JPH0333688A - Boiling water reactor - Google Patents
Boiling water reactorInfo
- Publication number
- JPH0333688A JPH0333688A JP1166686A JP16668689A JPH0333688A JP H0333688 A JPH0333688 A JP H0333688A JP 1166686 A JP1166686 A JP 1166686A JP 16668689 A JP16668689 A JP 16668689A JP H0333688 A JPH0333688 A JP H0333688A
- Authority
- JP
- Japan
- Prior art keywords
- water level
- liquid
- riser
- grating plate
- fluctuation
- 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
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 title claims abstract description 37
- 238000009835 boiling Methods 0.000 title claims description 11
- 239000007788 liquid Substances 0.000 claims abstract description 14
- 239000007791 liquid phase Substances 0.000 claims abstract description 6
- 239000012071 phase Substances 0.000 claims description 13
- 239000000446 fuel Substances 0.000 claims description 8
- 230000000712 assembly Effects 0.000 claims description 4
- 238000000429 assembly Methods 0.000 claims description 4
- 230000026058 directional locomotion Effects 0.000 claims 1
- 239000012808 vapor phase Substances 0.000 abstract 3
- 230000000694 effects Effects 0.000 description 3
- 238000005516 engineering process Methods 0.000 description 3
- 239000002826 coolant Substances 0.000 description 1
- 238000007689 inspection Methods 0.000 description 1
- 230000000737 periodic effect Effects 0.000 description 1
- 238000010248 power generation Methods 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)
Abstract
Description
【発明の詳細な説明】
〔産業上の利用分野〕
本発明は遠心分離型の気水分離器を削除した沸騰水型原
子炉の内部構造に関する。DETAILED DESCRIPTION OF THE INVENTION [Industrial Application Field] The present invention relates to the internal structure of a boiling water nuclear reactor in which a centrifugal type steam separator is eliminated.
従来の高出力の沸騰水型原子炉は、例えば、原子炉講座
（昭和５４年（社）火力発電技術協会）に記載されてい
るように、ライザの上方に気水分離器が取り付けられて
いる。また、出力の低い自然循環型の沸騰水型原子炉で
は気水分離器を削除したものがある。In conventional high-output boiling water reactors, for example, a steam-water separator is installed above the riser, as described in Nuclear Reactor Course (Thermal Power Generation Technology Association, 1978). . In addition, some low-output natural circulation boiling water reactors do not have a steam-water separator.
上記従来技術は出力の高い自然循環型の沸騰水型原子炉
において、自然循環力を確保すると共に気液二相水位の
変動をおさえるという点については考慮されておらず、
自然循環力を確保するために気水分離器を削除すると気
液二相水位の変動が大きくなり、気液二相水位の変動を
おさえるために気水分離器を設置すると自然循環力が低
下する問題があった。The above conventional technology does not take into account the need to ensure natural circulation force and suppress fluctuations in the gas-liquid two-phase water level in high-output natural circulation boiling water reactors.
If a steam/water separator is removed to ensure the natural circulation force, fluctuations in the gas-liquid two-phase water level will increase, and if a steam-water separator is installed to suppress fluctuations in the gas-liquid two-phase water level, the natural circulation force will decrease. There was a problem.
本発明の目的は出力の高い自然循環型の沸騰水型原子炉
において、自然循環力を確保すると共に気液二相水位の
変動をおさえることを目的としており、これにより炉内
機器の健全性を高めた経済的な沸騰水型原子炉を提供す
ることにある。The purpose of the present invention is to secure the natural circulation force in a high output natural circulation boiling water reactor and to suppress fluctuations in the gas-liquid two-phase water level, thereby improving the integrity of the reactor equipment. The objective is to provide an improved and economical boiling water reactor.
上記目的を達成するために、従来の遠心分離型の気水分
離器を削除しライザ上方の気液二相水位が形成される位
置に、ライザ上端と距離をおいて格子板を設置したもの
である。In order to achieve the above purpose, the conventional centrifugal type steam/water separator was removed and a grid plate was installed above the riser at a distance from the top of the riser where a gas-liquid two-phase water level was formed. be.
ライザ上方の気液二相水位が形成される位置に設置した
格子板は、液相の水平方向の運動を妨げるため気液二相
水位の水平方向の変動は格子板により分断され、変動が
おさえられる。また、格子板はライザ上端と距離をおい
て設置されているため循環する液相にとっては流動抵抗
にならず自然循環力が確保される。The grid plate installed above the riser at the position where the gas-liquid two-phase water level is formed prevents the horizontal movement of the liquid phase, so horizontal fluctuations in the gas-liquid two-phase water level are separated by the grid plate, suppressing the fluctuations. It will be done. Further, since the grid plate is installed at a distance from the upper end of the riser, it does not create flow resistance for the circulating liquid phase, and natural circulation force is ensured.
以下、本発明の一実施例を第１図により説明する。本実
施例は、電気出力６００ＭＷｅの自然循環型原子炉に本
発明を適用した例である。上部格子板５と下部格子板４
で保持された多数の燃料集合体２で構成される炉心で発
生した蒸気はドライヤ６で湿分を除去したのち、主蒸気
管７を通してタービン（図示せず）に導かれ、タービン
で電気３−
に変換されたのち水に戻され、給水管８を通して圧力容
器１に戻る。炉心には、ライザ３内外の圧力差に基づく
自然循環によって冷却材が流入し、炉心が冷却される。An embodiment of the present invention will be described below with reference to FIG. This example is an example in which the present invention is applied to a natural circulation nuclear reactor with an electrical output of 600 MWe. Upper lattice plate 5 and lower lattice plate 4
The steam generated in the reactor core, which is composed of a large number of fuel assemblies 2 held in the After being converted into water, it is returned to the pressure vessel 1 through the water supply pipe 8. Coolant flows into the core through natural circulation based on the pressure difference between the inside and outside of the riser 3, and the core is cooled.
このような自然循環型原子炉のライザ３の上方の気液二
相水位が形成される位置に、ライザ３の上端と距離をお
いて、格子板１ｏが設置されている。格子板１０の高さ
は、圧力容器ｌの直径の１／１０から１／３０の値が好
適である。第１図のｎ−ｎ矢視断面図を第２図に示す。A grid plate 1o is installed at a position above the riser 3 of such a natural circulation nuclear reactor, at a distance from the upper end of the riser 3, where a gas-liquid two-phase water level is formed. The height of the grid plate 10 is preferably 1/10 to 1/30 of the diameter of the pressure vessel l. A sectional view taken along the line nn in FIG. 1 is shown in FIG. 2.
格子板１０は液相の水平方向の運動を妨げるため気液二
相水位の水平方向の変動は格子板１０により分断され、
変動がおさえられている。Since the grid plate 10 prevents horizontal movement of the liquid phase, horizontal fluctuations in the gas-liquid two-phase water level are separated by the grid plate 10.
Fluctuations are suppressed.
これによって、炉内機器、例えば、計装用配管に作用す
る応力の頻度、及び、強度が低下するため炉内機器の信
頼性がさらに向上し、二相水位の変動によって生じる液
滴の量が低下するため蒸気に同伴されたドライヤ６に達
する液滴の量も低下し、ドライヤ６の設計条件が緩和さ
れる。また、格子板１０はライザ３の上端と距離をおい
て設置されているため循環する液相にとっては流動抵抗
にな４
らず、自然循環力は格子板１０がない場合と、はぼ、同
じである。また、格子板１０の水平方向の位置を、炉心
を構成する燃料集合体２を保持する上部格子板５の水平
方向の位置と同じにしであるため、格子板ｌＯを取り外
すことなく燃料交換を行うことができる。本実施例は自
然循環型原子炉の場合を示すが、強制循環型原子炉の場
合にも本発明は有効である。このように、本実施例によ
れば自然循環力を低下することなく、気液二相水面の変
動を押さえることができ、圧力容器内部構造物を取り外
すこなく燃料交換を行える効果がある。This further improves the reliability of the reactor equipment by reducing the frequency and strength of stresses acting on the equipment, such as instrumentation piping, and reduces the amount of droplets generated by two-phase water level fluctuations. Therefore, the amount of droplets that are entrained in the steam and reach the dryer 6 is also reduced, and the design conditions for the dryer 6 are relaxed. In addition, since the grid plate 10 is installed at a distance from the upper end of the riser 3, it does not create flow resistance for the circulating liquid phase, and the natural circulation force is almost the same as without the grid plate 10. It is. Furthermore, since the horizontal position of the grid plate 10 is the same as the horizontal position of the upper grid plate 5 that holds the fuel assemblies 2 constituting the reactor core, fuel exchange can be performed without removing the grid plate IO. be able to. Although this example shows the case of a natural circulation nuclear reactor, the present invention is also effective in the case of a forced circulation nuclear reactor. As described above, according to this embodiment, fluctuations in the gas-liquid two-phase water level can be suppressed without reducing the natural circulation force, and there is an effect that fuel exchange can be performed without removing the internal structure of the pressure vessel.
本発明によれば、自然循環力を確保すると共に気液二相
水位の変動をおさえることができるので、炉内機器の健
全性を高めた経済的な沸騰水型原子炉を提供することが
できる。According to the present invention, natural circulation force can be ensured and fluctuations in the gas-liquid two-phase water level can be suppressed, so it is possible to provide an economical boiling water reactor with improved soundness of the reactor equipment. .
また、圧力容器内部構造物を取り外すことなく燃料交換
を行えるので、定期検査の期間が短縮される。Furthermore, since fuel can be replaced without removing the internal structure of the pressure vessel, the period of periodic inspections can be shortened.
第１図は本発明の一実施例を示す圧力容器の縦断面図、
第２図は第１図のｎ−ｎ矢視断面図である。
１・・・圧力容器、２・・・燃料集合体、３・・・ライ
ザ、４・・・下部格子板、５・・・上部格子板、６・・
・ドライヤ、第
１
図
特開平３
３３６８８ （３）
第２図FIG. 1 is a longitudinal sectional view of a pressure vessel showing an embodiment of the present invention;
FIG. 2 is a sectional view taken along the line nn in FIG. 1. DESCRIPTION OF SYMBOLS 1... Pressure vessel, 2... Fuel assembly, 3... Riser, 4... Lower grid plate, 5... Upper grid plate, 6...
・Dryer, Fig. 1 JP-A-3-33688 (3) Fig. 2
Claims (1)
よりなる沸騰水型原子炉において、 前記ライザ上方の気液二相水位が形成される位置に、液
相の水平方向の運動を妨げるように格子板を設置したこ
とを特徴とする沸騰水型原子炉。 ２、請求項１において、前記格子板の水平方向の位置は
前記炉心を構成する燃料集合体を保持する上部格子板の
水平方向の位置と同じであることを特徴とする沸騰水型
原子炉。[Claims] 1. In a boiling water nuclear reactor consisting of a core made up of fuel assemblies and a riser surrounding the core, a horizontal liquid phase is formed above the riser at a position where a gas-liquid two-phase water level is formed. A boiling water reactor characterized by having a grid plate installed to prevent directional movement. 2. The boiling water nuclear reactor according to claim 1, wherein the horizontal position of the grid plate is the same as the horizontal position of the upper grid plate that holds the fuel assemblies constituting the reactor core.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1166686A JPH0333688A (en) | 1989-06-30 | 1989-06-30 | Boiling water reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1166686A JPH0333688A (en) | 1989-06-30 | 1989-06-30 | Boiling water reactor |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH0333688A true JPH0333688A (en) | 1991-02-13 |
Family
ID=15835856
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP1166686A Pending JPH0333688A (en) | 1989-06-30 | 1989-06-30 | Boiling water reactor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH0333688A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2007232423A (en) * | 2006-02-28 | 2007-09-13 | Hitachi Ltd | Natural circulation boiling water reactor |
-
1989
- 1989-06-30 JP JP1166686A patent/JPH0333688A/en active Pending
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2007232423A (en) * | 2006-02-28 | 2007-09-13 | Hitachi Ltd | Natural circulation boiling water reactor |
| JP4568238B2 (en) * | 2006-02-28 | 2010-10-27 | 日立Ｇｅニュークリア・エナジー株式会社 | Natural circulation boiling water reactor |
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