JPH03277994A - Tank-shaped fast breeder - Google Patents
Tank-shaped fast breederInfo
- Publication number
- JPH03277994A JPH03277994A JP2076594A JP7659490A JPH03277994A JP H03277994 A JPH03277994 A JP H03277994A JP 2076594 A JP2076594 A JP 2076594A JP 7659490 A JP7659490 A JP 7659490A JP H03277994 A JPH03277994 A JP H03277994A
- Authority
- JP
- Japan
- Prior art keywords
- sodium
- core
- reactor vessel
- coolant
- heat exchanger
- 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 56
- 239000002826 coolant Substances 0.000 claims description 35
- 229910001338 liquidmetal Inorganic materials 0.000 claims description 8
- 229910052708 sodium Inorganic materials 0.000 abstract description 78
- 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 77
- 239000011734 sodium Substances 0.000 abstract description 77
- 239000000463 material Substances 0.000 abstract description 13
- 238000001816 cooling Methods 0.000 abstract description 8
- 239000007789 gas Substances 0.000 description 18
- 230000008646 thermal stress Effects 0.000 description 9
- 230000000712 assembly Effects 0.000 description 4
- 238000000429 assembly Methods 0.000 description 4
- 239000000446 fuel Substances 0.000 description 4
- 238000005192 partition Methods 0.000 description 4
- XKRFYHLGVUSROY-UHFFFAOYSA-N Argon Chemical compound [Ar] XKRFYHLGVUSROY-UHFFFAOYSA-N 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 230000001771 impaired effect Effects 0.000 description 2
- 238000002844 melting Methods 0.000 description 2
- 230000008018 melting Effects 0.000 description 2
- 229910052786 argon Inorganic materials 0.000 description 1
- 238000003384 imaging method Methods 0.000 description 1
- 230000000149 penetrating effect Effects 0.000 description 1
- 230000001105 regulatory effect Effects 0.000 description 1
- 230000003252 repetitive 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)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
Description
【発明の詳細な説明】 〔発明の目的〕 （産業上の利用分野） 本発明は原子炉容器内の冷却材液面の変動。[Detailed description of the invention] [Purpose of the invention] (Industrial application field) The present invention deals with fluctuations in the coolant liquid level within the reactor vessel.
波立ちを抑制し、ガス巻込みの防止、原子炉容器と炉内
機器に加わる撮画および熱応力を低減したタンク型高速
増殖炉に関する。This invention relates to a tank-type fast breeder reactor that suppresses ripples, prevents gas entrainment, and reduces imaging and thermal stress applied to the reactor vessel and internal equipment.
（従来の技術）
一般に高速増殖炉は大略的に原子炉容器の上部開口をル
ーフスラブで閉塞し、多数本の燃料集合体を植設した炉
心を原子炉容器下部の炉心支持機構によって原子炉容器
の中央に配置するとともに、この炉心の上部に炉心上部
機構をルーフスラブを貫通して設け、さらに炉心上部機
構の外周に循環ポンプと中間熱交換器とを複数ルーフス
ラブから垂下した配置構成となっている。また、高速増
殖炉の冷却材には液体金属ナトリウムが使用されており
、炉心は循環ポンプによって送り込まれた低温のナトリ
ウムで冷却される。炉心を冷却して高温になったナトリ
ウムは熱交換器で２次冷却材と熱交換し冷却されたのち
、再び循環ポンプによって炉心に送り込まれる。(Prior art) In general, in a fast breeder reactor, the upper opening of the reactor vessel is roughly closed with a roof slab, and the reactor, in which a large number of fuel assemblies are installed, is supported by a core support mechanism in the lower part of the reactor vessel. At the same time, a core upper mechanism is installed in the upper part of the core, penetrating the roof slab, and a plurality of circulation pumps and intermediate heat exchangers are arranged around the outer periphery of the core upper mechanism, hanging from the roof slab. ing. In addition, liquid metallic sodium is used as a coolant in fast breeder reactors, and the reactor core is cooled with low-temperature sodium pumped in by circulation pumps. The sodium, which has cooled to a high temperature after cooling the reactor core, is cooled by exchanging heat with the secondary coolant in a heat exchanger, and then pumped into the reactor core again by a circulation pump.
第６図および第７図に従来の実施例を示すタンク型高速
増殖炉の縦断面を示している。なお、第７図は第６図の
■−■矢視方向の横断面を示している。FIGS. 6 and 7 show longitudinal sections of tank-type fast breeder reactors showing conventional examples. Note that FIG. 7 shows a cross section taken in the direction of the arrows ■-■ in FIG. 6.
第６図および第７図において、原子炉容器ｌ内には冷却
材である液体ナトリウム２が収納され、原子炉容器１の
上端開口はルーフスラブ３によって閉塞されている。ル
ーフスラブ３にはこのルーフスラブ３を貫通して循環ポ
ンプ４と上部に二次ナトリウムの入口５ａおよび出口５
ｂを備えた熱交換器６とが挿入され、それぞれの下部は
隔壁７によって支持されている。In FIGS. 6 and 7, liquid sodium 2, which is a coolant, is stored in a reactor vessel 1, and the upper opening of the reactor vessel 1 is closed by a roof slab 3. The roof slab 3 is provided with a circulation pump 4 passing through the roof slab 3, and a secondary sodium inlet 5a and outlet 5 at the top.
A heat exchanger 6 with a heat exchanger 6 is inserted, the lower part of each of which is supported by a partition wall 7.
さらに、原子炉容器１の中央には多数本の燃料集合体を
植設した炉心８が炉心支持機構９によって配設されてい
る。この炉心８の上部にはルーフスラブ３を貫通して炉
心上部機構ｌＯが配置されている。Further, in the center of the reactor vessel 1, a reactor core 8 in which a large number of fuel assemblies are installed is arranged by a core support mechanism 9. A core upper mechanism IO is disposed in the upper part of the core 8, passing through the roof slab 3.
このような構成による冷却材の流れは＠環ポンプ４によ
って炉心８へ送り込まれた低温ナトリウム２ｂにより炉
心８を冷却する。炉心８を冷却して高温となった高温ナ
トリウム２ａは炉心上部機構ｌＯの下端に沿って矢印で
示したごとく斜め上方へ放射状に流れ、一部は熱交換器
６の入口窓１１から熱交換器６内に導かれ、熱交換器６
内に組込まれた図示していない多数本の伝熱管部を通っ
て二次ナトリウムと熱交換して低温となり、熱交換器６
の出口１２から流出する。出口１２から流出した低温ナ
トリウム２ｂは循環ポンプ４に導かれて再び炉心８へと
送り込まれる。The flow of coolant with this configuration cools the core 8 by the low-temperature sodium 2b sent into the core 8 by the ring pump 4. The high-temperature sodium 2a, which has become hot by cooling the core 8, flows radially upward obliquely as shown by the arrow along the lower end of the upper core mechanism 1O, and a part of the sodium flows from the inlet window 11 of the heat exchanger 6 to the heat exchanger. 6 into the heat exchanger 6
It exchanges heat with the secondary sodium through a large number of heat exchanger tubes (not shown) built into the heat exchanger 6, and the temperature becomes low.
It flows out from the outlet 12 of. The low temperature sodium 2b flowing out from the outlet 12 is guided by the circulation pump 4 and sent into the reactor core 8 again.
このように炉心８の熱は熱交換器６によって二次ナトリ
ウムへと伝えられるが、高温ナトリウム２ａの流れはか
なり複雑な流れ方をする。すなわち、炉心８を通過した
ナトリウム２ａは前述したように炉心上部機構ｌＯに沿
って矢印で示したごとく斜め上方へ放射状に流れ、一方
は熱交換器６の入口窓１１へ向かう流れとなり、他方は
原子炉容器ｌの壁面および循環ポンプ４の壁面にぶつか
り、主流は上昇流となる。この主流はナトリウム液面１
３の近傍では第６図および第７図に示すような複雑な表
面流れとなる。なお、循環ポンプ４の壁面に当った流れ
はその壁面に沿ってナトリウム液面１３に向う上昇流と
なる。In this way, the heat of the core 8 is transferred to the secondary sodium by the heat exchanger 6, but the flow of the high-temperature sodium 2a is quite complicated. That is, as described above, the sodium 2a that has passed through the core 8 flows diagonally upward radially as shown by the arrows along the upper core mechanism 1O, with one direction flowing toward the inlet window 11 of the heat exchanger 6, and the other flowing toward the inlet window 11 of the heat exchanger 6. The main flow hits the wall of the reactor vessel l and the wall of the circulation pump 4, and becomes an upward flow. This mainstream is sodium liquid level 1
In the vicinity of 3, the surface flow becomes complicated as shown in FIGS. 6 and 7. Note that the flow hitting the wall of the circulation pump 4 becomes an upward flow toward the sodium liquid level 13 along the wall.
（発明が解決しようとする課題）
しかして、その複雑な表面流れによってナトリウム液面
１３は乱されて変動し波立ちが発生する。(Problem to be Solved by the Invention) However, due to the complicated surface flow, the sodium liquid level 13 is disturbed and fluctuated, causing ripples.
特に第６図および第７図に示したような循環ポンプ４お
よび熱交換器６の配置が対称になっている場合ではナト
リウム液面１３の近傍を流れる高温ナトリウム２ａは原
子炉容器１の側から炉心上部機構ｌＯへ向う流れも対称
的な流れになる。In particular, when the circulation pump 4 and heat exchanger 6 are arranged symmetrically as shown in FIGS. The flow toward the upper core mechanism IO also becomes a symmetrical flow.
すなわち、第６図および第７図に示すように循環ポンプ
４と熱交換器６の間隙を通る高温ナトリウム２ａの流れ
は炉心上部機構１０にぶつかり左右に分かれようとする
流れになる。従って、この流れは隣接した循環ポンプ４
と熱交換器６を通ってきた流れとぶつかり合うことにな
り、この部分で大きな液面変動および旋回渦が発生する
。That is, as shown in FIGS. 6 and 7, the flow of high-temperature sodium 2a passing through the gap between the circulation pump 4 and the heat exchanger 6 hits the core upper mechanism 10 and becomes a flow that tends to split into left and right sides. Therefore, this flow is transferred to the adjacent circulation pump 4.
The liquid collides with the flow that has passed through the heat exchanger 6, and large liquid level fluctuations and swirling vortices occur in this area.
そのナトリウム液面１３の大きな乱れおよび旋回渦の発
生によりカバーガス１４を微細な気泡としてナトリウム
液面１３から流れに巻込む恐れがある。The large turbulence of the sodium liquid level 13 and the generation of swirling vortices may cause the cover gas 14 to be drawn into the flow from the sodium liquid level 13 in the form of fine bubbles.
仮に、流れの中にカバーガス１４の巻き込みを生じた場
合には、カバーガス１４は循環ポンプ４に導かれ、熱交
換器６を介して炉心８に送り込まれる。If the cover gas 14 is entrained in the flow, the cover gas 14 is guided to the circulation pump 4 and sent into the reactor core 8 via the heat exchanger 6.
炉心８へ送り込まれたカバーガス１４は炉心８によって
加熱され体積膨張し、炉心８とナトリウム２との接触を
一部妨げることになる。The cover gas 14 sent into the reactor core 8 is heated by the reactor core 8 and expands in volume, thereby partially preventing contact between the reactor core 8 and the sodium 2 .
そこで、カバーガス１４．例えばアルゴンがガスではナ
トリウムに比べ熱伝達率が１／１０００以下と非常に悪
いために、カバーガス１４が通過する部分に於いて炉心
８は過熱状態となり、炉心８が溶融して重大事故を起こ
す可能性がある。Therefore, cover gas 14. For example, when argon is a gas, the heat transfer coefficient is very poor, less than 1/1000 compared to sodium, so the core 8 becomes overheated in the area where the cover gas 14 passes, causing the core 8 to melt and cause a serious accident. there is a possibility.
また、ナトリウム液面１３は１８０℃程度のカバーガス
１４によって覆われている。ナトリウム液面１３に炉上
部機構、循環ポンプ４、熱交換器６および炉容器１など
炉内機器の壁面には、高温（５００℃以上）のナトリウ
ム２ａとカバーガス１４の温度差によって通常でも急激
な温度勾配が生じ、熱応力が発生している。前述したよ
うに高温ナトリウム２ａの流れによってナトリウム液面
１３が変動することになり、熱疲労によって構造材の健
全性を損なう課題がある。Further, the sodium liquid surface 13 is covered with a cover gas 14 having a temperature of about 180°C. Even under normal conditions, the sodium liquid level 13 is exposed to the walls of in-furnace equipment such as the upper furnace mechanism, circulation pump 4, heat exchanger 6, and furnace vessel 1 due to the temperature difference between the high-temperature (500°C or higher) sodium 2a and the cover gas 14. A temperature gradient occurs and thermal stress occurs. As described above, the sodium liquid level 13 fluctuates due to the flow of the high-temperature sodium 2a, which poses a problem of impairing the integrity of the structural material due to thermal fatigue.
以上のように上部プレナム内において、ナトリウム液面
１３を乱し、カバーガス１４を主流に巻き込み炉心８の
健全性を損なう課題がある。また、液面１３の変動によ
り発生する繰返し熱応力による熱疲労により構造材の健
全性を損なう課題もある。As described above, there is a problem in that the sodium liquid level 13 is disturbed in the upper plenum, the cover gas 14 is drawn into the mainstream, and the integrity of the core 8 is impaired. Further, there is also the problem that the soundness of the structural material is impaired due to thermal fatigue due to repeated thermal stress caused by fluctuations in the liquid level 13.
本発明は上記課題を解決するためになされたもので、上
部ブレナム内での液面変動、波立ち旋回渦を抑制し、カ
バーガスの巻き込みを防止することによって炉心の溶融
事故を未然に防止し、またナトリウム液面に接する炉内
機器に発生する繰返し熱応力を防止し、炉心および構造
材の健全性を確保して信頼性の大きいタンク型高速増殖
炉を提供することにある。The present invention has been made to solve the above problems, and it prevents core melting accidents by suppressing liquid level fluctuations and ripples and swirling vortices in the upper brenum, and preventing entrainment of cover gas. It is also an object of the present invention to provide a highly reliable tank-type fast breeder reactor that prevents repeated thermal stress from occurring in reactor equipment that comes into contact with the sodium liquid level and ensures the integrity of the reactor core and structural materials.
（課題を解決するための手段）
第１の発明は液体金属の冷却材を収納し液面を有する原
子炉容器の上部開口を閉塞するために配設されるルーフ
スラブと、前記原子炉容器内に設けられた炉心に冷却材
を送り込み該原子炉容器内の冷却材を循環するための前
記ルーフスラブを貫通して設けられた循環ポンプと、前
記冷却材と熱交換して前記原子炉容器外へ熱を取出す熱
交換器とを具備してなるタンク型高速増殖炉において、
前記循環ポンプと前記熱交換器との間に前記ルーフスラ
ブの上部から挿入し前記冷却材液面の下部まで達し、前
記液面近傍の流れを規制する流路偏向板を設けてなるこ
とを特徴とする。(Means for Solving the Problems) A first invention provides a roof slab disposed to close an upper opening of a reactor vessel which houses a liquid metal coolant and has a liquid surface, and a roof slab provided inside the reactor vessel. A circulation pump is installed through the roof slab to feed coolant into the reactor core installed in the reactor vessel and circulate the coolant inside the reactor vessel, and a circulation pump is installed through the roof slab to circulate the coolant inside the reactor vessel, and a circulation pump that exchanges heat with the coolant to circulate the coolant outside the reactor vessel. In a tank-type fast breeder reactor equipped with a heat exchanger for extracting heat from
A flow path deflection plate is provided between the circulation pump and the heat exchanger, inserted from the upper part of the roof slab, reaching the lower part of the coolant liquid level, and regulating the flow near the liquid level. shall be.
第２の発明は液体金属の冷却材を収納し液面を有する原
子炉容器の上部開口を閉塞するために配設されるルーフ
スラブと、前記原子炉容器内に設けられた炉心に冷却材
を送り込み該原子炉容器内の冷却材を循環するための前
記ルーフスラブを貫通して設けられた循環ポンプと、前
記冷却材と熱交換して前記原子炉容器外へ熱を取出す熱
交換器とを具備してなるタンク型高速増殖炉において、
前記循環ポンプの外周部に炉心から流出した冷却材の流
路を偏向、流速を抑制する流路偏向板を設けてなること
を特徴とする。The second invention includes a roof slab disposed to close an upper opening of a reactor vessel that houses a liquid metal coolant and has a liquid level, and a roof slab that is arranged to close an upper opening of a reactor vessel that houses a liquid metal coolant and that supplies a coolant to a core provided in the reactor vessel. a circulation pump provided through the roof slab for circulating coolant inside the reactor vessel; and a heat exchanger for exchanging heat with the coolant and extracting heat to the outside of the reactor vessel. In a tank-type fast breeder reactor equipped with
The circulation pump is characterized in that a flow path deflecting plate is provided on the outer circumferential portion of the circulation pump to deflect the flow path of the coolant flowing out from the core and suppress the flow velocity.
（作 用）
第１の発明において、液面近傍のナトリウムの流れは循
環ポンプと熱交換器の間隙を通り、流路偏向板により一
定方向に曲げられ、炉心上部機構に沿った流れが形成さ
れ、常に安定した旋回流れが炉心上部機構の囲りに形成
される。従って、向い合う流れおよびぶつかり合う流れ
がなくなり、ナトリウム液面の変動波立ち旋回渦の発生
を抑制できカバーガスの巻込みを防止できる。さらに、
ナトリウム液面も安定して液面変動および波立ちによる
構造材への繰返し熱応力を低減できる。(Function) In the first invention, the flow of sodium near the liquid surface passes through the gap between the circulation pump and the heat exchanger, is bent in a certain direction by the flow path deflection plate, and a flow is formed along the upper core mechanism. , a constantly stable swirling flow is formed around the upper core mechanism. Therefore, opposing flows and colliding flows are eliminated, and the generation of fluctuating undulations and swirling vortices in the sodium liquid level can be suppressed, and entrainment of the cover gas can be prevented. moreover,
The sodium liquid level is also stable, reducing repeated thermal stress on structural materials due to liquid level fluctuations and ripples.
第２の発明において、炉心から流出したナトリウムは炉
心上部機構の下端に沿って斜め上方に流れ、一方は熱交
換器の入口窓に向う流れとなり、他方は循環ポンプの外
壁へ向かい循環ポンプの外壁に沿って流れる。そして、
循環ポンプの外壁の周方向に設けられた流路偏向板によ
ってナトリウム液面に向う流れを偏向分散する。これに
よってナトリウム液面に向かう流速が抑制され、ナトリ
ウム液面の変動、波立ちが抑制でき、カバーガスの巻き
込みを防止できる。またナトリウム液面も安定して液面
変動および波立ちによる構造材への繰返し熱応力を低減
できる。In the second invention, the sodium flowing out from the core flows obliquely upward along the lower edge of the upper core mechanism, one flow toward the inlet window of the heat exchanger, and the other flow toward the outer wall of the circulation pump. flows along. and,
The flow toward the sodium liquid surface is deflected and dispersed by a flow path deflection plate provided in the circumferential direction of the outer wall of the circulation pump. This suppresses the flow velocity toward the sodium liquid level, suppresses fluctuations and ripples in the sodium liquid level, and prevents entrainment of the cover gas. In addition, the sodium liquid level is stable, reducing repeated thermal stress on structural materials due to liquid level fluctuations and ripples.
（実施例）
本発明の第１の実施例を第１図および第２図を参照して
説明する。(Example) A first example of the present invention will be described with reference to FIGS. 1 and 2.
本発明に係るタンク型高速増殖炉を示す第１図において
、原子炉容器１内に・は冷却材である液体ナトリウム２
が収納され、原子炉容器ｌの上端開口はルーフスラブ３
によって閉塞されている。ルーフスラブ３にはルーフス
ラブ３を貫通して循環ポンプ４と上部に二次ナトリウム
の入口５ａおよび出口５ｂを備えた熱交換器６とが挿入
され、それぞれの下部は隔壁７によって支持されている
。In FIG. 1 showing a tank-type fast breeder reactor according to the present invention, inside a reactor vessel 1, there is liquid sodium 2, which is a coolant.
is housed, and the upper opening of the reactor vessel l is the roof slab 3.
is blocked by. A circulation pump 4 and a heat exchanger 6 having an inlet 5a and an outlet 5b for secondary sodium at the upper part are inserted through the roof slab 3, and the lower part of each is supported by a partition wall 7. .
原子炉容器１の中央には多数本の燃料集合体を植設した
炉心８が炉心支持機構９によって配設されている。この
炉心８の上部にはルーフスラブ３を貫通して炉心上部機
構ｌＯが配置されている。A reactor core 8 in which a large number of fuel assemblies are installed is disposed in the center of the reactor vessel 1 by a core support mechanism 9. A core upper mechanism IO is disposed in the upper part of the core 8, passing through the roof slab 3.
このような構成による冷却材の流れは循環ポンプ４によ
って炉心８へ送り込まれた低温ナトリウム２ｂにより炉
心８を冷却する。炉心８を冷却して高温となった高温ナ
トリウム２ａは炉心上部機構ｌＯの下端に沿って矢印で
示したごとく斜め上方へ放射状に流れ、熱交換器６の入
口窓１１から熱交換器６内に導かれ、熱交換器６内に組
込まれた図示していない多数本の伝熱管部を通って二次
ナトリウムと熱交換して低湿となり、熱交換器６の出口
１２から流出する。出口１２から流出した低温ナトリウ
ム２ｂは循環ポンプ４に導かれて再び炉心８へと送り込
まれる。The flow of coolant with this configuration cools the core 8 by the low-temperature sodium 2b sent into the core 8 by the circulation pump 4. The high-temperature sodium 2a, which has become hot by cooling the core 8, flows radially upward obliquely as shown by the arrow along the lower end of the upper core mechanism IO, and flows into the heat exchanger 6 from the inlet window 11 of the heat exchanger 6. It passes through a large number of heat exchanger tubes (not shown) incorporated in the heat exchanger 6, exchanges heat with the secondary sodium, becomes low in humidity, and flows out from the outlet 12 of the heat exchanger 6. The low temperature sodium 2b flowing out from the outlet 12 is guided by the circulation pump 4 and sent into the reactor core 8 again.
循環ポンプ４と熱交換器６と炉心上部機構１０との間に
はルーフスラブ３の上部から挿入され、冷却材のナトリ
ウム液面１３の下部まで没入する流路偏向板１５が設け
られている。A flow path deflection plate 15 is provided between the circulation pump 4, the heat exchanger 6, and the upper core mechanism 10, which is inserted from the top of the roof slab 3 and immersed below the sodium liquid level 13 of the coolant.
しかして、ナトリウム液面１３の近傍で原子炉容器１の
側から循環ポンプ４と熱交換器６の間隙を通って、炉心
上部機構ｌＯへ向うナトリウムの流れは循環ポンプ４と
熱交換器６と炉心上部機構１０の間に設けられた流路偏
向板１５により第２図に示すように一定方向へ曲げられ
る。Therefore, the flow of sodium from the side of the reactor vessel 1 near the sodium liquid level 13 toward the upper core mechanism IO through the gap between the circulation pump 4 and the heat exchanger 6 is caused by the circulation pump 4 and the heat exchanger 6. The flow path deflecting plate 15 provided between the upper core mechanism 10 bends the flow path in a certain direction as shown in FIG.
従って、炉心上部機構ｌＯの囲りでは常に安定した旋回
流れが発生し、流れのぶつかりおよび向い合う流れに伴
なう不安定な流れがなくなり、ナトリウム液面１３の変
動、波立ち旋回渦の発生が抑制され、カバーガス１４の
巻込みを防止できる。さらにこれらの効果により構造材
に加わる繰返し熱応力を防止できる。Therefore, a stable swirling flow is always generated around the upper core mechanism 1O, and unstable flows due to collisions of flows and opposing flows are eliminated, and fluctuations in the sodium liquid level 13 and generation of rippled swirling vortices are prevented. This can prevent the cover gas 14 from being involved. Furthermore, these effects can prevent repeated thermal stress from being applied to the structural material.
つぎに本発明の第２の実施例を第３図、第４図および第
５図を参照して説明する。Next, a second embodiment of the present invention will be described with reference to FIGS. 3, 4, and 5.
本発明によるタンク型高速増殖炉を示す第３図において
原子炉容器内には冷却材である液体ナトリウム２が収納
され、原子炉容器１の上端開口はルーフスラブ３によっ
て閉塞されている。ルーフスラブ３には、ルーフスラブ
３を貫通して循環ポンプ４と上部に二次ナトリウムの入
口５ａおよび出口５ｂを備えた熱交換器６が挿入され、
それぞれの下部は隔壁７によって支持されている。In FIG. 3, which shows a tank-type fast breeder reactor according to the present invention, liquid sodium 2 as a coolant is housed in the reactor vessel, and the upper opening of the reactor vessel 1 is closed by a roof slab 3. A circulation pump 4 and a heat exchanger 6 having an inlet 5a and an outlet 5b for secondary sodium in the upper part are inserted into the roof slab 3 through the roof slab 3,
The lower part of each is supported by a partition wall 7.
さらに原子炉容器１の中央には、多数本の燃料集合体を
植設した炉心８が炉心支持機構９によって配設されてい
る。そして、この炉心８の上部には炉心上部機構１０が
配置されている。Further, in the center of the reactor vessel 1, a reactor core 8 in which a large number of fuel assemblies are installed is arranged by a core support mechanism 9. A core upper mechanism 10 is disposed above the core 8.
このような構成による冷却材の流れは、循環ポンプ４に
よって炉心８へ送り込まれた低温ナトリウム２ｂにより
炉心８を冷却する。炉心８を冷却して高温となった高温
ナトリウム２ａは炉心上部機構１０の下端に沿って矢印
で示したごとく斜め上方へ放射状に流れ一部は熱交換器
人口窓１１から熱交換器６内に導かれ、熱交換器６内に
組込まれた図示していない多数本の伝熱管部を通って二
次ナトリウムと熱交換して低温となり、熱交換器６の出
口１２から流出する。出口１２から流出した低温ナトリ
ウム２ｂは循環ポンプ４に導かれて再と炉心８へと送り
込まれる。＠環ポンプ４の外壁にはナトリウム液面１３
に向かうナトリウムの上昇流を抑制し、流路を変えるた
めの流路偏向板１７が設けられている。The flow of coolant with this configuration cools the core 8 by the low temperature sodium 2b sent into the core 8 by the circulation pump 4. The high-temperature sodium 2a, which has reached a high temperature by cooling the reactor core 8, flows diagonally upward radially along the lower end of the core upper mechanism 10 as shown by the arrow, and a portion of the sodium 2a flows into the heat exchanger 6 through the heat exchanger artificial window 11. It passes through a large number of heat exchanger tubes (not shown) incorporated in the heat exchanger 6, exchanges heat with the secondary sodium, becomes low temperature, and flows out from the outlet 12 of the heat exchanger 6. The low-temperature sodium 2b flowing out from the outlet 12 is guided to the circulation pump 4 and sent into the reactor core 8 again. @ Sodium liquid level 13 on the outer wall of the ring pump 4
A flow path deflecting plate 17 is provided to suppress the upward flow of sodium toward the flow path and change the flow path.
なお、この流路偏向板１７は複数段を軸方向に沿って設
けることもできる。Note that this flow path deflection plate 17 can also be provided in multiple stages along the axial direction.
すなわち、炉心８から循環ポンプ４の流れの状態を矢印
で示した第３図において、循環ポンプ４の外壁面でかつ
ナトリウム液面１３の直下に位置する部分に流路偏向板
１７が複数設けられている。この流路偏向板１７は、第
４図および第５図に示すように多数のフローホール１６
を有する多孔板で形成されている。That is, in FIG. 3, which shows the state of flow from the core 8 to the circulation pump 4 with arrows, a plurality of flow path deflection plates 17 are provided on the outer wall surface of the circulation pump 4 and located directly below the sodium liquid level 13. ing. This flow path deflecting plate 17 has a large number of flow holes 16 as shown in FIGS. 4 and 5.
It is made of a perforated plate with
このように構成された本発明によるタンク型高速増殖炉
の作用を説明する。炉心８から流出した高温のナトリウ
ム２ａは、炉心上部機構ｌＯの下端に沿って斜め上方に
流れ、一方は熱交換器６の入口窓１１に向う流れとなる
。他方は循環ポンプ４の外壁へ向い循環ポンプ４の外壁
に沿って流れ循環ポンプ４の外壁の周方向に設けられた
流路偏向板１７によってナトリウム液面１３に向う流れ
を偏向分散してナトリウム液面１３に向う流速が抑制さ
れ、ナトリウム液面１３の変動、波立ちが抑制できる。The operation of the tank-type fast breeder reactor according to the present invention configured as described above will be explained. The high-temperature sodium 2a flowing out from the core 8 flows obliquely upward along the lower end of the core upper mechanism IO, and one side flows toward the inlet window 11 of the heat exchanger 6. The other side flows toward the outer wall of the circulation pump 4 and flows along the outer wall of the circulation pump 4, and the flow toward the sodium liquid level 13 is deflected and dispersed by the flow path deflection plate 17 provided in the circumferential direction of the outer wall of the circulation pump 4, and the sodium liquid is The flow velocity toward the surface 13 is suppressed, and fluctuations and ripples in the sodium liquid level 13 can be suppressed.
したがって、高温ナトリウム２ａの流れは第３図の矢印
で示すごとく循環ポンプ４に沿ってナトリウム液面１３
に向う流れは流路偏向板１７によって抑制され、流れ方
向が偏向される。そのため、ナトリウム液面１３の変動
、波立ちが抑制でき、ナトリウム液面１３の乱れによっ
て生じるナトリウム液面１３からのカバーガス１４の巻
込みを防止できる。また、流路偏向板１７によってナト
リウム液面１３の変動。Therefore, the high temperature sodium 2a flows along the circulation pump 4 as shown by the arrow in FIG.
The flow toward is suppressed by the channel deflecting plate 17, and the flow direction is deflected. Therefore, fluctuations and ripples in the sodium liquid level 13 can be suppressed, and entrainment of the cover gas 14 from the sodium liquid level 13 caused by disturbances in the sodium liquid level 13 can be prevented. In addition, the sodium liquid level 13 fluctuates due to the channel deflection plate 17.
波立ちによって構造材に発生する繰返しの熱応力を防止
できる。It is possible to prevent repetitive thermal stress caused in structural materials due to ripples.
本発明によれば、流路偏向板を設けたことによって原子
炉容器内のナトリウム液面の乱れを抑制し、ナトリウム
液面からのカバーガスの巻き込みを防止し、炉心の溶融
事故を未然に防止し、炉心の健全性を確保できる。また
、ナトリウム液に接する構造材に発生する繰返しの熱応
力による熱疲労を低減し、構造材の健全性も確保できる
。According to the present invention, by providing a flow path deflection plate, turbulence of the sodium liquid level in the reactor vessel is suppressed, and entrainment of cover gas from the sodium liquid level is prevented, thereby preventing core melting accidents. This will ensure the integrity of the reactor core. In addition, thermal fatigue due to repeated thermal stress generated in structural materials that come into contact with sodium liquid can be reduced, and the integrity of the structural materials can be ensured.
第１図は本発明に係るタンク型高速増殖炉の第１の実施
例を示す縦断面図、第２図は第１図における■−■矢視
方向に沿って切断して示す横断面図、第３図は本発明の
第２の実施例を示す縦断面図、第４図は第３図における
偏向板を部分的に拡大して示す平面図、第５図は第４図
の縦断面図、第６図は従来のタンク型高速増殖炉を示す
縦断面図、第７図は第６図における■−■矢視方向に沿
って切断して示す横断面図である。
１・・・原子炉容器 ２・・・液体ナトリウ
ム２ａ・・・高温ナトリウム ２ｂ・・・低温ナ
トリウム３・・・ルーフスラブ ４・・・循環
ポンプ５ａ・・・二次ナトリウムの入口 ５ｂ・・・二
次ナトリウムの出口６・・・熱交換器 ７
・・・隔壁８・・・炉心 ９・・・炉
心支持機構ｌＯ・・・炉心上部機構 １３・・
・ナトリウム液面１４・・・カバーガス １
５．１７・・・流路偏向板１６・・・フローホール
竿
３
図
第
図
第
図
第
乙
図FIG. 1 is a longitudinal cross-sectional view showing a first embodiment of a tank-type fast breeder reactor according to the present invention, and FIG. 2 is a cross-sectional view taken along the direction of the ■-■ arrow in FIG. 1. FIG. 3 is a longitudinal sectional view showing a second embodiment of the present invention, FIG. 4 is a partially enlarged plan view of the deflection plate in FIG. 3, and FIG. 5 is a longitudinal sectional view of FIG. 4. , FIG. 6 is a longitudinal cross-sectional view showing a conventional tank-type fast breeder reactor, and FIG. 7 is a cross-sectional view taken along the direction of arrows -■ in FIG. 6. 1... Reactor vessel 2... Liquid sodium 2a... High temperature sodium 2b... Low temperature sodium 3... Roof slab 4... Circulation pump 5a... Secondary sodium inlet 5b... Secondary sodium outlet 6...heat exchanger 7
... Partition wall 8 ... Core 9 ... Core support mechanism lO ... Core upper mechanism 13 ...
・Sodium liquid level 14...Cover gas 1
5.17...Flow path deflection plate 16...Flow hole rod 3
Claims (2)
器の上部開口を閉塞するために配設されるルーフスラブ
と、前記原子炉容器内に設けられた炉心に冷却材を送り
込み該原子炉容器内の冷却材を循環するための前記ルー
フスラブを貫通して設けられた循環ポンプと、前記冷却
材と熱交換して前記原子炉容器外へ熱を取出す熱交換器
とを具備してなるタンク型高速増殖炉において、前記循
環ポンプと前記熱交換器との間に前記ルーフスラブの上
部から挿入し前記冷却材液面の下部まで達し、前記液面
近傍の流れを規制する流路偏向板を設けてなることを特
徴とするタンク型高速増殖炉。(1) A roof slab is installed to store liquid metal coolant and close the upper opening of the reactor vessel, which has a liquid level, and a roof slab is installed to close the upper opening of the reactor vessel, which houses liquid metal coolant and has a liquid surface. A circulation pump provided through the roof slab for circulating coolant in the reactor vessel, and a heat exchanger for exchanging heat with the coolant and extracting heat to the outside of the reactor vessel. In a tank-type fast breeder reactor comprising: a flow path inserted from the top of the roof slab between the circulation pump and the heat exchanger and reaching below the coolant liquid level to regulate the flow near the liquid level; A tank-type fast breeder reactor characterized by being equipped with a deflection plate.
器の上部開口を閉塞するために配設されるルーフスラブ
と、前記原子炉容器内に設けられた炉心に冷却材を送り
込み該原子炉容器内の冷却材を循環するための前記ルー
フスラブを貫通して設けられた循環ポンプと、前記冷却
材と熱交換して前記原子炉容器外へ熱を取出す熱交換器
とを具備してなるタンク型高速増殖炉において、前記循
環ポンプの外周部に炉心から流出した冷却材の流路を偏
向、流速を抑制する流路偏向板を設けてなることを特徴
とするタンク型高速増殖炉。(2) A roof slab is installed to store liquid metal coolant and close the upper opening of the reactor vessel, which has a liquid level, and a roof slab is installed to block the upper opening of the reactor vessel, which contains liquid metal coolant and has a liquid surface, and a roof slab that is installed to block the upper opening of the reactor vessel, which contains liquid metal coolant, and which supplies the coolant to the reactor core installed in the reactor vessel. A circulation pump provided through the roof slab for circulating coolant in the reactor vessel, and a heat exchanger for exchanging heat with the coolant and extracting heat to the outside of the reactor vessel. A tank-type fast breeder reactor comprising: a flow path deflecting plate for deflecting the flow path of the coolant flowing out from the core and suppressing the flow velocity on the outer periphery of the circulation pump; .
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP2076594A JPH03277994A (en) | 1990-03-28 | 1990-03-28 | Tank-shaped fast breeder |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP2076594A JPH03277994A (en) | 1990-03-28 | 1990-03-28 | Tank-shaped fast breeder |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH03277994A true JPH03277994A (en) | 1991-12-09 |
Family
ID=13609640
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP2076594A Pending JPH03277994A (en) | 1990-03-28 | 1990-03-28 | Tank-shaped fast breeder |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH03277994A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US20100177860A1 (en) * | 2009-01-14 | 2010-07-15 | Korea Atomic Energy Research Institute | Fully passive decay heat removal system for sodium-cooled fast reactors that utilizes partially immersed decay heat exchanger |
-
1990
- 1990-03-28 JP JP2076594A patent/JPH03277994A/en active Pending
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US20100177860A1 (en) * | 2009-01-14 | 2010-07-15 | Korea Atomic Energy Research Institute | Fully passive decay heat removal system for sodium-cooled fast reactors that utilizes partially immersed decay heat exchanger |
| US8670518B2 (en) * | 2009-01-14 | 2014-03-11 | Korea Atomic Energy Research Institute | Fully passive decay heat removal system for sodium-cooled fast reactors that utilizes partially immersed decay heat exchanger |
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