JPS63284489A - Tank type fast breeder - Google Patents
Tank type fast breederInfo
- Publication number
- JPS63284489A JPS63284489A JP62118913A JP11891387A JPS63284489A JP S63284489 A JPS63284489 A JP S63284489A JP 62118913 A JP62118913 A JP 62118913A JP 11891387 A JP11891387 A JP 11891387A JP S63284489 A JPS63284489 A JP S63284489A
- Authority
- JP
- Japan
- Prior art keywords
- sodium
- reactor
- flows
- coolant
- hanging
- 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
Links
- 239000007788 liquid Substances 0.000 claims abstract description 24
- 239000002826 coolant Substances 0.000 claims abstract description 19
- 230000002093 peripheral effect Effects 0.000 claims abstract description 6
- 230000002238 attenuated effect Effects 0.000 claims abstract description 4
- 229910052708 sodium Inorganic materials 0.000 abstract description 57
- 239000011734 sodium Substances 0.000 abstract description 57
- 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 abstract description 56
- 230000001174 ascending effect Effects 0.000 abstract description 2
- 230000010355 oscillation Effects 0.000 abstract 1
- 239000000725 suspension Substances 0.000 description 20
- 239000000446 fuel Substances 0.000 description 6
- 238000005253 cladding Methods 0.000 description 2
- 238000005192 partition Methods 0.000 description 2
- 230000002159 abnormal effect Effects 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 230000020169 heat generation Effects 0.000 description 1
- 230000001771 impaired effect Effects 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
- Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)
Abstract
Description
【発明の詳細な説明】
〔発明の目的〕
（産業上の利用分野）
本発明はタンク型高速増殖炉に係り、特に炉心部をルー
フスラブに垂設される吊胴に保持したタンク型高速増殖
炉に関する。[Detailed Description of the Invention] [Object of the Invention] (Industrial Application Field) The present invention relates to a tank-type fast breeder reactor, and in particular to a tank-type fast breeder reactor in which the reactor core is held in a hanging shell suspended from a roof slab. Regarding furnaces.
（従来の技術）
一般に、タンク型高速増殖炉は′−次および二次冷却材
として液体金属ナトリウムを使用し、炉心部で加熱され
た一次ナトリウムを原子炉容器内に設置した中間熱交換
器に導いて二次ナトリウムと熱交換させ、冷却された一
次ナトリウムを再び炉心部へ送り込むようにしている。(Prior technology) Tank-type fast breeder reactors generally use liquid metallic sodium as the primary and secondary coolant, and the primary sodium heated in the reactor core is transferred to an intermediate heat exchanger installed in the reactor vessel. The cooled primary sodium is then fed back into the reactor core to exchange heat with the secondary sodium.
第４図は従来のタンク型高速増殖炉の概略構成を示すも
ので、原子炉容器１内に炉心部２が形成され、この炉心
部２は原子炉容器１上部開口を覆うルーＸスラブ３に垂
設される吊胴４に保持されている。原子炉容器１内は冷
却材としての一次ナトリウム６で満たされ、上記吊胴４
には炉心部２を通って昇流した一次ナトリウム６を流通
させる吊胴フローホール８が設けられている。炉心部２
は燃料集合体９、ブランケット燃料朶合体ｌＯおよび反
射体１１から構成されている。FIG. 4 shows a schematic configuration of a conventional tank-type fast breeder reactor, in which a reactor core part 2 is formed inside a reactor vessel 1, and this reactor core part 2 is attached to a Lux slab 3 that covers the upper opening of the reactor vessel 1. It is held by a suspension barrel 4 that is installed vertically. The inside of the reactor vessel 1 is filled with primary sodium 6 as a coolant, and the suspension shell 4 is filled with primary sodium 6 as a coolant.
A hanger flow hole 8 is provided in which the primary sodium 6 that has flowed up through the reactor core 2 flows. Reactor core 2
is composed of a fuel assembly 9, a blanket fuel assembly IO, and a reflector 11.
原子炉容器１内は隔壁１３によって上部プレナム１４と
下部プレナム１５に仕切られている。ルーフスラブ３の
中央部には炉心上部機構１６が貫通して設置され、周辺
部には複数基の中間熱交換器１７および複数基の循環ポ
ンプ１８がそれぞれ独立して設置されている。The inside of the reactor vessel 1 is partitioned into an upper plenum 14 and a lower plenum 15 by a partition wall 13 . A core upper mechanism 16 is installed through the center of the roof slab 3, and a plurality of intermediate heat exchangers 17 and a plurality of circulation pumps 18 are installed independently at the periphery.
循環ポンプ１８はモータ１９により駆動されるインペラ
２０を偉え、この循環ポンプ１８の吐出側は入口配管２
１を介して高圧プレナム２２に連結されている。The circulation pump 18 has an impeller 20 driven by a motor 19, and the discharge side of the circulation pump 18 is connected to the inlet pipe 2.
1 to a high pressure plenum 22.
中間熱交換器１７はシュラウド２５の中心部に同軸的に
二次ナトリウム出口管２６が設けられ、その二次ナトリ
ウム出口管２６内にさらに二次ナトリウム入口管２７が
設けられている。上記シュラウド２５と二次ナトリウム
出口管２６の間に設けられた上部管板２７および下部管
板２８に多数本の伝熱管２９が支持されている。In the intermediate heat exchanger 17, a secondary sodium outlet pipe 26 is provided coaxially in the center of the shroud 25, and a secondary sodium inlet pipe 27 is further provided within the secondary sodium outlet pipe 26. A large number of heat transfer tubes 29 are supported by an upper tube sheet 27 and a lower tube sheet 28 provided between the shroud 25 and the secondary sodium outlet pipe 26.
上記シュラウド２５にはｍへナトリウム６を吸い込むた
めの透孔３０が設けられ、二次ナトリウム出口管２６に
は二次ナトリウム３１を伝熱管２９の周囲へ出入りさせ
るための透孔３２．３３が設けられている。The shroud 25 is provided with a through hole 30 for sucking sodium 6 into m, and the secondary sodium outlet pipe 26 is provided with through holes 32 and 33 for allowing the secondary sodium 31 to enter and exit around the heat transfer tube 29. It is being
シュラウド２５の下端部にはｍへナトリウム６の出口ノ
ズル３４が設けられている。An outlet nozzle 34 for sodium 6 is provided at the lower end of the shroud 25.
上述のように構成したタンク型高速増殖炉において、下
部プレナム１５内のｍへナトリウム６は循環ポンプ１８
により入口配管２１を通り、高圧プレナム２２から炉心
部２へ送り込まれる。−次ナトリウム６は炉心部２を通
って昇流する際に炉心部２の熱により昇温する。In the tank-type fast breeder reactor configured as described above, the sodium 6 in the lower plenum 15 is pumped through the circulation pump 18.
It passes through the inlet pipe 21 and is fed into the reactor core 2 from the high-pressure plenum 22. - When sodium 6 flows up through the reactor core 2, its temperature increases due to the heat of the reactor core 2.
昇温したｍへナトリウム６は炉心部２から上部プレナム
１４へ流入し、吊胴フローホール８を通って中間熱交換
器１７内に流入する。中間熱交換器１７内へはシュラウ
ド２５の透孔３０から流入し、伝熱管２９を通る際に二
次ナトリウム３１と熱交換し、先に炉心部２で得た熱を
二次ナトリウム３１に与える。The heated sodium 6 flows from the reactor core 2 into the upper plenum 14, passes through the hanging shell flow hole 8, and flows into the intermediate heat exchanger 17. It flows into the intermediate heat exchanger 17 through the through hole 30 of the shroud 25 and exchanges heat with the secondary sodium 31 as it passes through the heat transfer tube 29, giving the secondary sodium 31 the heat previously obtained in the reactor core 2. .
熱交換後の温度が低下した一次ナトリウム３１は出口ノ
ズル３４を通って下部プレナム１５に流入し、再び循環
ポンプ１８によって炉心部２へ送り込まれる。The primary sodium 31 whose temperature has been reduced after heat exchange flows into the lower plenum 15 through the outlet nozzle 34 and is again sent into the reactor core 2 by the circulation pump 18.
一方、二次ナトリウム３１は二次ナトリウム入口管２７
から流入し、入口側の透孔３３から二次ナトリウム出口
管２６とシュラウド２５の間に流れ込み、伝熱管２９の
周囲を流れてｍへナトリウム６と熱交換を行なって昇温
する。昇温した二次ナトリウム３１は出口側の透孔３２
から二次ナトリウム出口管２６内を流れ、二次系熱交換
器（図示せず）に導がれ。On the other hand, the secondary sodium 31 is connected to the secondary sodium inlet pipe 27
It flows from the through hole 33 on the inlet side between the secondary sodium outlet pipe 26 and the shroud 25, flows around the heat exchanger tube 29, and exchanges heat with the sodium 6 to m, raising its temperature. The heated secondary sodium 31 passes through the through hole 32 on the outlet side.
The sodium flows through the secondary sodium outlet pipe 26 and is led to a secondary heat exchanger (not shown).
そこで放熱した後、二次系ポンプ（図示せず）で加圧さ
れ、再び二次ナトリウム入口管２７を通って中間熱交換
器１７内へ送り込まれる。After dissipating heat there, the sodium is pressurized by a secondary pump (not shown) and sent into the intermediate heat exchanger 17 through the secondary sodium inlet pipe 27 again.
（発明が解決しようとする問題点）
上述のように構成したタンク型高速増殖炉においては、
第５図に示すように、炉心部２を通って昇流したｍへナ
トリウム６は上部プレナム１４に流入し、大部分のｍへ
ナトリウム６は吊胴フローホール８を通って循環する。(Problems to be solved by the invention) In the tank-type fast breeder reactor configured as described above,
As shown in FIG. 5, the sodium 6 that has flowed up through the reactor core 2 flows into the upper plenum 14, and the sodium 6 that has flowed up through the reactor core 2 flows through the hanger flow hole 8.
しかし、一部のｍへナトリウム６は吊Ｍ４の内壁面に沿
って昇流し、−次ナトリウム６の自由液面に達して液面
揺動を引き起こす。特に吊３５１４のうち吊胴フローホ
ール８が設けられていない部分で、この液面揺動が大き
い。However, the sodium 6 in a part of m rises along the inner wall surface of the hanging M4 and reaches the free liquid level of the -order sodium 6, causing liquid level fluctuation. This liquid level fluctuation is particularly large in a portion of the suspension 3514 where the suspension body flow hole 8 is not provided.
この液面揺動により一次ナトリウム６液面上方を覆うカ
バーガス３６がｍへナトリウム６に巻き込まれ、このカ
バーガス３６を混入したｍへナトリウム６が炉心部２を
通って循環すると、高圧プレナム２２内にガス溜りが生
じる。このガス溜りは温度上昇により膨張するため炉心
部２の適正な流量配分ができず、原子炉の健全な運転が
困難になる。Due to this liquid level fluctuation, the cover gas 36 covering the upper part of the primary sodium 6 liquid level is drawn into the sodium 6 into m, and when the sodium 6 mixed with this cover gas 36 circulates through the reactor core 2, the high pressure plenum 22 Gas accumulates inside. This gas pool expands as the temperature rises, making it impossible to properly distribute the flow rate in the reactor core 2, making it difficult to operate the reactor in a healthy manner.
また、−次ナトリウム６に混入したガスが炉心燃料集合
体９に設置されている燃料ビン部（図示せず）に溜まる
と、ガス近傍の被覆管がｍへナトリウム６によって冷却
されず、異常発熱し、最悪の場合には被覆管が破裂する
。In addition, if the gas mixed in the -order sodium 6 accumulates in the fuel bottle (not shown) installed in the core fuel assembly 9, the cladding tube near the gas will not be cooled by the sodium 6, causing abnormal heat generation. However, in the worst case, the cladding pipe will burst.
また、−次ナトリウムの自由液面の揺動が大きいと液面
波動によって炉心上部機構１６、吊胴４等の炉内構造物
に対して加震源となり、炉内構造物が振動し、構造疲労
のため炉内構造物に亀裂（疲労破壊）が入るなどして炉
内構造物の健全性を損う恐れがある。In addition, if the free liquid level of -order sodium fluctuates greatly, the liquid level waves will act as a source of vibration for the reactor internal structures such as the upper core mechanism 16 and the hanging shell 4, causing the reactor internal structures to vibrate and cause structural fatigue. Therefore, there is a risk that the integrity of the reactor internals may be impaired due to cracks (fatigue fracture) in the reactor internals.
本発明は上記の事情を考慮してなされたもので、その目
的は一次ナトリウムの自由液面の揺動を防止することに
より゛、カバーガスの巻き込みを防止すると共に、炉心
上部機構、吊胴等の震動による構造疲労を防止すること
ができるタンク型高速増殖炉を提供することである。The present invention has been made in consideration of the above circumstances, and its purpose is to prevent the fluctuation of the free liquid level of primary sodium, prevent the entrainment of cover gas, and prevent the upper core mechanism, suspension structure, etc. An object of the present invention is to provide a tank-type fast breeder reactor that can prevent structural fatigue due to vibrations.
（問題点を解決するための手段） 本発明は、原子炉容器内の炉心部が収容され。 (Means for solving problems) In the present invention, a reactor core is housed within a reactor vessel.
この炉心部は原子炉容器の上部開口を覆うルーフスラブ
から垂設される吊胴に保持され、上記炉心部を昇流した
冷却材が上記吊胴に設けられた吊胴フローホールを通っ
て循環するように構成されたタンク型高速増殖炉におい
て、上記吊胴内周面に冷却材液面へ向って流れる冷却材
の垂直流速成分を減速させる案内板を設けたものである
。This reactor core is held in a suspension shell suspended from a roof slab that covers the upper opening of the reactor vessel, and the coolant that has flowed up in the reactor core is circulated through the suspension shell flow hole provided in the suspension shell. In the tank-type fast breeder reactor configured to do so, a guide plate is provided on the inner circumferential surface of the hanging barrel to reduce the vertical flow velocity component of the coolant flowing toward the coolant liquid surface.
（作 用）
炉心部を通って昇流した冷却材は、上部プレナムに流入
し、その一部が吊胴内周面に沿って昇流する。その冷却
材の流れは案内板により垂直流速成分が減衰され、冷却
材液面に液面揺動が生じない、また吊胴４の液面近くに
フローホールを設けることができるので熱過渡時の層化
流動を早期に消滅させることができる。(Function) The coolant that has flowed up through the reactor core flows into the upper plenum, and a portion of it flows up along the inner peripheral surface of the suspension barrel. The vertical flow velocity component of the coolant flow is attenuated by the guide plate, and no fluctuations occur in the coolant liquid level.Furthermore, a flow hole can be provided near the liquid level of the suspension shell 4, so that it can be used during thermal transients. Stratified flow can be quickly eliminated.
（実 施 例）
本発明に係るタンク型高速増殖炉の実施例を第１図ない
し第３図を用いて説明する。タンク型高速増殖炉の概略
構成については第１図に示し、第４図、第５図と同じ部
材には同符号を付して説明を省略する。(Embodiment) An embodiment of a tank-type fast breeder reactor according to the present invention will be described with reference to FIGS. 1 to 3. The schematic structure of the tank-type fast breeder reactor is shown in FIG. 1, and the same members as in FIGS. 4 and 5 are denoted by the same reference numerals and the explanation thereof will be omitted.
本発明の第１実施例は第１図に示すようになっており、
吊ＷＡ４内周面の一次ナトリウム６液面下に案内板とし
ての内周筒状の案内板４０を設けたものである。案内板
４０は一次ナトリウム６の自由液面近傍において、吊胴
４の内側に周方向に筒状に突出している。A first embodiment of the present invention is shown in FIG.
An inner cylindrical guide plate 40 as a guide plate is provided below the primary sodium 6 liquid level on the inner circumferential surface of the hanging WA4. The guide plate 40 protrudes in a cylindrical shape in the circumferential direction inside the hanging barrel 4 near the free liquid level of the primary sodium 6 .
このタンク型高速増殖炉においては、炉心部２から流出
した一次ナトリウム６は炉心上部機構１６下部で放射状
に向きを変え、吊胴４の内壁へ向かう、大部”分の一次
ナトリウム６は吊胴フローホール８から流出し、一部の
一次ナトリウム６が吊胴４の内周壁に沿って昇流する。In this tank-type fast breeder reactor, the primary sodium 6 flowing out from the reactor core section 2 changes its direction radially at the bottom of the upper core mechanism 16 and heads toward the inner wall of the suspension shell 4. A part of the primary sodium 6 flows out from the flow hole 8 and rises along the inner circumferential wall of the suspension barrel 4.
この−次ナトリウム６の上昇流は吊胴４の内周面に設け
られた周状の案内板４０と吊胴４のアニユラス部を通り
その大部分はフローホール８から吊胴外へ出る。一方、
オリフィス４１を通って吊胴４内へ戻る流れもできる。This ascending flow of secondary sodium 6 passes through a circumferential guide plate 40 provided on the inner circumferential surface of the suspension shell 4 and the annulus section of the suspension shell 4, and most of it exits from the flow hole 8 to the outside of the suspension shell. on the other hand,
A flow can also flow back into the suspension shell 4 through the orifice 41.
このオリフィス４１通過後は垂直流速成分が減衰され、
−次ナトリウム６は側方へ向きを変えて流れる。そのた
め、−次ナトリウム６の自由液面の液面揺動が防止され
る。またスクラム時等の低流量、低温冷却材が炉心から
出てくる場合でも吊胴４内の層化界面は吊胴フローホー
ル８の高さまで達するためミキシングボリュームが大き
くなり層化流動の早期消滅ができる
第２図は、第３図はタンク型高速増殖炉の別の実施例を
示すもので、吊胴４の内側にアニユラス部を形成するよ
うに設けた案内板４０のオリライス４２を炉心センタに
向けて斜めに開孔したことを特徴とする。こうすること
により吊胴４の内側では弱い旋回流を伴い、また液面に
向けて噴流が吹き上げることもないので吊胴内の液面揺
動は防止できる。After passing through this orifice 41, the vertical flow velocity component is attenuated,
- Sodium 6 turns to the side and flows. Therefore, the free liquid level of the -order sodium 6 is prevented from fluctuating. In addition, even when low-flow, low-temperature coolant comes out of the core during scram, the stratified interface inside the suspension shell 4 reaches the height of the suspension shell flow hole 8, so the mixing volume increases and the stratified flow disappears early. Figures 2 and 3 show another embodiment of a tank-type fast breeder reactor, in which an ori-rice 42 of a guide plate 40 provided to form an annulus portion inside the suspension shell 4 is placed at the core center. It is characterized by the holes being opened diagonally. By doing so, there is a weak swirling flow inside the hanging barrel 4, and no jet stream is blown up toward the liquid surface, so it is possible to prevent the liquid level inside the hanging barrel from fluctuating.
本発明に係るタンク型高速増殖炉は吊胴内周面に冷却材
液面へ向って流れる冷却材の垂直流速成分を減速させる
案内板を設けたもので、冷却材の液面揺動を防止するこ
とができる。The tank-type fast breeder reactor according to the present invention is equipped with a guide plate on the inner circumferential surface of the hanging barrel to decelerate the vertical flow velocity component of the coolant flowing toward the coolant liquid level, thereby preventing the coolant liquid level from swinging. can do.
したがって、カバーガスの巻き込みを防止するとともに
、炉心上部機構、吊胴等の震動による構造疲労を防止し
て原子炉の健全な運転を保持することができるという効
果がある。Therefore, it is possible to prevent entrainment of the cover gas, and also to prevent structural fatigue due to vibrations of the core upper mechanism, suspension shell, etc., thereby maintaining healthy operation of the nuclear reactor.
第１図は本発明に係るタンク型高速増殖炉の第１実施例
の吊胴部分の拡大図、第２図、第３図は本発明の他の実
施例を示すものである。第４図は従来のタンク型高速増
殖炉の概略構成図、第５図は上記従来例の吊胴部分の拡
大図である。
１・・・原子炉容器、 ２・・・炉心部、３・・・
ルーフスラブ、 ４・・・吊胴６・・・−次ナトリ
ウム、 ８・・・吊胴フローホール、９・・・燃料集
合体、
１０・・・ブランケット燃料集合体。
１１・・・反射体、１３・・・隔壁。
１４・・・上部プレナム、 １５・・・下部プレナム
、１６・・・炉心上部機構、 １７・・・中間熱交換
器、１８・・・再循環ポンプ、 ３６・・・カバーガ
ス、４０・・・案内板、 ４１．４２・・・
オリフィス。
第 １ 図
第 ２ 図
第 ３ 図
第 ４ 図
第５図FIG. 1 is an enlarged view of a hanging barrel portion of a first embodiment of a tank-type fast breeder reactor according to the present invention, and FIGS. 2 and 3 show other embodiments of the present invention. FIG. 4 is a schematic configuration diagram of a conventional tank-type fast breeder reactor, and FIG. 5 is an enlarged view of the hanging barrel portion of the conventional example. 1... Reactor vessel, 2... Reactor core, 3...
Roof slab, 4... Hanging shell 6... - secondary sodium, 8... Hanging barrel flow hole, 9... Fuel assembly, 10... Blanket fuel assembly. 11... Reflector, 13... Partition wall. 14... Upper plenum, 15... Lower plenum, 16... Core upper mechanism, 17... Intermediate heat exchanger, 18... Recirculation pump, 36... Cover gas, 40... Information board, 41.42...
Orifice. Figure 1 Figure 2 Figure 3 Figure 4 Figure 5
Claims (1)
子炉容器の上部開口を覆うルーフスラブから垂設される
吊胴に保持され、上記炉心部を昇流した冷却材が上記吊
胴に設けられた吊胴フローホールを通って循環するよう
に構成されたタンク型高速増殖炉において、上記吊胴内
周面に冷却材液面へ向って流れる冷却材の垂直流速成分
を減衰させる案内板を設けたことを特徴とするタンク型
高速増殖炉。1. A reactor core is housed in the reactor vessel, and this reactor core is held in a hanging shell suspended from a roof slab that covers the upper opening of the reactor vessel, and the coolant that has flowed up through the reactor core is carried by the hanging shell. In a tank-type fast breeder reactor configured to circulate through a hanging barrel flow hole provided in the shell, the vertical flow velocity component of the coolant flowing toward the coolant liquid level on the inner peripheral surface of the hanging barrel is attenuated. A tank-type fast breeder reactor characterized by the provision of a guide plate.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP62118913A JPS63284489A (en) | 1987-05-18 | 1987-05-18 | Tank type fast breeder |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP62118913A JPS63284489A (en) | 1987-05-18 | 1987-05-18 | Tank type fast breeder |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS63284489A true JPS63284489A (en) | 1988-11-21 |
Family
ID=14748272
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP62118913A Pending JPS63284489A (en) | 1987-05-18 | 1987-05-18 | Tank type fast breeder |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS63284489A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR2659781A1 (en) * | 1990-03-14 | 1991-09-20 | Commissariat Energie Atomique | Fast-neutron nuclear reactor equipped with a deflector (thrower, diffuser) at the output of the core |
-
1987
- 1987-05-18 JP JP62118913A patent/JPS63284489A/en active Pending
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR2659781A1 (en) * | 1990-03-14 | 1991-09-20 | Commissariat Energie Atomique | Fast-neutron nuclear reactor equipped with a deflector (thrower, diffuser) at the output of the core |
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