上方から
液面下方にかけて設けるとともに、前記原子炉容
器の上部開口を閉塞するルーフスラブの外縁部と
前記原子炉容器の内壁との間に形成された間隙部
に前記原子炉容器の内壁に近接して上部円筒ライ
ナを設け、この上部円筒ライナの下端と前記円筒
ライナの上端とを上広がりの円すい台筒を介して
連結したものである。
In order to achieve the above object, the present invention provides a cylindrical liner that forms an annular space that is open at the top and closed at the bottom inside the reactor vessel, extending from above the liquid level of the coolant to below the liquid level, and An upper cylindrical liner is provided in close proximity to the inner wall of the reactor vessel in a gap formed between the outer edge of a roof slab that closes the upper opening of the reactor vessel and the inner wall of the reactor vessel, and the upper cylindrical liner The lower end of the cylindrical liner and the upper end of the cylindrical liner are connected via an upwardly widening conical cylinder.
本発明は冷却材が自由液面をもつて充填されて
いる如何なる原子炉容器にも適用されるものであ
り、特に冷却材温度が500℃以上で運転されるこ
との多いループ型やタンク型の高速増殖炉の原子
炉容器に適している。
The present invention is applicable to any type of reactor vessel filled with coolant with a free liquid level, and is particularly applicable to loop-type and tank-type reactor vessels that are often operated at coolant temperatures of 500°C or higher. Suitable for reactor vessels of fast breeder reactors.
第2図は本発明をタンク型高速増殖炉に適用し
た一実施例を示したものである。 FIG. 2 shows an embodiment in which the present invention is applied to a tank-type fast breeder reactor.
原子炉容器1内方に設けた円筒ライナ16上方
を、炉容器1と円筒ライナ16がなす環状空間面
積がなだらかに狭間になる方向で変化させる部
分、つまり円すい台筒18を設けて極力環状空間
面積が狭まくなつた部分から炉容器1と平行にル
ーフスラブ狭間下面まで設けた上部円筒ライナ1
9より形成されている。なお、環状空間面積が変
化し始めるライナ変化部20は曲面に形成されて
いる。高温域14a内の冷却材5は炉心8を通過
する間に500℃以上に加熱され、その自由液面5
aからカバーガス空間6へ蒸発する。一方ルーフ
スラブ4は、その上面は常温近く低温であり、そ
のためにカバーガス空間6に面する下面の温度も
冷却材5の温度より低い。そこでカバーガス空間
6内へ蒸発した冷却材5の蒸気がルーフスラブ4
の下面に凝縮する。また原子炉容器1の壁面も安
全容器を通して外部へ熱が放散されて冷却され
る。カバーガス空間6にある原子炉容器1の内壁
部分の温度は冷却材5の温度よりも低いため、第
1図に示す構造では、やはり蒸気が原子炉容器1
の内壁部分に凝縮する。この冷却材5の凝縮は原
子炉運転中または冷却材5が原子炉容器1の内壁
温度よりも高温に保たれている間は常に進行す
る。従つて原子炉容器1の内壁温度が冷却材5で
ある液体金属ナトリウムの凝固温度(約98℃)以
上に保たれていると、原子炉容器1の内壁面に凝
縮したナトリウムが常に液体状態に保たれる為に
液滴として流下し上部開口型の従来の環状空間
(ガスダム)17の底に溜まる。この環状空間1
7の底に溜つたナトリウムの熱伝導率は極めて高
いので円筒ライナ16の断熱効果が著しく低下す
る。そこで本実施例では上記で説明したように、
円筒ライナ16上方を、環状空間面積を狭まく
し、ルーフスラブ4狭間下面まで達する構造であ
るため冷却材5aから蒸発した蒸気が原子炉容器
1の内壁面に凝縮、流下することが少なくガスダ
ム17には断熱空間が維持されるため熱遮蔽効果
を増す。 A part where the area above the cylindrical liner 16 provided inside the reactor vessel 1 is changed so that the area of the annular space formed by the reactor vessel 1 and the cylindrical liner 16 is gradually narrowed, that is, a conical base cylinder 18 is provided to minimize the annular space. The upper cylindrical liner 1 is provided from the narrowed area to the lower surface of the roof slab gap in parallel with the furnace vessel 1.
It is formed from 9. Note that the liner changing portion 20 where the annular space area begins to change is formed into a curved surface. The coolant 5 in the high temperature region 14a is heated to 500°C or more while passing through the core 8, and its free liquid level 5
evaporates from a into the cover gas space 6. On the other hand, the upper surface of the roof slab 4 is at a low temperature close to room temperature, and therefore the temperature of the lower surface facing the cover gas space 6 is also lower than the temperature of the coolant 5. There, the vapor of the coolant 5 evaporated into the cover gas space 6 is transferred to the roof slab 4.
It condenses on the bottom surface of. Furthermore, the wall surface of the reactor vessel 1 is also cooled by dissipating heat to the outside through the safety vessel. Since the temperature of the inner wall of the reactor vessel 1 in the cover gas space 6 is lower than the temperature of the coolant 5, in the structure shown in FIG.
condenses on the inner wall of the This condensation of the coolant 5 always proceeds while the reactor is operating or while the coolant 5 is maintained at a higher temperature than the inner wall temperature of the reactor vessel 1. Therefore, if the temperature of the inner wall of the reactor vessel 1 is kept above the solidification temperature (approximately 98°C) of liquid metal sodium, which is the coolant 5, the sodium condensed on the inner wall of the reactor vessel 1 will always remain in a liquid state. In order to be retained, the gas flows down as droplets and accumulates at the bottom of a conventional annular space (gas dam) 17 with an open top. This annular space 1
Since the thermal conductivity of the sodium accumulated at the bottom of the cylindrical liner 16 is extremely high, the thermal insulation effect of the cylindrical liner 16 is significantly reduced. Therefore, in this embodiment, as explained above,
Since the annular space area above the cylindrical liner 16 is narrowed and reaches all the way to the lower surface of the roof slab 4, the steam evaporated from the coolant 5a is less likely to condense and flow down onto the inner wall surface of the reactor vessel 1, thereby reducing the gas dam 17. Since the insulation space is maintained, the heat shielding effect is increased.
環状空間面積をなだらかに変化させた円すい台
筒18は、環状空間面積を狭まくする事はもちろ
んのこと、カバーガス空間6側の壁面に凝縮した
冷却材が液滴として流下しやすい構造でなおかつ
軸方向の伸びを吸収する為のものである。又、環
状空間面積が変化し始めるライナ変化部20の曲
面部は、軸方向の伸びによる熱応力の低減を計る
ものである。 The conical base cylinder 18, whose annular space area changes gradually, not only narrows the annular space area, but also has a structure in which the coolant condensed on the wall surface on the side of the cover gas space 6 easily flows down as droplets. This is to absorb the elongation in the axial direction. Further, the curved surface portion of the liner changing portion 20 where the area of the annular space begins to change is intended to reduce thermal stress caused by elongation in the axial direction.
第3図は本発明の他の実施例で、上部円筒ライ
ナ19の冷却材側にルーフスラブ4下面より垂下
した熱遮蔽筒21を設けた例である。 FIG. 3 shows another embodiment of the present invention, in which a heat shielding tube 21 is provided on the coolant side of the upper cylindrical liner 19 and hangs down from the lower surface of the roof slab 4.
以上説明したように本発明に係る高速増殖炉の
炉壁保護装置は、原子炉容器の内側に上方が開口
し下方が閉塞された環状空間を形成する円筒ライ
ナを冷却材の液面上方から液面下方にかけて設け
るとともに、前記原子炉容器の上部開口を閉塞す
るルーフスラブの外縁部と前記原子炉容器の内壁
との間に形成された間隙部に前記原子炉容器の内
壁に近接して上部円筒ライナを設け、この上部円
筒ライナの下端と前記円筒ライナの上端とを上広
がりの円すい台筒を介して連結したので、原子炉
容器内のナトリウム蒸気が円筒ライナの内側に入
り込むのを防止することができ、これによりガス
ダムの底部にナトリウムが溜まるようなことがな
いので、ガスダムの断熱性能を維持することがで
きる。
As explained above, in the fast breeder reactor wall protection device according to the present invention, a cylindrical liner that forms an annular space that is open at the top and closed at the bottom inside the reactor vessel is heated from above the liquid level of the coolant. An upper cylindrical cylinder is provided near the inner wall of the reactor vessel in a gap formed between the outer edge of the roof slab that extends downward from the surface and closes the upper opening of the reactor vessel and the inner wall of the reactor vessel. A liner is provided, and the lower end of the upper cylindrical liner and the upper end of the cylindrical liner are connected via an upwardly expanding conical pedestal, thereby preventing sodium vapor within the reactor vessel from entering the inside of the cylindrical liner. This prevents sodium from accumulating at the bottom of the gas dam, allowing the gas dam to maintain its insulation performance.
第1図は従来の炉壁保護装置を備えた高速増殖
炉の縦断面図、第2図は本発明の一実施例である
炉壁保護装置の拡大断面図、第3図は本発明の他
の実施例における炉壁保護装置の部分拡大断面図
である。
1……原子炉容器、4……ルーフスラブ、5…
…冷却材、5a……冷却材液面、6……カバーガ
ス空間、16……円筒ライナ、17……ガスダ
ム、18……円すい台筒、19……上部円筒ライ
ナ、20……ライナ変化部、21……熱遮蔽筒。
FIG. 1 is a longitudinal sectional view of a fast breeder reactor equipped with a conventional reactor wall protection device, FIG. 2 is an enlarged sectional view of a reactor wall protection device that is an embodiment of the present invention, and FIG. FIG. 2 is a partially enlarged sectional view of the furnace wall protection device in the embodiment. 1... Reactor vessel, 4... Roof slab, 5...
... Coolant, 5a ... Coolant liquid level, 6 ... Cover gas space, 16 ... Cylindrical liner, 17 ... Gas dam, 18 ... Conical base cylinder, 19 ... Upper cylindrical liner, 20 ... Liner change part , 21... Heat shield cylinder.
Claims (1)
された環状空間を形成する円筒ライナを冷却材の
液面上方から液面下方にかけて設けるとともに、
前記原子炉容器の上部開口を閉塞するルーフスラ
ブの外縁部と前記原子炉容器の内壁との間に形成
された間隙部に前記原子炉容器の内壁に近接して
上部円筒ライナを設け、この上部円筒ライナの下
端と前記円筒ライナの上端とを上広がりの円すい
台筒を介して連結したことを特徴とする高速増殖
炉の炉壁保護装置。1. A cylindrical liner is provided inside the reactor vessel from above the coolant liquid level to below the liquid level, forming an annular space that is open at the top and closed at the bottom.
An upper cylindrical liner is provided close to the inner wall of the reactor vessel in a gap formed between the outer edge of the roof slab that closes the upper opening of the reactor vessel and the inner wall of the reactor vessel, and 1. A reactor wall protection device for a fast breeder reactor, characterized in that a lower end of a cylindrical liner and an upper end of the cylindrical liner are connected via an upwardly expanding conical pedestal.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP60057725A JPS61215989A (en) | 1985-03-22 | 1985-03-22 | Protective device for reactor wall of fast breeder reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP60057725A JPS61215989A (en) | 1985-03-22 | 1985-03-22 | Protective device for reactor wall of fast breeder reactor |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS61215989A JPS61215989A (en) | 1986-09-25 |
| JPH0224480B2 true JPH0224480B2 (en) | 1990-05-29 |
Family
ID=13063908
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP60057725A Granted JPS61215989A (en) | 1985-03-22 | 1985-03-22 | Protective device for reactor wall of fast breeder reactor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS61215989A (en) |
Family Cites Families (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS59168388A (en) * | 1983-03-16 | 1984-09-22 | 財団法人電力中央研究所 | Reactor container |
-
1985
- 1985-03-22 JP JP60057725A patent/JPS61215989A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS61215989A (en) | 1986-09-25 |
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