JPH03595B2 - - Google Patents
Info
- Publication number
- JPH03595B2 JPH03595B2 JP57173944A JP17394482A JPH03595B2 JP H03595 B2 JPH03595 B2 JP H03595B2 JP 57173944 A JP57173944 A JP 57173944A JP 17394482 A JP17394482 A JP 17394482A JP H03595 B2 JPH03595 B2 JP H03595B2
- Authority
- JP
- Japan
- Prior art keywords
- liquid sodium
- temperature
- temperature liquid
- inner cylinder
- low
- 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
- 239000007788 liquid Substances 0.000 claims description 63
- 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 claims description 58
- 229910052708 sodium Inorganic materials 0.000 claims description 57
- 239000011734 sodium Substances 0.000 claims description 57
- 230000007423 decrease Effects 0.000 description 6
- 230000000630 rising effect Effects 0.000 description 3
- 238000013517 stratification Methods 0.000 description 3
- 238000009792 diffusion process Methods 0.000 description 2
- 230000005484 gravity Effects 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 238000004088 simulation Methods 0.000 description 1
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 1
Classifications
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
- Secondary Cells (AREA)
- Image-Pickup Tubes, Image-Amplification Tubes, And Storage Tubes (AREA)
Description
【発明の詳細な説明】
高速増殖炉の炉内反応の緊急停止時には、急激
に原子炉内の液体ナトリウムの温度が低下し、且
つ炉内に流入する液体ナトリウムの流量は定格時
の100％から9.5％に減少する。炉内へ流入する液
体ナトリウムは炉内に残存する液体ナトリウムよ
り遥かに低温であり、流量が減少するので噴流に
よる炉内液体ナトリウムへの貫通力がなくなり、
流入低温液体ナトリウムは残存高温液体ナトリウ
ムと十分に混合されず、高温液体ナトリウムと低
温液体ナトリウムとが夫々層をなす。而して高温
液体ナトリウムは低温液体ナトリウムより比重が
小さいため、高温液体ナトリウムの層が低温液体
ナトリウムの層の上に浮くという成層化現象が発
生する。この際上部に高温液体ナトリウム、下部
に低温液体ナトリウムが層をなしているので原子
炉圧力容器の軸方向に大きな温度差が生じ、炉体
材料に大きな温度勾配が発生する。この温度勾配
が構造不連続部や、応力集中が考えられる個所に
発生すると、原子炉容器の構造式立上問題にな
る。[Detailed description of the invention] During an emergency shutdown of the reactor reaction in a fast breeder reactor, the temperature of liquid sodium inside the reactor drops rapidly, and the flow rate of liquid sodium flowing into the reactor decreases from 100% of the rated value. This decreases to 9.5%. The liquid sodium flowing into the furnace is much lower in temperature than the liquid sodium remaining in the furnace, and as the flow rate decreases, the jet no longer has the ability to penetrate the liquid sodium inside the furnace.
The inflow low temperature liquid sodium is not sufficiently mixed with the remaining high temperature liquid sodium, and the high temperature liquid sodium and the low temperature liquid sodium form separate layers. Since high-temperature liquid sodium has a lower specific gravity than low-temperature liquid sodium, a stratification phenomenon occurs in which a layer of high-temperature liquid sodium floats on a layer of low-temperature liquid sodium. At this time, since there is a layer of high-temperature liquid sodium in the upper part and low-temperature liquid sodium in the lower part, a large temperature difference occurs in the axial direction of the reactor pressure vessel, and a large temperature gradient occurs in the reactor body material. If this temperature gradient occurs at structural discontinuities or at locations where stress concentration is likely, it will cause problems in the structural formula start-up of the reactor vessel.
第１図は原子炉容器の概要を示し、胴１には液
体ナトリウム入口ノズル２、液体ナトリウム出口
ノズル３及び小口径ノズル４が取付けられ、更に
胴１の内部には液体ナトリウムを上方へ導くため
の内筒５が配設されている。内筒５の上端近傍に
はＹピース部１′と称する胴１の構造不連続部が
ある。 Figure 1 shows an outline of the reactor vessel.A liquid sodium inlet nozzle 2, a liquid sodium outlet nozzle 3, and a small-diameter nozzle 4 are attached to the shell 1. Furthermore, inside the shell 1, a liquid sodium inlet nozzle 2, a liquid sodium outlet nozzle 3, and a small diameter nozzle 4 are installed to guide liquid sodium upward. An inner cylinder 5 is provided. Near the upper end of the inner cylinder 5 there is a structural discontinuity of the cylinder 1 called the Y-piece part 1'.
而して原子炉容器内で上記成層化現象が発生す
ると、入口ノズル２から器内に入つた低温液体ナ
トリウムは、器内に残存する高温液体ナトリウム
と混合しないで夫々が層をなし、徐々に低温液体
ナトリウムと高温液体ナトリウムとの成層界面
（境界面）が円筒５の上端を越えた後は、低温液
体ナトリウムは胴１と内筒５との間の環状部に流
入するため、成層界面の上昇速度は急減する。 When the above-mentioned stratification phenomenon occurs in the reactor vessel, the low-temperature liquid sodium that entered the vessel from the inlet nozzle 2 does not mix with the high-temperature liquid sodium remaining in the vessel, but forms layers, and gradually After the stratified interface (boundary surface) between low-temperature liquid sodium and high-temperature liquid sodium exceeds the upper end of the cylinder 5, the low-temperature liquid sodium flows into the annular part between the shell 1 and the inner cylinder 5, so that the stratified interface The rate of rise sharply decreases.
このため成層界面は内筒５の上端近傍で長時間
停滞し、Ｙピース部１′とそれに近い小口径ノズ
ル４に軸方向の温度差が長時間生じるので、きび
しい応力が生じ、原子炉容器の構造成立上問題に
なる。第２図はこの状態を示すもので、低温液体
ナトリウムＬの層と高温液体ナトリウムＨの層と
の両者の間に拡散及び熱伝導によつて混合してで
きた中間温度の比較的薄い中間層Ｍを挟んで、低
温液体ナトリウムＬの液面が上昇するが、内筒５
の上端を越えると上昇速度が急減し、成層界面が
内筒５の上端近傍で長時間停滞すると、従来のも
のは内筒５の上端の高さがＹピース部１′の高さ
とほぼ同じであるので、Ｙピース部１′及びそれ
に近接した小口径ノズル４が温度差の大きい成層
界面に長時間接近し、前記各部に応力に関して厳
しい条件を与える温度分布を生じる。 For this reason, the stratified interface remains stagnant for a long time near the upper end of the inner cylinder 5, and a temperature difference in the axial direction occurs for a long time between the Y-piece portion 1' and the small-diameter nozzle 4 near it, resulting in severe stress and This poses a problem in terms of structure establishment. Figure 2 shows this state, where a relatively thin intermediate layer of intermediate temperature is formed between a layer of low-temperature liquid sodium L and a layer of high-temperature liquid sodium H, which are mixed by diffusion and heat conduction. The liquid level of low-temperature liquid sodium L rises across M, but the inner cylinder 5
When the upper end is exceeded, the rising speed suddenly decreases, and the stratified interface remains for a long time near the upper end of the inner cylinder 5. In the conventional case, the height of the upper end of the inner cylinder 5 is almost the same as the height of the Y-piece part 1'. Therefore, the Y-piece portion 1' and the small-diameter nozzle 4 adjacent thereto are in close proximity to the laminated interface with a large temperature difference for a long time, creating a temperature distribution that imposes severe stress conditions on each of the portions.
本発明はこのような問題点を解決するために提
案されたもので、原子炉容器の胴内に配設された
内筒における液体ナトリウムの溢流する上端部
を、前記胴におけるＹピース部等の構造不連続部
より上方に位置せしめ、前記内筒上端から溢流し
た低温液体ナトリウムが高温液体ナトリウムと混
合して中間温度となつた後、前記胴の構造不連続
部に達しうるように構成されたことを特徴とする
高速増殖炉の原子炉容器に係るものである。 The present invention was proposed in order to solve such problems, and the upper end of the inner cylinder disposed in the shell of the reactor vessel, through which liquid sodium overflows, is connected to the Y-piece part of the shell, etc. located above the structural discontinuity of the cylinder, and configured such that the low-temperature liquid sodium overflowing from the upper end of the inner cylinder can reach the structural discontinuity of the shell after mixing with high-temperature liquid sodium and reaching an intermediate temperature. The present invention relates to a reactor vessel for a fast breeder reactor characterized by:
本発明においては前記したように、原子炉容器
の胴内に配設された内筒を、その上端部が前記胴
におけるＹピース部等の構造不連続部より上方に
位置するように十分に高くして、内筒上端から溢
流した低温液体ナトリウムが高温液体ナトリウム
と混合して中間温度となつた後に、初めて前記胴
の構造不連続部に達しうるようにし、かくして低
温液体ナトリウムが高温液体ナトリウムと混合し
た後に、低温液体ナトリウムと高温液体ナトリウ
ムとの境界面である成層界面を、胴の構造不連続
部近傍に停滞させないようにし、同部に応力に関
して厳しい条件を与えるような温度分布を生起す
ることのないようにして原子炉容器の構造上の安
全を図るものである。 In the present invention, as described above, the inner cylinder disposed in the shell of the reactor vessel is set at a sufficiently high height so that the upper end thereof is located above a structural discontinuity such as a Y-piece part in the shell. The low temperature liquid sodium overflowing from the upper end of the inner cylinder mixes with the high temperature liquid sodium and reaches an intermediate temperature before reaching the structural discontinuity of the body, and thus the low temperature liquid sodium becomes the high temperature liquid sodium. After mixing with the liquid sodium, the stratified interface, which is the interface between the low-temperature liquid sodium and the high-temperature liquid sodium, is prevented from stagnation near the structural discontinuity of the shell, and a temperature distribution is created that imposes severe stress conditions on the part. This is to ensure the structural safety of the reactor vessel.
以下本発明を図示の実施例について説明する。 The present invention will be described below with reference to the illustrated embodiments.
第３図において、１１は原子炉容器の胴で、液
体ナトリウム入口ノズル１２、液体ナトリウム出
口ノズル１３、及び小口径ノズル１４が取付けら
れ、更に胴１１の内部には液体ナトリウムを上方
へ導くための内筒１５が配設され、同内筒１５に
はフローホール１６と称される多数の小径孔が穿
設されている。 In FIG. 3, reference numeral 11 denotes the shell of the reactor vessel, to which a liquid sodium inlet nozzle 12, a liquid sodium outlet nozzle 13, and a small-diameter nozzle 14 are attached. An inner cylinder 15 is provided, and a large number of small diameter holes called flow holes 16 are bored in the inner cylinder 15.
前記内筒１５は十分に高く構成され、その上端
部が胴１１におけるＹピース部１１′と称する構
造不連続部より上方に位置するように配設されて
いる。 The inner cylinder 15 has a sufficiently high structure and is arranged such that its upper end is located above a structural discontinuity in the body 11 called the Y-piece part 11'.
原子炉容器内に成層化現象が発生すると、入口
ノズル１２から入つた低温液体ナトリウムＬは器
内に残存する高温液体ナトリウムＨと混合しない
で夫々が層をなし、低温液体ナトリウムＬの液面
が上昇する。而して低温液体ナトリウムＬの液面
が内筒５の上端に達すると、低温液体ナトリウム
Ｌの一部は、器内で低温及び高温両液体ナトリウ
ムＨ，Ｌが拡散で混合して中間温度となつた比較
的薄い中間層Ｍとともに胴１１と内筒１５との間
に環状部に流入して、低温ナトリウムＬの液面の
上昇速度を急減する。 When a stratification phenomenon occurs in the reactor vessel, the low temperature liquid sodium L entering from the inlet nozzle 12 does not mix with the high temperature liquid sodium H remaining in the vessel and forms layers, causing the liquid level of the low temperature liquid sodium L to rise. Rise. When the liquid level of the low-temperature liquid sodium L reaches the upper end of the inner cylinder 5, a part of the low-temperature liquid sodium L mixes with the low-temperature and high-temperature liquid sodium H and L in the vessel by diffusion, and reaches an intermediate temperature. It flows into the annular portion between the shell 11 and the inner cylinder 15 together with the relatively thin middle layer M, which has softened, and rapidly reduces the rising speed of the liquid level of the low-temperature sodium L.
第４図はこの状態を示し、その後中間層Ｍは低
温液体ナトリウムＬの液面の上昇に伴なつて内筒
５の上端より押上げられ、前記内筒５と胴１との
間の環状部には低温液体ナトリウムＬだけが流入
する。 FIG. 4 shows this state, after which the intermediate layer M is pushed up from the upper end of the inner cylinder 5 as the liquid level of the low-temperature liquid sodium L rises, and the annular portion between the inner cylinder 5 and the shell 1 is pushed up. Only low temperature liquid sodium L flows into.
第５図はこの状態を示すもので、低温液体ナト
リウムＬが内筒の上端を越えて液面の上昇温度が
急減し、低温液体ナトリウムＬと高温液体ナトリ
ウムＨとの境界面が停滞したとき、Ｙピース部１
１′及び小口径ノズル部１４には温度差の激しい
成層界面に接触することがなく、応力に関して厳
しい条件を与えるような温度分布を生じることが
なく、原子炉容器の強度を保全するものである。 Figure 5 shows this state. When the low temperature liquid sodium L exceeds the upper end of the inner cylinder, the rising temperature of the liquid level suddenly decreases, and the interface between the low temperature liquid sodium L and the high temperature liquid sodium H becomes stagnant. Y piece part 1
1' and the small-diameter nozzle part 14 do not come into contact with the stratified interface where there is a large temperature difference, so there is no temperature distribution that would create severe stress conditions, and the strength of the reactor vessel is maintained. .
なお第６図及び第７図は水による模擬実験結果
を示すもので、第６図のＡ及び第７図のＢは夫々
従来の構造並に本発明の構造による原子炉容器内
の高さ方向における液体ナトリウムの温度分布曲
線を示すもので、この結果本発明による効果が大
であることが実証された。 Note that FIGS. 6 and 7 show the results of a simulation experiment using water, and A in FIG. 6 and B in FIG. This figure shows the temperature distribution curve of liquid sodium at
以上本発明を実施例について説明したが、本発
明は勿論このような実施例にだけ局限されるもの
ではなく、本発明の精神を逸脱しない範囲内で
種々の設計の改変を施しうるものである。 Although the present invention has been described above with reference to embodiments, the present invention is, of course, not limited to such embodiments, and can be modified in various ways without departing from the spirit of the present invention. .
第１図は従来の高速増殖炉の原子炉容器の縦断
面図、第２図はその炉内反応緊急停止時の状態を
示す縦断面図、第３図は本発明に係る高速増殖炉
の原子炉容器の一実施例を示す縦断面図、第４図
及び第５図は夫々その炉内反応緊急停止時の状態
を示す縦断面図、第６図及び第７図は夫々従来並
に本発明の原子炉容器内における液体ナトリウム
の炉内軸方向の温度分布状態の実験結果を示す図
表である。
１１……胴、１１′……Ｙピース部、１２……
入口ノズル、１３……出口ノズル、１４……小口
径ノズル、１５……内筒。
FIG. 1 is a longitudinal sectional view of the reactor vessel of a conventional fast breeder reactor, FIG. 2 is a longitudinal sectional view showing the state at the time of emergency shutdown of the reactor reaction, and FIG. 3 is a longitudinal sectional view of the reactor vessel of a conventional fast breeder reactor. FIGS. 4 and 5 are longitudinal sectional views showing one embodiment of the reactor vessel, and FIGS. 4 and 5 are longitudinal sectional views showing the state at the time of emergency shutdown of the reactor reaction, respectively. FIGS. 6 and 7 are the conventional and the present invention, respectively. 2 is a chart showing the experimental results of the temperature distribution state of liquid sodium in the reactor vessel in the axial direction of the reactor. 11... Trunk, 11'... Y piece part, 12...
Inlet nozzle, 13... Outlet nozzle, 14... Small diameter nozzle, 15... Inner cylinder.
Claims (1)
液体ナトリウムの溢流する上端部を前記胴におけ
るＹピース部等の構造不連続部より上方に位置せ
しめ、前記内筒上端から溢流した低温液体ナトリ
ウムが高温液体ナトリウムと混合して中間温度と
なつた後、前記胴の構造不連続部に達しうるよう
に構成されたことを特徴とする高速増殖炉の原子
炉容器。1. The upper end of the inner cylinder disposed in the reactor vessel, through which liquid sodium overflows, is positioned above the structural discontinuity such as the Y-piece part in the shell, and the liquid sodium overflows from the upper end of the inner cylinder. A nuclear reactor vessel for a fast breeder reactor, characterized in that the reactor vessel for a fast breeder reactor is configured such that the low temperature liquid sodium can reach the structural discontinuity of the shell after being mixed with the high temperature liquid sodium to reach an intermediate temperature.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP57173944A JPS5963593A (en) | 1982-10-05 | 1982-10-05 | Fast breeder container |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP57173944A JPS5963593A (en) | 1982-10-05 | 1982-10-05 | Fast breeder container |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS5963593A JPS5963593A (en) | 1984-04-11 |
| JPH03595B2 true JPH03595B2 (en) | 1991-01-08 |
Family
ID=15969955
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP57173944A Granted JPS5963593A (en) | 1982-10-05 | 1982-10-05 | Fast breeder container |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS5963593A (en) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US8073184B2 (en) | 2006-11-17 | 2011-12-06 | Pioneer Corporation | Speaker device |
Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5520451B2 (en) * | 1972-03-30 | 1980-06-03 | ||
| JPS567098A (en) * | 1979-06-29 | 1981-01-24 | Tokyo Shibaura Electric Co | Nuclear reactor cooling device |
Family Cites Families (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5747754Y2 (en) * | 1978-07-28 | 1982-10-20 |
-
1982
- 1982-10-05 JP JP57173944A patent/JPS5963593A/en active Granted
Patent Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5520451B2 (en) * | 1972-03-30 | 1980-06-03 | ||
| JPS567098A (en) * | 1979-06-29 | 1981-01-24 | Tokyo Shibaura Electric Co | Nuclear reactor cooling device |
Also Published As
| Publication number | Publication date |
|---|---|
| JPS5963593A (en) | 1984-04-11 |
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