JPH05119175A - Fast reactor - Google Patents

Fast reactor

Info

Publication number
JPH05119175A
JPH05119175A JP3282600A JP28260091A JPH05119175A JP H05119175 A JPH05119175 A JP H05119175A JP 3282600 A JP3282600 A JP 3282600A JP 28260091 A JP28260091 A JP 28260091A JP H05119175 A JPH05119175 A JP H05119175A
Authority
JP
Japan
Prior art keywords
heat exchanger
sealing mechanism
intermediate heat
inner cylinder
bellows
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Pending
Application number
JP3282600A
Other languages
Japanese (ja)
Inventor
Kenji Ogura
健志 小倉
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Toshiba Corp
Original Assignee
Toshiba Corp
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Toshiba Corp filed Critical Toshiba Corp
Priority to JP3282600A priority Critical patent/JPH05119175A/en
Publication of JPH05119175A publication Critical patent/JPH05119175A/en
Pending legal-status Critical Current

Links

Classifications

    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Abstract

PURPOSE:To lover a leakage value of a coolant by arranging upper and lower sealing mechanisms provided at a joint between upper and lower parts of an intermediate heat exchanger and an inner cylinder and a decompression mechanism to relax conditions of intensity working on a seal bellows. CONSTITUTION:A lover seal bellows 18 is compressed by the weight of an intermediate heat exchanger 9 so that a lower plate 19 and a lower bellows base 20 are welded under pressure to form a lower sealing mechanism 21. At the same time, an upper sealing mechanism 22 is welded under pressure and a lower plate 23 and an upper bellows base 24 are welded under pressure to form an upper sealing mechanism 25. A pressure reducing mechanism 26 comprising a lower tiny hole 27 and an upper tiny hole 29 is added near the sealing mechanism 21. With an electromagnetic pump 7, a primary sodium 6 is pressurized by suction with the heat exchanger 9 to be introduced to the bottom of a reactor core 2 so that a pressure works on the outside of the lower seal bellows 18. The sodium 6 flows toward the upper tiny hole 29 from the lower tiny hole 27 to be returned to an outlet plenum of a heat exchanger tube 11 of the heat exchanger 9. The sodium 6 flowing into the upper part of the inner cylinder 4 is sealed up with the upper sealing mechanism 25 and returned to the suction side of the electromagnetic pump 7 thereby reducing a pressure difference working on the lover sealing mechanism 21 and the upper sealing mechanism 25 significantly.

Description

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

【0001】[0001]

【産業上の利用分野】本発明は、小型で長期間燃料交換
を必要としない高速炉に係り、特に取外し可能な中間熱
交換器を有する高速炉に関する。
BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a fast reactor which is compact and does not require refueling for a long period of time, and more particularly to a fast reactor having a removable intermediate heat exchanger.

【0002】[0002]

【従来の技術】従来の原子炉構造を図3、図4に示す。
なお図4は、図3のY−Y矢視断面図である。この原子
炉は、原子炉容器1の中心部に核燃料を装荷した炉心2
より構成される。この炉心2を囲むように反射体3が設
けられている。この反射体3は、原子炉容器1の上部に
設置した反射体駆動機構(図示せず)により上下移動さ
れる。またこの反射体3の外側には、内筒4及び遮蔽体
5が設置されている。この原子炉容器1内には、炉心2
を冷却する1次ナトリウム6が内包されている。原子炉
は、一部分の炉心2を包囲した反射体3を徐々に移動す
ることにより、この反射体に面した燃焼していない炉心
2に中性子を照射し少しずつ燃焼させ10年以上の長期間
にわたり燃焼し続けさすことができる。原子炉冷却材で
ある1次ナトリウム6は、電磁ポンプ7で吸引加圧する
ことにより、炉心2を冷却した後、崩壊熱除去コイル8
で冷却される。1次ナトリウム6は、中間熱交換器9で
更に冷却され、遮蔽体5内を通って、炉心2を支持する
支持構造物30に形成された流入孔31を介して炉心2の下
部に流入する。この1次ナトリウム6は、再び支持構造
物30に形成された流出孔32を通って炉心2に導かれる。
この中間熱交換器9は、1次ナトリウム6が流れる複数
の伝熱管11および2次冷却材10の流通部を形成するため
の外筒12及び内筒13より構成される。このため、2次冷
却材10は、冷却材入口33を通って、外筒12及び内筒13と
から成る流通部に導かれる。この2次冷却材10は、伝熱
管11の外側を冷却し、冷却材出口34より流出する。尚、
2次冷却材10は、冷却材シール部35によりシールされて
いる。またこの中間熱交換器9は、保守点検を考慮し
て、原子炉容器1から取出せる構造となっている。この
ため、内筒4の側面に固定したベローズ台座14の上に、
中間熱交換器9の下端に設置したシールベローズ15の下
板16を載置する。中間熱交換器9の重量により、シール
ベローズ15が圧縮され、シールベローズ14の下端に固定
した下板16とベローズ台座14が圧着する。この圧着によ
り、炉心2から流出する高温1次ナトリウム6と中間熱
交換器9から流出する低温ナトリウム6が封じられる。
2. Description of the Related Art A conventional nuclear reactor structure is shown in FIGS.
Note that FIG. 4 is a cross-sectional view taken along the line YY of FIG. This reactor has a core 2 in which a nuclear fuel is loaded in the center of a reactor vessel 1.
It is composed of A reflector 3 is provided so as to surround the reactor core 2. The reflector 3 is moved up and down by a reflector driving mechanism (not shown) installed on the upper part of the reactor vessel 1. Further, an inner cylinder 4 and a shield 5 are installed outside the reflector 3. In this reactor vessel 1, a core 2
The primary sodium 6 for cooling is contained. In the nuclear reactor, by gradually moving the reflector 3 that surrounds a part of the core 2, the unburned core 2 facing this reflector is irradiated with neutrons and burned little by little over a long period of 10 years or more. Can continue to burn. Primary sodium 6 which is a reactor coolant is sucked and pressurized by an electromagnetic pump 7 to cool the core 2, and then a decay heat removal coil 8
Is cooled by. The primary sodium 6 is further cooled by the intermediate heat exchanger 9, passes through the inside of the shield 5, and flows into the lower portion of the core 2 through the inflow holes 31 formed in the support structure 30 that supports the core 2. .. The primary sodium 6 is guided to the core 2 again through the outflow holes 32 formed in the support structure 30.
The intermediate heat exchanger 9 is composed of a plurality of heat transfer tubes 11 through which the primary sodium 6 flows and an outer cylinder 12 and an inner cylinder 13 for forming a circulation portion of the secondary coolant 10. For this reason, the secondary coolant 10 is guided through the coolant inlet 33 to the flow section including the outer cylinder 12 and the inner cylinder 13. The secondary coolant 10 cools the outside of the heat transfer tube 11 and flows out from the coolant outlet 34. still,
The secondary coolant 10 is sealed by the coolant seal portion 35. The intermediate heat exchanger 9 has a structure that can be taken out from the reactor vessel 1 in consideration of maintenance and inspection. Therefore, on the bellows pedestal 14 fixed to the side surface of the inner cylinder 4,
The lower plate 16 of the seal bellows 15 installed at the lower end of the intermediate heat exchanger 9 is placed. The seal bellows 15 is compressed by the weight of the intermediate heat exchanger 9, and the lower plate 16 fixed to the lower end of the seal bellows 14 and the bellows pedestal 14 are crimped. By this pressure bonding, the high temperature primary sodium 6 flowing out from the core 2 and the low temperature sodium 6 flowing out from the intermediate heat exchanger 9 are sealed.

【0003】[0003]

【発明が解決しようとする課題】中間熱交換器9の下部
に設けたシールベローズ15の下板16と内筒4の側面に設
けたベローズ台座14とが圧着することにより、1次ナト
リウム6が仕切られる。このため中間熱交換器9の下部
に固定された電磁ポンプ7の吐出側の高圧状態になった
1次ナトリウム6が直接シールベローズ15に接触する。
一方、シールベローズ15の内側には、炉心2からの低圧
状態の1次ナトリウム6が流入する。このためシールベ
ローズ15には高圧力差が作用することになり、シールベ
ローズ15には厳しい強度条件が課せられる。またこの高
圧力差がシールベローズ15の下板16とベローズ台座14と
の圧着によるシール部に作用する。このため、シール部
からの1次ナトリウム6の漏洩量が増加する。つまり高
温冷却材の中に、低温冷却材が混入するため、冷却材の
接液部に熱疲労が発生するおそれがある。
The lower plate 16 of the seal bellows 15 provided in the lower portion of the intermediate heat exchanger 9 and the bellows pedestal 14 provided on the side surface of the inner cylinder 4 are pressure-bonded to each other, so that the primary sodium 6 is removed. Partitioned. Therefore, the high pressure primary sodium 6 on the discharge side of the electromagnetic pump 7 fixed to the lower portion of the intermediate heat exchanger 9 directly contacts the seal bellows 15.
On the other hand, low pressure primary sodium 6 from the core 2 flows into the seal bellows 15. For this reason, a high pressure difference acts on the seal bellows 15, and the seal bellows 15 is subjected to severe strength conditions. Further, this high pressure difference acts on the seal portion by pressing the lower plate 16 of the seal bellows 15 and the bellows base 14 together. Therefore, the amount of primary sodium 6 leaking from the seal portion increases. That is, since the low temperature coolant is mixed in the high temperature coolant, thermal fatigue may occur in the liquid contact portion of the coolant.

【0004】本発明は上記の点を考慮してなされたもの
で、シールベローズに作用する強度条件を緩和させると
共に、シール部からの冷却材漏洩量を低減させ熱疲労を
大幅に軽減できる高速炉を提供することを目的としてい
る。
The present invention has been made in consideration of the above points, and is a fast reactor capable of relieving the strength condition acting on the seal bellows and reducing the amount of coolant leakage from the seal portion to greatly reduce thermal fatigue. Is intended to provide.

【0005】[0005]

【課題を解決するための手段】上記目的を達成するため
に、本発明においては、1次冷却材を収容する原子炉容
器と、この原子炉容器内にあって核燃料より構成される
炉心と、この炉心と同心円でその外側に配置される内筒
と、この内筒と炉心との間の環状空間を上下に移動する
反射体と、前記内筒と原子炉容器との間の環状空間に配
置される遮蔽体と、この遮蔽体の上方の環状空間に設置
され更に前記原子炉容器より取外し可能とする中間熱交
換器と、この中間熱交換器の上部に設置された崩壊熱除
去コイルと、前記中間熱交換器の下部に設置された電磁
ポンプと、前記中間熱交換器下部と内筒との接合部に設
けられた下部シール機構と、前記中間熱交換器上部と内
筒との接合部に設けられた上部シール機構と、前記中間
熱交換器の下部および前記下部シール機構に設けられた
減圧機構とから成ることを特徴とする高速炉を提供す
る。
In order to achieve the above object, in the present invention, a reactor vessel containing a primary coolant, a reactor core in the reactor vessel, which is composed of nuclear fuel, An inner cylinder arranged concentrically with the core and arranged on the outer side thereof, a reflector moving vertically in an annular space between the inner cylinder and the core, and arranged in an annular space between the inner cylinder and the reactor vessel. A shield, an intermediate heat exchanger installed in the annular space above the shield and removable from the reactor vessel, and a decay heat removal coil installed on top of the intermediate heat exchanger, An electromagnetic pump installed in the lower part of the intermediate heat exchanger, a lower sealing mechanism provided in a joint part between the lower part of the intermediate heat exchanger and the inner cylinder, and a joint part between the upper part of the intermediate heat exchanger and the inner cylinder. Upper sealing mechanism provided on the bottom of the intermediate heat exchanger. It consists of a pressure reducing mechanism provided in fine the lower seal mechanism provides a fast reactor according to claim.

【0006】[0006]

【作用】このように構成することにより、原子炉容器内
の内筒に中間熱交換器が設置され、この中間熱交換器の
重量により、中間熱交換器下部と内筒との接合部に設け
られた下部シール機構が形成される。また中間熱交換器
上部と内筒との接合部に設けられた上部シール機構が形
成される。更に下部シール機構近傍に設けられた減圧機
構が働くことになる。これにより、シールベローズに作
用する強度条件を緩和させると共に、シール部からの冷
却材漏洩量を低減させ熱疲労の大幅な軽減を図ることが
可能となる。
With this structure, the intermediate heat exchanger is installed in the inner cylinder of the reactor vessel, and the weight of the intermediate heat exchanger causes the intermediate heat exchanger to be installed at the joint between the lower part of the intermediate heat exchanger and the inner cylinder. A lower sealing mechanism is formed. Further, an upper sealing mechanism provided at the joint between the upper part of the intermediate heat exchanger and the inner cylinder is formed. Further, the pressure reducing mechanism provided near the lower sealing mechanism works. As a result, the strength condition that acts on the seal bellows can be relaxed, and the amount of coolant leaking from the seal portion can be reduced to significantly reduce thermal fatigue.

【0007】[0007]

【実施例】以下図面を参照して本発明実施例について説
明する。
Embodiments of the present invention will be described below with reference to the drawings.

【0008】図1は本発明による高速炉の一実施例を示
す縦断面図である。なお図1において、図3と同一部品
については同一符号を付し、その部分の構成の説明は省
略する。図2は、図1のX部の部分拡大図を示す。原子
炉容器1と内筒4との環状空間17に、原子炉容器1より
取外可能な中間熱交換器9が設置される。中間熱交換器
9の下部に固定された下部シールベローズ18の下板19
を、内筒4の側面に取付けられた下部ベローズ台座20上
に載置される。中間熱交換器9の重量により、下部シー
ルベローズ18が圧縮され、下部シールベローズ18の下端
に固定した下板19と下部ベローズ台座20が圧着されて下
部シール機構21を構成する。同時に中間熱交換器9の上
部に固定された上部シールベローズ22の下板23を、内筒
4の上端に取付けられた上部シールベローズ台座24上に
載置される。中間熱交換器9の重量により、上部シール
ベローズ22が圧縮され、上部シールベローズ22の下端に
固定した下板23と上部ベローズ台座24が圧着し上部シー
ル機構25を形成する。下部シール機構21には減圧機構26
が設けられている。この減圧機構26は、下部シールベロ
ーズ18の下端に設けられた下部小孔27から構成されてい
る。さらに、減圧機構として、中間熱交換器9の伝熱管
11の出口プレナム28の側面に上部小孔29が形成されてい
る。
FIG. 1 is a vertical sectional view showing an embodiment of a fast reactor according to the present invention. Note that, in FIG. 1, the same parts as those in FIG. FIG. 2 shows a partially enlarged view of the X portion of FIG. An intermediate heat exchanger 9 removable from the reactor vessel 1 is installed in an annular space 17 between the reactor vessel 1 and the inner cylinder 4. Lower plate 19 of the lower seal bellows 18 fixed to the lower part of the intermediate heat exchanger 9
Is placed on the lower bellows pedestal 20 attached to the side surface of the inner cylinder 4. The lower seal bellows 18 is compressed by the weight of the intermediate heat exchanger 9, and the lower plate 19 fixed to the lower end of the lower seal bellows 18 and the lower bellows pedestal 20 are crimped to form a lower seal mechanism 21. At the same time, the lower plate 23 of the upper seal bellows 22 fixed to the upper portion of the intermediate heat exchanger 9 is placed on the upper seal bellows pedestal 24 attached to the upper end of the inner cylinder 4. The upper seal bellows 22 is compressed by the weight of the intermediate heat exchanger 9, and the lower plate 23 fixed to the lower end of the upper seal bellows 22 and the upper bellows pedestal 24 are pressure-bonded to each other to form the upper seal mechanism 25. The lower seal mechanism 21 has a pressure reducing mechanism 26
Is provided. The pressure reducing mechanism 26 is composed of a lower small hole 27 provided at the lower end of the lower seal bellows 18. Further, as a pressure reducing mechanism, a heat transfer tube of the intermediate heat exchanger 9 is used.
An upper small hole 29 is formed on the side surface of the outlet plenum 28 of 11.

【0009】次にこのような構成からなる本実施例の作
用について説明する。中間熱交換器9の重量により、下
部シールベローズ18が圧縮され、下部シールベローズ18
の下板19と内筒4の側面に取付いた下部ベローズ台座20
が圧着されて下部シール機構21を形成する。同時に、上
部シールベローズ22が圧着されて、上部シールベローズ
22の下板23と内筒4の上部に取付いた上部ベローズ台座
24が圧着されて上部シール機構25を形成する。また下部
シール機構21の近傍に、下部小孔27と上部小孔29より成
る減圧機構26が付加される。電磁ポンプ7により、1次
ナトリウム6が中間熱交換器9より吸引加圧されて炉心
2の下部に導かれる。このため加圧された1次ナトリウ
ム6の圧力が下部シールベローズ18の外側に作用する。
ところで減圧機構26を形成する下部小孔27より上部小孔
29に向けて、高圧となった1次ナトリウム6が流れ、中
間熱交換器9の伝熱管11の出口プレナム28に戻される。
また上部シール機構25により、内筒4上部に流入した1
次ナトリウム6の流れが封じられる。1次ナトリウム6
の流れが減圧機構26により電磁ポンプ7の吸込側に戻さ
れるので、下部シール機構21及び上部シール機構25に作
用する圧力差が大幅に軽減される。
Next, the operation of this embodiment having such a configuration will be described. The lower seal bellows 18 is compressed by the weight of the intermediate heat exchanger 9,
Lower plate 19 and lower bellows pedestal 20 attached to the side of the inner cylinder 4
Are pressed to form the lower sealing mechanism 21. At the same time, the upper seal bellows 22 is crimped,
22 Lower plate 23 and upper bellows pedestal mounted on top of inner cylinder 4
24 is crimped to form the upper sealing mechanism 25. In addition, a pressure reducing mechanism 26 including a lower small hole 27 and an upper small hole 29 is added near the lower seal mechanism 21. The electromagnetic pump 7 sucks and pressurizes the primary sodium 6 from the intermediate heat exchanger 9 and guides it to the lower portion of the core 2. Therefore, the pressure of the pressurized primary sodium 6 acts on the outside of the lower seal bellows 18.
By the way, the small hole above the lower small hole 27 forming the pressure reducing mechanism 26
The high pressure primary sodium 6 flows toward 29 and is returned to the outlet plenum 28 of the heat transfer tube 11 of the intermediate heat exchanger 9.
In addition, by the upper seal mechanism 25, it flows into the upper part of the inner cylinder 1.
The next sodium 6 stream is blocked. Primary sodium 6
Since the flow of is returned to the suction side of the electromagnetic pump 7 by the pressure reducing mechanism 26, the pressure difference acting on the lower sealing mechanism 21 and the upper sealing mechanism 25 is greatly reduced.

【0010】このように本実施例によれば、下部シール
機構21及び上部シール機構25に作用する圧力差が軽減さ
れることにより、下部シールベローズ18及び上部シール
ベローズ22の強度条件が大幅に緩和される。また下部シ
ール機構21と上部シール機構25に作用する圧力差が低減
され、このシール部を通しての1次ナトリウム6の漏洩
量を低減させ、熱疲労の大幅な軽減を図ることができ
る。
As described above, according to this embodiment, since the pressure difference acting on the lower seal mechanism 21 and the upper seal mechanism 25 is reduced, the strength conditions of the lower seal bellows 18 and the upper seal bellows 22 are greatly relaxed. To be done. Further, the pressure difference acting on the lower seal mechanism 21 and the upper seal mechanism 25 is reduced, the leakage amount of the primary sodium 6 through the seal portion is reduced, and the thermal fatigue can be greatly reduced.

【0011】[0011]

【発明の効果】以上説明したように、本発明に係る高速
炉によれば、シールベローズに作用する強度条件を緩和
させると共に、シール部からの冷却材漏洩量を低減させ
熱疲労の大幅な軽減を図ることができる。
As described above, according to the fast reactor of the present invention, the strength condition acting on the seal bellows is relaxed, and the leakage amount of the coolant from the seal portion is reduced to greatly reduce the thermal fatigue. Can be planned.

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

【図1】本発明による高速炉の一実施例を示す縦断面
図。
FIG. 1 is a vertical sectional view showing an embodiment of a fast reactor according to the present invention.

【図2】図1のX部を拡大して示す部分拡大図。FIG. 2 is a partially enlarged view showing an X portion of FIG. 1 in an enlarged manner.

【図3】従来の高速炉を示す縦断面図。FIG. 3 is a vertical sectional view showing a conventional fast reactor.

【図4】図3のY−Y矢視断面図。FIG. 4 is a sectional view taken along the line YY of FIG.

【符号の説明】[Explanation of symbols]

1…原子炉容器 2…炉心 3…反射体 4…内筒 5…遮蔽体 6…1次ナトリウム 7…電磁ポンプ 9…中間熱交換器 21…下部シール機構 25…上部シール機構 26…減圧機構 27…下部小孔 29…上部小孔 DESCRIPTION OF SYMBOLS 1 ... Reactor vessel 2 ... Core 3 ... Reflector 4 ... Inner cylinder 5 ... Shield 6 ... Primary sodium 7 ... Electromagnetic pump 9 ... Intermediate heat exchanger 21 ... Lower sealing mechanism 25 ... Upper sealing mechanism 26 ... Decompression mechanism 27 … Lower hole 29… Upper hole

Claims (1)

【特許請求の範囲】[Claims] 【請求項1】 1次冷却材を収容する原子炉容器と、こ
の原子炉容器内にあって核燃料より構成される炉心と、
この炉心と同心円でその外側に配置される内筒と、この
内筒と炉心との間の環状空間を上下に移動する反射体
と、前記内筒と原子炉容器との間の環状空間に配置され
る遮蔽体と、この遮蔽体の上方の環状空間に設置され更
に前記原子炉容器より取外し可能とする中間熱交換器
と、この中間熱交換器の上部に設置された崩壊熱除去コ
イルと、前記中間熱交換器の下部に設置された電磁ポン
プと、前記中間熱交換器下部と内筒との接合部に設けら
れた下部シール機構と、前記中間熱交換器上部と内筒と
の接合部に設けられた上部シール機構と、前記中間熱交
換器の下部および前記下部シール機構に設けられた減圧
機構とから成ることを特徴とする高速炉。
1. A reactor vessel containing a primary coolant, and a reactor core in the reactor vessel, which is composed of nuclear fuel,
An inner cylinder arranged concentrically with the core and arranged on the outer side thereof, a reflector moving vertically in an annular space between the inner cylinder and the core, and arranged in an annular space between the inner cylinder and the reactor vessel. A shield, an intermediate heat exchanger installed in the annular space above the shield and removable from the reactor vessel, and a decay heat removal coil installed on top of the intermediate heat exchanger, An electromagnetic pump installed in the lower part of the intermediate heat exchanger, a lower sealing mechanism provided in a joint part between the lower part of the intermediate heat exchanger and the inner cylinder, and a joint part between the upper part of the intermediate heat exchanger and the inner cylinder. A fast reactor, comprising: an upper sealing mechanism provided in a lower part of the intermediate heat exchanger; and a pressure reducing mechanism provided in the lower sealing mechanism of the intermediate heat exchanger.
JP3282600A 1991-10-29 1991-10-29 Fast reactor Pending JPH05119175A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP3282600A JPH05119175A (en) 1991-10-29 1991-10-29 Fast reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP3282600A JPH05119175A (en) 1991-10-29 1991-10-29 Fast reactor

Publications (1)

Publication Number Publication Date
JPH05119175A true JPH05119175A (en) 1993-05-18

Family

ID=17654619

Family Applications (1)

Application Number Title Priority Date Filing Date
JP3282600A Pending JPH05119175A (en) 1991-10-29 1991-10-29 Fast reactor

Country Status (1)

Country Link
JP (1) JPH05119175A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2010126028A1 (en) 2009-04-27 2010-11-04 株式会社 東芝 Fast reactor
CN111128410A (en) * 2019-12-31 2020-05-08 中国核动力研究设计院 Heat pipe reactor system and energy conversion mode thereof

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2010126028A1 (en) 2009-04-27 2010-11-04 株式会社 東芝 Fast reactor
CN111128410A (en) * 2019-12-31 2020-05-08 中国核动力研究设计院 Heat pipe reactor system and energy conversion mode thereof

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