JP2507361Y2 - Vortex prevention device in the upper plenum of the reactor vessel - Google Patents
Vortex prevention device in the upper plenum of the reactor vesselInfo
- Publication number
- JP2507361Y2 JP2507361Y2 JP1990084517U JP8451790U JP2507361Y2 JP 2507361 Y2 JP2507361 Y2 JP 2507361Y2 JP 1990084517 U JP1990084517 U JP 1990084517U JP 8451790 U JP8451790 U JP 8451790U JP 2507361 Y2 JP2507361 Y2 JP 2507361Y2
- Authority
- JP
- Japan
- Prior art keywords
- reactor vessel
- upper plenum
- coolant pipe
- upward
- prevention device
- 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)
- Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)
Description
【考案の詳細な説明】 （産業上の利用分野） 本考案は，高速増殖炉の原子炉容器の上部プレナムに
おける渦防止装置に関するものである。DETAILED DESCRIPTION OF THE INVENTION (Industrial field of application) The present invention relates to a vortex preventive device in an upper plenum of a reactor vessel of a fast breeder reactor.
（従来の技術） 従来の高速増殖炉の原子炉容器を第3,4図により説明
すると，（01）が炉心，（02）が上部プレナム内構造
物，（03）が原子炉容器底板部，（04）が原子炉容器側
板部，（05）が原子炉容器（03）（04）の上部プレナム
に垂下状態に配設した冷却材配管で，炉心（01）を出た
高温冷却材を原子炉容器（03）（04）の上部プレナムを
経て冷却材配管（05）の底部に設けた呑口から中間熱交
換器（図示せず）へ流出させる。また原子炉容器（03）
（04）の上部プレナムに配設した冷却材配管（05）の呑
口部の没液深さを深くすることにより，同呑口部付近で
のガス巻込み渦（Ｂ）の発生を抑制するようにしてい
る。(Prior Art) A conventional reactor vessel for a fast breeder reactor will be described with reference to FIGS. 3 and 4. (01) is a core, (02) is an upper plenum structure, (03) is a reactor vessel bottom plate, (04) is a side wall of the reactor vessel, (05) is a coolant pipe arranged in a hanging state in the upper plenum of the reactor vessel (03) (04), and the high temperature coolant that has exited the core (01) is atomized. It flows out through the upper plenum of the furnace vessel (03) (04) to the intermediate heat exchanger (not shown) from the dowel provided at the bottom of the coolant pipe (05). Also reactor vessel (03)
By increasing the submerged depth of the mouth of the coolant pipe (05) arranged in the upper plenum of (04), the generation of gas entrainment vortex (B) near the mouth is suppressed. ing.
（考案が解決しようとする課題） 前記第3,4図に示す従来の高速増殖炉では，原子炉容
器（03）（04）の上部プレナムに配設した冷却材配管
（05）の呑口部の没液深さを深くすることにより，同呑
口部付近でのガス巻込み渦（Ｂ）の発生を抑制している
ので，冷却材配管（05）の吊下げ長さが長くなり，地震
発生時等には，冷却材配管（05）が大きく揺れ，これが
原子炉容器側板部（04）内面に衝接して，破損する惧れ
があり，これを防止するために，原子炉容器内に冷却材
配管（05）の振れ止め防止機構が必要になっている。(Problems to be Solved by the Invention) In the conventional fast breeder reactor shown in FIGS. 3 and 4, the cooling pipe (05) at the mouth of the reactor vessel (03) (04) is arranged in the upper plenum. By increasing the immersion depth, the generation of gas entrainment vortex (B) in the vicinity of the spout is suppressed, so the suspension length of coolant pipe (05) becomes longer and an earthquake occurs. In such cases, the coolant pipe (05) may shake greatly, and this may collide with the inner surface of the reactor vessel side plate (04) and be damaged. In order to prevent this, the coolant is placed in the reactor vessel. A steady stop mechanism for the pipe (05) is required.
本考案は前記の問題点に鑑み提案するものであり，そ
の目的とする処は，冷却材配管の振れ止め防止機構を不
要にできる原子炉容器の上部プレナムにおける渦防止装
置を提供しようとする点にある。The present invention is proposed in view of the above problems, and an object of the present invention is to provide a vortex preventive device in an upper plenum of a reactor vessel in which a steady rest prevention mechanism for a coolant pipe is unnecessary. It is in.
（課題を解決するための手段） 上記の目的を達成するために，本考案の原子炉容器の
上部プレナムにおける渦防止装置は，炉心を出て上部プ
レナム内構造物の底面部に沿って斜め外上方へ流動する
高温冷却材を衝突させてから斜め内上方へ変向させて冷
却材配管の周りを液面に向かわせる斜め内上方に傾斜し
た環状の流れ案内板を有し、同流れ案内板を原子炉容器
の上部プレナム内壁面にその全周にわたって設けてい
る。(Means for Solving the Problems) In order to achieve the above-mentioned object, the vortex preventive device in the upper plenum of the reactor vessel of the present invention exits the core and is slanted outward along the bottom surface of the upper plenum internal structure. The flow guide plate has an annular flow guide plate that is inclined obliquely inward and upward so that the high temperature coolant flowing upward is collided and then deflected obliquely inward and upward to direct the periphery of the coolant pipe to the liquid surface. Is provided on the inner wall surface of the upper plenum of the reactor vessel over the entire circumference thereof.
（作用） 本考案の原子炉容器の上部プレナムにおける渦防止装
置は前記のように構成されており，炉心を出た高温冷却
材の主流を上部プレナム内構造物の底面部に沿い斜め外
上方へ流動させて，流れ案内板へ衝突させ，同流れ案内
板からは斜め内上方へ変向させて，冷却材配管の周りを
液面に向かわせ，液面からは反転させて，冷却材配管の
周りを斜め下向きに流れる下降流とし，冷却材配管の底
部に設けた呑口部へ向かわせて，冷却材配管の呑口部付
近でのガス巻込み渦の発生を防止する。(Operation) The vortex preventive device in the upper plenum of the reactor vessel of the present invention is configured as described above, and the main flow of the high-temperature coolant exiting the core is slanted outward and upward along the bottom surface of the upper plenum internal structure. It is made to flow and collide with the flow guide plate, and is deflected obliquely inward and upward from the flow guide plate so that the periphery of the coolant pipe is directed to the liquid surface and inverted from the liquid surface. A downward flow that flows diagonally downward is directed to the mouth part provided at the bottom of the coolant pipe to prevent gas entrainment vortices near the mouth part of the coolant pipe.
（実施例） 次に本考案の原子炉容器の上部プレナムにおける渦防
止装置を第1,2図に示す一実施例により説明すると，
（１）が炉心，（２）が上部プレナム内構造物，（３）
が原子炉容器底板部，（４）が原子炉容器側板部，
（５）が原子炉容器（３）（４）の上部プレナムに垂下
状態に配設した冷却材配管，（６）が本考案で最も特徴
とする環状の流れ案内板で，同流れ案内板（６）が原子
炉容器（３）（４）の上部プレナム内壁面にその全周に
わたって設けられている。(Embodiment) Next, the vortex preventive device in the upper plenum of the reactor vessel of the present invention will be explained with reference to an embodiment shown in Figs.
(1) core, (2) upper plenum internal structure, (3)
Is the bottom plate of the reactor vessel, (4) is the side plate of the reactor vessel,
(5) is a coolant pipe arranged in a hanging state in the upper plenum of the reactor vessel (3) (4), and (6) is an annular flow guide plate which is the most characteristic of the present invention. 6) is provided on the inner wall surface of the upper plenum of the reactor vessel (3) (4) over the entire circumference thereof.
次に前記第1,2図に示す原子炉容器の上部プレナムに
おける渦防止装置の作用を具体的に説明する。炉心
（１）を出た高温冷却材の主流を上部プレナム内構造物
（２）の底面部に沿い斜め外上方へ流動させて（（Ａ）
参照），斜め内上方に傾斜した環状の流れ案内板（６）
へ衝突させ，同流れ案内板（６）からは斜め内上方へ変
向させて，冷却材配管（５）の周りを液円に向かわせ，
液面からは反転させ，冷却材配管（５）の周りを斜め下
向きに流れる下降流として冷却材配管（５）の底部に設
けた呑口部へ向かわせて，冷却材配管（５）の呑口部付
近でのガス巻込み渦の発生を防止する。Next, the operation of the vortex preventive device in the upper plenum of the reactor vessel shown in FIGS. 1 and 2 will be specifically described. The main stream of high-temperature coolant exiting the core (1) is made to flow diagonally outward and upward along the bottom surface of the upper plenum internal structure (2) ((A)
), An annular flow guide plate (6) inclined inward and upward
To the liquid circle from the same flow guide plate (6) by turning it obliquely inward and upward, and directing it around the coolant pipe (5) toward the liquid circle.
It is reversed from the liquid surface, and is directed as a downward flow that flows obliquely downward around the coolant pipe (5) toward the dowel part provided at the bottom of the coolant pipe (5), and the dovetail part of the coolant pipe (5). Prevents the generation of gas entrainment vortices in the vicinity.
（考案の効果） 本考案の原子炉容器の上部プレナムにおける渦防止装
置は前記のように炉心を出た高温冷却材の主流を上部プ
レナム内構造物の底面部に沿い斜め外上方へ流動させ
て，斜め内上方に傾斜した環状の流れ案内板へ衝突さ
せ，同流れ案内板からは斜め内上方へ変向させて，冷却
材配管の周りを液面に向かわせ，液面からは反転させ
て，冷却材配管の周りを斜め下向きに流れる下降流と
し，冷却材配管の底部に設けた呑口部へ向かわせて，冷
却材配管の呑口部付近でのガス巻込み渦の発生を防止す
るので，ガス巻込み渦の発生を抑制するのに冷却材配管
の吊下げ長さを長くする必要がなく，地震発生時等に冷
却材配管の原子炉容器内壁面への衝接を防止できて，冷
却材配管の振れ止め防止機構を不要にできる効果があ
る。(Effect of the Invention) As described above, the vortex preventer in the upper plenum of the reactor vessel of the present invention causes the main stream of the high temperature coolant, which has exited the core, to flow diagonally outward and upward along the bottom surface of the internal structure of the upper plenum. , Collide with an annular flow guide plate that is inclined inward and upward, and turn it obliquely inward and upward from the same flow guide plate so that the circumference of the coolant pipe is directed toward the liquid surface and inverted from the liquid surface. , As it is a downward flow that flows diagonally downward around the coolant pipe and is directed to the mouth part provided at the bottom of the coolant pipe, the generation of gas entrainment vortex near the mouth part of the coolant pipe is prevented. It is not necessary to increase the suspension length of the coolant pipe to suppress the generation of gas entrainment vortex, and it is possible to prevent the coolant pipe from colliding with the inner wall of the reactor vessel in the event of an earthquake, etc. This has the effect of eliminating the need for a steady rest prevention mechanism for material piping.
第１図は本考案に係わる原子炉容器の上部プレナムにお
ける渦防止装置の一実施例を示す縦断側面図，第２図は
その平面図，第３図は従来の高速増殖炉の原子炉容器を
示す縦断側面図，第４図はその平面図である。 （１）……炉心，（２）……上部プレナム内構造物，
（３）……原子炉容器底板部，（４）……原子炉容器側
板部，（５）……冷却材配管，（６）……流れ案内板。FIG. 1 is a vertical side view showing an embodiment of a vortex preventive device in an upper plenum of a reactor vessel according to the present invention, FIG. 2 is a plan view thereof, and FIG. 3 is a reactor vessel of a conventional fast breeder reactor. The vertical side view shown in FIG. 4 is a plan view thereof. (1) …… Reactor core, (2) …… Upper plenum internal structure,
(3) …… Reactor vessel bottom plate, (4) …… Reactor vessel side plate, (5) …… Coolant piping, (6) …… Flow guide plate.
───────────────────────────────────────────────────── フロントページの続き (72)考案者 郡 泰次 兵庫県高砂市荒井町新浜２丁目８番25号 高菱エンジニアリング株式会社内 (56)参考文献 特開 昭63−108293（ＪＰ，Ａ) 特開 昭62−88992（ＪＰ，Ａ) 特開 昭57−3082（ＪＰ，Ａ) ─────────────────────────────────────────────────── ─── Continuation of the front page (72) Inventor Taiji Gun 2-8-25 Niihama, Arai-cho, Takasago, Hyogo Prefecture Takahishi Engineering Co., Ltd. (56) References JP-A-63-108293 (JP, A) Kai 62-88992 (JP, A) JP-A-57-3082 (JP, A)
Claims (1)
に沿って斜め外上方へ流動する高温冷却材を衝突させて
から斜め内上方へ変向させて冷却材配管の周りを液面に
向かわせる斜め内上方に傾斜した環状の流れ案内板を有
し、同流れ案内板を原子炉容器の上部プレナム内壁面に
その全周にわたって設けたことを特徴とする原子炉容器
の上部プレナムにおける渦防止装置。1. A liquid surface around a coolant pipe by colliding with a high temperature coolant flowing obliquely outward and upward along the bottom surface of the upper plenum internal structure after leaving the core and deflecting it obliquely inward and upward. In an upper plenum of a reactor vessel, which has an annular flow guide plate inclined inwardly and upwardly and is provided on the inner wall surface of the upper plenum of the reactor vessel over the entire circumference thereof. Vortex prevention device.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1990084517U JP2507361Y2 (en) | 1990-08-13 | 1990-08-13 | Vortex prevention device in the upper plenum of the reactor vessel |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1990084517U JP2507361Y2 (en) | 1990-08-13 | 1990-08-13 | Vortex prevention device in the upper plenum of the reactor vessel |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPH0443300U JPH0443300U (en) | 1992-04-13 |
| JP2507361Y2 true JP2507361Y2 (en) | 1996-08-14 |
Family
ID=31633055
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP1990084517U Expired - Lifetime JP2507361Y2 (en) | 1990-08-13 | 1990-08-13 | Vortex prevention device in the upper plenum of the reactor vessel |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JP2507361Y2 (en) |
Family Cites Families (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS573082A (en) * | 1980-06-09 | 1982-01-08 | Tokyo Shibaura Electric Co | Lmfbr type reactor |
| JPS6288992A (en) * | 1985-10-15 | 1987-04-23 | 三菱原子力工業株式会社 | Nuclear reactor vessel with wave return |
| JPS63108293A (en) * | 1986-10-27 | 1988-05-13 | 株式会社東芝 | Tank type fast breeder reactor |
-
1990
- 1990-08-13 JP JP1990084517U patent/JP2507361Y2/en not_active Expired - Lifetime
Also Published As
| Publication number | Publication date |
|---|---|
| JPH0443300U (en) | 1992-04-13 |
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