JPH02268293A - Natural circulation type boiling water nuclear reactor - Google Patents
Natural circulation type boiling water nuclear reactorInfo
- Publication number
- JPH02268293A JPH02268293A JP1088158A JP8815889A JPH02268293A JP H02268293 A JPH02268293 A JP H02268293A JP 1088158 A JP1088158 A JP 1088158A JP 8815889 A JP8815889 A JP 8815889A JP H02268293 A JPH02268293 A JP H02268293A
- Authority
- JP
- Japan
- Prior art keywords
- boiling water
- reactor
- reactor core
- flow
- core shroud
- 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 48
- 238000009835 boiling Methods 0.000 title claims abstract description 38
- 239000002826 coolant Substances 0.000 claims abstract description 25
- 230000001174 ascending effect Effects 0.000 claims description 2
- 230000007423 decrease Effects 0.000 abstract description 6
- 239000007788 liquid Substances 0.000 abstract description 6
- 238000000926 separation method Methods 0.000 abstract description 6
- 230000005514 two-phase flow Effects 0.000 abstract description 6
- 239000000463 material Substances 0.000 description 2
- 230000005540 biological transmission Effects 0.000 description 1
- 238000001816 cooling Methods 0.000 description 1
- 239000000498 cooling water Substances 0.000 description 1
- 230000007797 corrosion Effects 0.000 description 1
- 238000005260 corrosion Methods 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000000034 method Methods 0.000 description 1
- 238000010248 power generation Methods 0.000 description 1
- 230000002250 progressing effect Effects 0.000 description 1
- 230000001737 promoting effect Effects 0.000 description 1
- 230000000630 rising 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
- Structure Of Emergency Protection For 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)
本発明は自然循環式沸騰水型原子炉に係り、特に蒸気と
水分との分離効率を改善し、タービン等の付属機器の運
転効率および炉心における伝熱効率を向上させることが
できる自然循環式沸騰水型原子炉に関する。[Detailed Description of the Invention] [Object of the Invention] (Industrial Application Field) The present invention relates to a natural circulation boiling water nuclear reactor, and in particular improves the separation efficiency of steam and water, and improves the efficiency of auxiliary equipment such as a turbine. This invention relates to a natural circulation boiling water reactor that can improve the operational efficiency and heat transfer efficiency in the reactor core.
(従来の技術)
従来の沸騰水型原子炉は一般に第2図に示すように構成
されている。すなわち図において原子炉圧力容器1内の
中心部には炉心2が収納され、この炉心2を覆うように
筒状の炉心シュラウド3が配設されている。そして、炉
心シュラウド3と原子炉圧力容器1との間隙の下部には
複数の再循環ポンプ4が配設されている。(Prior Art) A conventional boiling water nuclear reactor is generally configured as shown in FIG. That is, in the figure, a reactor core 2 is housed in the center of a reactor pressure vessel 1, and a cylindrical core shroud 3 is disposed to cover this reactor core 2. A plurality of recirculation pumps 4 are disposed below the gap between the core shroud 3 and the reactor pressure vessel 1.
炉心2における核反応によって生成した熱エネルギを得
て、冷却水は高温高圧の蒸気となって、炉心シュラウド
3内を上方向に流れる。水と蒸気との混合流は、セパレ
ータ5によって水分が分離された後に、さらに蒸気乾燥
器6に導入され、ここで湿分を十分除去された侵に、主
蒸気配管7等を通り、タービン8に導かれる。タービン
8を駆動した蒸気はコンデンサ9において復水とされ、
この復水は給水配管10を通り、再び炉心シュラウド3
の外側の環状流路に流入する。The cooling water obtains thermal energy generated by the nuclear reaction in the reactor core 2, turns into high-temperature, high-pressure steam, and flows upward in the core shroud 3. After the water and steam are separated by the separator 5, the mixed flow of water and steam is further introduced into the steam dryer 6, where the moisture is sufficiently removed, and then passed through the main steam pipe 7, etc., to the turbine 8. guided by. The steam that drove the turbine 8 is condensed in a condenser 9,
This condensate passes through the water supply pipe 10 and returns to the core shroud 3.
into the outer annular channel.
ところで第2図に示すような強制循環式沸騰水型原子炉
においては、大型の再循環ポンプ4やそれに付属する補
助発電設備および制@装首などを装備する必要があるた
め原子炉のシスデム構成が?!2雑化し、設備費および
運転コストも高騰する問題点がある。By the way, in a forced circulation boiling water reactor as shown in Fig. 2, it is necessary to equip a large recirculation pump 4, an auxiliary power generation equipment attached to it, a head restraint, etc., so the system configuration of the reactor is but? ! There are problems in that the process becomes complicated and equipment costs and operating costs rise.
近年、システムの簡素化と設備コスト、運転コストの低
減とを図る目的で再循環ポンプ4を装備しない自然循環
式沸騰水型原子炉の開発が進められている。この形式の
沸騰水型原子炉は、冷却材を強制的に循環させる機器を
設けず、炉心シュラウド3内外を流れる冷却材の密度差
に基づく自然循環力によって冷却材を循環させるもので
ある。In recent years, development of a natural circulation boiling water reactor that is not equipped with a recirculation pump 4 has been progressing in order to simplify the system and reduce equipment costs and operating costs. This type of boiling water reactor does not have any equipment for forcibly circulating the coolant, but instead circulates the coolant by natural circulation force based on the density difference between the coolant flowing inside and outside the core shroud 3.
また上記の沸騰水型原子炉では、自然循環力を大きく確
保するために原子炉内における冷部材の流動抵抗を可及
的に低減するように工夫されており、例えば抵抗が大き
なセパレータ5も排除される場合が多い。In addition, in the boiling water reactor mentioned above, in order to ensure a large natural circulation force, the flow resistance of the cold parts in the reactor is reduced as much as possible, and for example, the separator 5, which has a large resistance, is also eliminated. It is often done.
(発明が解決しようとする課題)
しかしながら上記のような従来の自然循環式Ni l水
型原子炉においては、セパレータを排除しているため、
発生した蒸気中に混入した水分と蒸気との分離効十が低
く、蒸気乾燥器側への液滴の流出、いわゆるキャリーオ
ーバーが多い。そのためタービンに供給する悪気条件が
悪化し、タービンの腐食損傷を促進し、その運転効率を
低下させる問題点がある。(Problems to be Solved by the Invention) However, in the conventional natural circulation type Ni l water reactor as described above, since a separator is excluded,
The separation efficiency between the moisture mixed in the generated steam and the steam is low, and droplets often flow out to the steam dryer side, so-called carryover. Therefore, there is a problem in that the bad air conditions supplied to the turbine deteriorate, promoting corrosion damage to the turbine and reducing its operating efficiency.
一方、気液分離効率の低下は、必然的に炉心シュラウド
と原子炉圧力容器との間の環状流路を下降する冷却材に
蒸気が巻き込まれる、いわゆるキャリーアンダーの増大
化を誘発する。そのため炉心入口における冷却材のエン
タルピーが変化し、原子炉炉心における伝熱効率を低下
させ、ひいては原子炉の出力の低下を招く。On the other hand, a decrease in gas-liquid separation efficiency inevitably induces an increase in so-called carry-under, in which steam is drawn into the coolant descending in the annular flow path between the reactor core shroud and the reactor pressure vessel. As a result, the enthalpy of the coolant at the reactor core inlet changes, reducing the heat transfer efficiency in the reactor core, which in turn causes a reduction in the output of the reactor.
本発明は上記の問題点を解決するためになされたもので
あり、セパレータを排除しても蒸気と水分との分離効率
を高く維持することができる自然循環式沸騰水型原子炉
を提供することを目的とする。The present invention has been made in order to solve the above problems, and provides a natural circulation boiling water nuclear reactor that can maintain high separation efficiency between steam and water even if a separator is eliminated. With the goal.
(課題を解決するための手段)
本発明は、原子炉圧力容器内壁から隔離して同心状に炉
心シュラウドを配設し、炉心を通過した冷却材を沸騰水
面方向に案内する冷却材上昇路を形成するとともに、原
子炉圧力容器内壁と炉心シュラウドとの間に冷却材下降
路を形成した自然viU環式沸騰水型原子炉において、
上記炉心シュラウドの上部を沸騰水面方向に拡開し、流
路断面積を増大するように形成したことを特徴とする。(Means for Solving the Problems) The present invention includes a core shroud that is arranged concentrically and isolated from the inner wall of the reactor pressure vessel, and a coolant rise path that guides the coolant that has passed through the reactor core toward the boiling water surface. In a natural VIU ring boiling water reactor in which a coolant descending passage is formed between the reactor pressure vessel inner wall and the reactor core shroud,
It is characterized in that the upper part of the core shroud is expanded in the direction of the boiling water surface to increase the cross-sectional area of the flow passage.
(作用)
上記構成の自然循環式沸騰水型原子炉によれば、炉心シ
ュラウドの上部を沸騰水面方向に拡開してその流路断面
積を増大するように形成しているため、炉心を通過して
気液二相流となった冷却材の上昇速度は、沸騰水面近傍
において大幅に低減される。そのため沸騰水面から蒸気
乾燥器側向に流れる蒸気に同伴される液滴(キャリーオ
ーバー)は大幅に減少する。(Function) According to the natural circulation boiling water reactor with the above configuration, the upper part of the core shroud is expanded in the direction of the boiling water surface to increase the cross-sectional area of the flow passage, so that the flow passage through the core is expanded. The rising speed of the coolant, which has become a gas-liquid two-phase flow, is significantly reduced near the boiling water surface. Therefore, droplets (carryover) entrained in the steam flowing from the boiling water surface toward the side of the steam dryer are significantly reduced.
したがってタービンに送給される液滴Wも少なく、ター
ビンの損傷や運転効率の低下が効果的に防止される。Therefore, fewer droplets W are fed to the turbine, and damage to the turbine and reduction in operating efficiency are effectively prevented.
一方、沸騰水面から環状流路に流入する冷却材の流速も
低減されるため、冷却材に巻込まれる蒸気のキャリーア
ンダーも減少し、炉心における伝熱効率の低下をも防止
することができる。On the other hand, since the flow velocity of the coolant flowing into the annular flow path from the boiling water surface is also reduced, the amount of carry-under of steam entrained in the coolant is also reduced, and a decrease in heat transfer efficiency in the core can also be prevented.
(実施例)
以下本発明の一実施例について添付図面を参照して説明
する。第1図は本発明に係る自然循環式沸騰水型原子炉
の一実施例を示す概略縦断面図である。なお第2図に示
す従来例と同一要素には同一符号を付してその詳wI説
明は省略する。(Example) An example of the present invention will be described below with reference to the accompanying drawings. FIG. 1 is a schematic vertical sectional view showing an embodiment of a natural circulation boiling water nuclear reactor according to the present invention. Note that the same elements as those in the conventional example shown in FIG. 2 are given the same reference numerals, and detailed explanation thereof will be omitted.
本実施例に係る自然循環式沸騰水型原子炉は、原子炉圧
力容器1内壁から隔離して同心状に炉心シュラウド3a
を配設し、炉心2を通過した冷En材を沸企水面11方
向に案内する冷却材上昇路12を形成するとともに、原
子炉圧力容器1内壁と炉心シュラウド3aとの間に断面
環状の冷却材下降路13を形成した自然循環式沸騰水型
原子炉において、上記炉心シュラウド3aの上部を沸騰
水面方向に拡開し、流路断面積を増大するように形成し
て構成される。In the natural circulation boiling water reactor according to this embodiment, a core shroud 3a is installed concentrically and isolated from the inner wall of the reactor pressure vessel 1.
is arranged to form a coolant ascending passage 12 that guides the cold En material that has passed through the reactor core 2 in the direction of the boiling water surface 11, and a cooling pipe having an annular cross section between the inner wall of the reactor pressure vessel 1 and the core shroud 3a. In a natural circulation boiling water nuclear reactor in which a material descending passage 13 is formed, the upper part of the core shroud 3a is expanded in the direction of the boiling water surface to increase the cross-sectional area of the passage.
炉心2を通過した冷却材は、蒸気と水との気液二相流を
形成し、炉心シュラウド3aの直筒部内を大きな上が速
度で蒸気乾燥器6方向に流れる。The coolant that has passed through the core 2 forms a gas-liquid two-phase flow of steam and water, and flows at a high velocity in the direction of the steam dryer 6 within the straight cylindrical portion of the core shroud 3a.
しかし炉心シュラウド3aの上方に流れるに従って流路
断面積が増大しているため、徐々に流動速度が低減され
る。そて沸騰水面11近傍における二相流の流速は、炉
心通過直後の流速の数分の1から10分の1程度ま?U
−?tさ゛れる。However, since the cross-sectional area of the flow path increases as it flows above the core shroud 3a, the flow rate gradually decreases. And the flow velocity of the two-phase flow near the boiling water surface 11 is about 1/10 to 1/10 of the flow velocity immediately after passing through the core? U
−? I can't stand it.
そのため、気液分離が容易に行なわれ、キャリーオーバ
ーやキャリーアンダーが大幅に減少する。Therefore, gas-liquid separation is easily performed, and carryover and carryunder are significantly reduced.
したがって主蒸気に同伴されてタービン8に送給される
液滴量が少なく、タービン8の損傷や運転効率の低下が
効果的に防止される。。Therefore, the amount of droplets entrained in the main steam and fed to the turbine 8 is small, and damage to the turbine 8 and reduction in operating efficiency are effectively prevented. .
一方、沸騰水面11から、炉心シュラウド3a外面側に
形成された断面環状の冷却材下降路13に流入する冷却
材流速も低減されるため、冷却材に混入する蒸気量も減
少し、炉心における伝熱特性を損う91合も大幅に低減
する。On the other hand, since the flow velocity of the coolant flowing from the boiling water surface 11 into the coolant descending path 13 having an annular cross section formed on the outer surface of the core shroud 3a is also reduced, the amount of steam mixed into the coolant is also reduced, and the transmission in the core is reduced. 91 degrees which impair thermal properties are also significantly reduced.
以上説明の通り本発明に係る自然循環式沸騰水型原子炉
によれば、炉心シュラウドの上部を沸騰水面方向に拡開
してその流路断面積を増大するように形成しているため
、炉心を通過して気液二相流となった冷却材の上界速度
は、沸騰水面近傍において大幅に低減される。そのため
沸騰水面から蒸気乾燥器方向に流れる蒸気に同伴される
液滴(キャリーオーバー)は大幅に減少する。したがっ
てタービンに送給される液滴量も少なく、タービンの損
傷や運転効率の低下が効果的に防止される。As explained above, according to the natural circulation boiling water reactor according to the present invention, the upper part of the core shroud is expanded in the direction of the boiling water surface to increase the cross-sectional area of the flow passage, so that the reactor core The upper limit velocity of the coolant that has passed through the gas-liquid two-phase flow is significantly reduced near the boiling water surface. Therefore, droplets (carryover) entrained in the steam flowing from the boiling water surface toward the steam dryer are significantly reduced. Therefore, the amount of droplets fed to the turbine is also small, and damage to the turbine and reduction in operating efficiency are effectively prevented.
一方、沸騰水面から環状流路に流入する冷却材の流速も
低減されるため、冷却材に巻込まれる蒸気のキャリーア
ンダーも減少し、炉心にお()る伝熱効率の低下をも防
止することができる。On the other hand, since the flow velocity of the coolant flowing from the boiling water surface into the annular flow path is reduced, the carry-under of steam entrained in the coolant is also reduced, and it is also possible to prevent a decrease in heat transfer efficiency into the reactor core. can.
第1図は本発明の一実施例の概略縦断面図、第2図は従
来の沸騰水型軽水炉の概略構成図である。
1・・・原子炉圧力容器、2・・・炉心、3,3a・・
・炉心シュラウド、4・・・再循環ポンプ、5・・・セ
パレータ、6・・・蒸気乾燥器、7・・・主蒸気管、8
・・・タービン、9・・・コンデンサ、10・・・給水
配管、11・・・沸騰水面、12・・・冷却材上界路、
13・・・冷却材下降路。FIG. 1 is a schematic longitudinal sectional view of an embodiment of the present invention, and FIG. 2 is a schematic diagram of a conventional boiling water type light water reactor. 1... Reactor pressure vessel, 2... Reactor core, 3, 3a...
・Core shroud, 4... Recirculation pump, 5... Separator, 6... Steam dryer, 7... Main steam pipe, 8
...Turbine, 9...Condenser, 10...Water supply piping, 11...Boiling water surface, 12...Coolant upper boundary path,
13... Coolant descending path.
Claims (1)
ドを配設し、炉心を通過した冷却材を沸騰水面方向に案
内する冷却材上昇路を形成するとともに、原子炉圧力容
器内壁と炉心シユラウドとの間に冷却材下降路を形成し
た自然循環式沸騰水型原子炉において、上記炉心シユラ
ウドの上部を沸騰水面方向に拡開し、流路断面積を増大
するように形成したことを特徴とする自然循環式沸騰水
型原子炉。The core shroud is arranged concentrically and isolated from the reactor pressure vessel inner wall to form a coolant ascending path that guides the coolant that has passed through the reactor core toward the boiling water surface. A natural circulation boiling water reactor in which a coolant descending path is formed between the reactor and the reactor, characterized in that the upper part of the core shroud is expanded in the direction of the boiling water surface to increase the cross-sectional area of the flow path. Natural circulation boiling water reactor.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP1088158A JPH02268293A (en) | 1989-04-10 | 1989-04-10 | Natural circulation type boiling water nuclear reactor |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP1088158A JPH02268293A (en) | 1989-04-10 | 1989-04-10 | Natural circulation type boiling water nuclear reactor |
Publications (1)
Publication Number | Publication Date |
---|---|
JPH02268293A true JPH02268293A (en) | 1990-11-01 |
Family
ID=13935116
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP1088158A Pending JPH02268293A (en) | 1989-04-10 | 1989-04-10 | Natural circulation type boiling water nuclear reactor |
Country Status (1)
Country | Link |
---|---|
JP (1) | JPH02268293A (en) |
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPH0610986U (en) * | 1992-07-09 | 1994-02-10 | 富泰 本多 | Bulletin board |
JP2008122143A (en) * | 2006-11-09 | 2008-05-29 | Hitachi-Ge Nuclear Energy Ltd | Boiling-water reactor of natural circulation type |
-
1989
- 1989-04-10 JP JP1088158A patent/JPH02268293A/en active Pending
Cited By (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPH0610986U (en) * | 1992-07-09 | 1994-02-10 | 富泰 本多 | Bulletin board |
JP2008122143A (en) * | 2006-11-09 | 2008-05-29 | Hitachi-Ge Nuclear Energy Ltd | Boiling-water reactor of natural circulation type |
JP4504343B2 (en) * | 2006-11-09 | 2010-07-14 | 日立Geニュークリア・エナジー株式会社 | Natural circulation boiling water reactor |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
US5924389A (en) | Heat recovery steam generator | |
WO2007100041A1 (en) | Gas-water separator | |
JPH10221480A (en) | Steam separator, atomic power plant and boiler device | |
US4847043A (en) | Steam-assisted jet pump | |
US20090120297A1 (en) | Steam-Water Separator | |
JPH0395496A (en) | Method for applying natural circulation type boiling water reactor of free surface vapor separation system with load following faculty | |
JPH02281194A (en) | Steam separating system for boiling water reactor | |
JPH02268293A (en) | Natural circulation type boiling water nuclear reactor | |
EP0298191B1 (en) | Multiple discharge cylindrical pump collector | |
US4193446A (en) | Intermediate steam superheater | |
JP2012058113A (en) | Steam separation facility for nuclear reactor | |
JP5663324B2 (en) | Steam separator and boiling water reactor using the same | |
US5976207A (en) | Water separating system | |
JPS61250406A (en) | Feedwater heater for steam generator | |
JP2003114293A (en) | Steam separator and boiling water type nuclear reactor | |
US11398317B2 (en) | Apparatuses for steam separation, and nuclear boiling water reactors including the same | |
US4473036A (en) | Means and method for vapor generation | |
JP4078057B2 (en) | Natural circulation boiling water reactor | |
JPH04230896A (en) | Output adjustable natural-circulation type boiling water reactor | |
JP2012117857A (en) | Steam separator | |
JPH05187736A (en) | Absorption type heat pump device | |
US5996350A (en) | Method and apparatus for the superheating of steam | |
JPH02251796A (en) | Boiling water nuclear reactor | |
JPH04244995A (en) | Boiling water reactor | |
JP2006125950A (en) | Feed water nozzle and reactor facility using feed water nozzle |