JPH0658424B2 - Light water cooled reactor - Google Patents
Light water cooled reactorInfo
- Publication number
- JPH0658424B2 JPH0658424B2 JP59241356A JP24135684A JPH0658424B2 JP H0658424 B2 JPH0658424 B2 JP H0658424B2 JP 59241356 A JP59241356 A JP 59241356A JP 24135684 A JP24135684 A JP 24135684A JP H0658424 B2 JPH0658424 B2 JP H0658424B2
- Authority
- JP
- Japan
- Prior art keywords
- primary cooling
- cooling water
- core
- water
- plenum
- 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
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 title claims description 55
- 239000000498 cooling water Substances 0.000 claims description 85
- 238000001816 cooling Methods 0.000 claims description 19
- KGBXLFKZBHKPEV-UHFFFAOYSA-N boric acid Chemical compound OB(O)O KGBXLFKZBHKPEV-UHFFFAOYSA-N 0.000 claims description 15
- 239000004327 boric acid Substances 0.000 claims description 15
- 230000001174 ascending effect Effects 0.000 claims 2
- 239000007788 liquid Substances 0.000 description 9
- 230000000694 effects Effects 0.000 description 5
- 238000006243 chemical reaction Methods 0.000 description 2
- 230000004992 fission Effects 0.000 description 2
- 230000005484 gravity Effects 0.000 description 2
- 239000007787 solid Substances 0.000 description 2
- 239000000725 suspension Substances 0.000 description 2
- 229910000831 Steel Inorganic materials 0.000 description 1
- 230000002159 abnormal effect Effects 0.000 description 1
- 230000000740 bleeding effect Effects 0.000 description 1
- 239000012530 fluid Substances 0.000 description 1
- 230000001939 inductive effect Effects 0.000 description 1
- 230000000149 penetrating effect Effects 0.000 description 1
- 239000011513 prestressed concrete Substances 0.000 description 1
- 239000012857 radioactive material Substances 0.000 description 1
- 239000010959 steel Substances 0.000 description 1
- 238000006467 substitution reaction Methods 0.000 description 1
- 230000002195 synergetic 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)
- Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)
- Physical Or Chemical Processes And Apparatus (AREA)
Description
【発明の詳細な説明】 「産業上の利用分野」 本発明は、ほう酸水の濃度により出力の制御を行なうよ
うにした軽水冷却型原子炉に関するものである。TECHNICAL FIELD The present invention relates to a light water cooled nuclear reactor in which the output is controlled by the concentration of boric acid water.
「従来の技術」 ほう酸水の濃度により出力の制御を行なうようにした軽
水冷却型原子炉は、万一、内部温度の異常上昇が生じた
ときに、炉心の付近とその周囲のプール水との温度差等
によって、流体の比重の差が生じ対流を起こす現象を利
用して、プール水であるほう酸水を炉心に送り込むこと
により、原子炉を自然停止状態に導くようにしたもの
で、いわゆるフールプルーフ式となっており、近年、原
子力発電プラントの都市接近等の立地条件を十分考慮し
なければならないところから、注目されている。"Prior art" A light water cooling type reactor, whose output is controlled by the concentration of boric acid water, should be kept in the vicinity of the core and pool water around it when an abnormal increase in internal temperature occurs. By utilizing the phenomenon that convection occurs due to the difference in specific gravity of fluid due to temperature difference, etc., boric acid water, which is pool water, is sent to the core to lead the reactor to a natural shutdown state. It is a proof type, and has recently attracted attention because it is necessary to fully consider the location conditions such as the approach of a nuclear power plant to the city.
その従来構造例について、第３図及び第４図に基づき説
明すると、ほう酸水からなるプール水Ｗを収納するため
の圧力容器31は、厚いプレストレストコンクリート壁に
よって構成されるとともに、圧力容器31のライナ32の中
に炉心33が設けられ、該炉心33は二重構造の外側ケース
34及び内側ケース35で囲まれ、また、二重ケース34・35
の上部に二重筒体36・37が連設され、内側ケース35は二
重筒体36・37の間の環状流路38に、二重ケース34・35の
間の環状流路39は連通管40を経由して内側筒体37に接続
され、外側筒体36の上部は熱交換器（蒸気発生器）41の
一次冷却水入り口42に、内側筒体37の上部は熱交換器41
の一次冷却水出口43にそれぞれ接続されている。また、
熱交換器41の下部には、一次冷却水を強制循環させるた
めのポンプ44が設けられている。An example of the conventional structure will be described with reference to FIGS. 3 and 4. A pressure vessel 31 for accommodating pool water W made of boric acid water is composed of a thick prestressed concrete wall and a liner of the pressure vessel 31. A core 33 is provided in the core 32, and the core 33 has a double-structured outer case.
Surrounded by 34 and inner case 35, double case 34/35
Double cylinders 36 and 37 are connected to the upper part of the inner case 35, and the inner case 35 is connected to the annular flow path 38 between the double cylinders 36 and 37, and the annular flow path 39 between the double cases 34 and 35 is connected. It is connected to the inner cylinder body 37 via a pipe 40, the upper part of the outer cylinder body 36 is the primary cooling water inlet 42 of the heat exchanger (steam generator) 41, and the upper part of the inner cylinder body 37 is the heat exchanger 41.
Are connected to the primary cooling water outlets 43, respectively. Also,
A pump 44 for forcibly circulating the primary cooling water is provided below the heat exchanger 41.
そして、二重筒体36・37の上方位置には、一次冷却水入
り口42及び出口43への配管を貫通状態に支持するための
プレナム用ケーシング45が設けられるとともに、該ケー
シング45の上にカバー46が取り付けられ、さらに、前記
圧力容器31等の上部に遮蔽蓋47が配設された構造であ
る。A plenum casing 45 for supporting the pipes to the primary cooling water inlet 42 and the outlet 43 in a penetrating state is provided above the double cylinders 36 and 37, and a cover is provided on the casing 45. 46 is attached, and a shielding lid 47 is arranged on the pressure vessel 31 and the like.
このような構造を有する原子炉を運転状態とすると、第
３図に実線の矢印で示すように、一次冷却水が炉心33、
内側ケース35、環状流路38、一次冷却水入り口42、熱交
換器41、一次冷却水出口43、内側筒体37、運通管40、環
状流路39、炉心33を経由する循環流となり、このとき、
プレナム用ケーシング45の中に液面レベルWL１が、ま
た、カバー46の中に液面レベルWL２がそれぞれ形成され
る。一方、運転停止状態とすると、第３図に破線の矢印
で示すように自然循環が生じる。即ち、一次冷却水が炉
心33、内側ケース35、環状流路38、プレナム用ケーシン
グ45の下部開口、外側筒体36等の周囲であるプール水
Ｗ、外側ケース34の下部開口、炉心33を経由する循環流
となり、このとき、ほう酸水の濃度の高いプール水Ｗが
順次炉心33に供給されることにより、核分裂反応が抑制
されて自然停止に導かれるものである。When the reactor having such a structure is brought into an operating state, as shown by the solid arrow in FIG.
The inner case 35, the annular flow passage 38, the primary cooling water inlet 42, the heat exchanger 41, the primary cooling water outlet 43, the inner tubular body 37, the passage pipe 40, the annular flow passage 39, the circulation flow through the core 33, When
A liquid level WL1 is formed in the plenum casing 45, and a liquid level WL2 is formed in the cover 46. On the other hand, when the operation is stopped, natural circulation occurs as shown by a dashed arrow in FIG. That is, the primary cooling water passes through the core 33, the inner case 35, the annular flow path 38, the lower opening of the casing 45 for the plenum, the pool water W around the outer cylindrical body 36, the lower opening of the outer case 34, and the core 33. When the pool water W having a high concentration of boric acid water is sequentially supplied to the core 33 at this time, the fission reaction is suppressed and the suspension is naturally stopped.
「発明が解決しようとする問題点」 しかしながら、前記従来例では、原子炉運転時の一次冷
却水の流路が、第３図に実線で示すように複雑な経路を
たどり、加熱状態及び冷却状態の一次冷却水を両筒体36
・37で往復させている等により、全体の構造が複雑とな
る傾向が避けられず、また、原子炉停止時には熱交換器
41における自然対流がほとんど期待できなくなる等の問
題点がある。本発明は、これらの問題点を有効に解決す
ることを目的としている。[Problems to be Solved by the Invention] However, in the above-mentioned conventional example, the flow path of the primary cooling water during the reactor operation follows a complicated path as shown by the solid line in FIG. Primary cooling water for both cylinders 36
・ There is an unavoidable tendency that the whole structure becomes complicated due to the reciprocating at 37, etc.
There is a problem that natural convection in 41 can hardly be expected. The present invention aims to effectively solve these problems.
「問題点を解決するための手段」 かかる目的を達成する手段として、圧力容器の内部のほ
う酸水からなるプール水中に、炉心及び一次冷却水を隔
離状態に収納し、ほう酸水の濃度により出力を制御する
軽水冷却型原子炉とする場合に、炉心の上部に接続され
一次冷却水の上昇流を導くライザ管と、該ライザ管の上
部に一次冷却水入り口を介して上部が接続される一次冷
却系用熱交換器と、該一次冷却系用熱交換器の下部に一
次冷却水出口を介して接続される一次冷却水出口用プレ
ナム部とその下方に位置して炉心の下部に対して接続さ
れる炉心入り口プレナム部とを形成する下部ケーシング
とを具備し、ライザ管の上部と下部ケーシングの下部と
に、一次冷却水とプール水との挿通を行なう上部境界と
下部境界とが配される構成を採用している。"Means for solving the problem" As means for achieving such an object, the core and the primary cooling water are stored in an isolated state in pool water consisting of boric acid water inside the pressure vessel, and the output depending on the concentration of boric acid water. In the case of a controlled light water cooling type reactor, a riser pipe connected to the upper part of the core to guide the upward flow of primary cooling water, and a primary cooling system in which the upper part is connected to the upper part of the riser pipe via a primary cooling water inlet System heat exchanger, a primary cooling water outlet plenum portion that is connected to the lower portion of the primary cooling system heat exchanger via a primary cooling water outlet, and is connected to the lower portion of the core located below the plenum portion. And a lower casing forming a core inlet plenum portion, and an upper boundary and a lower boundary for inserting the primary cooling water and the pool water are arranged at an upper portion of the riser pipe and a lower portion of the lower casing. Has adopted It
また、一次冷却水出口用プレナム部と炉心入り口プレナ
ム部との間に、一次冷却水を炉心入り口プレナム部に向
けて移送するポンプが介在状態に配され、該ポンプが、
一次冷却水出口用プレナム部の内部から吸引した一次冷
却水を駆動する駆動部と、該駆動部に接続され駆動状態
の一次冷却水を噴出するノズルと、該ノズルの噴出流に
よって一次冷却水を炉心入り口プレナム部に移送する拡
がり管部とを有するジェットポンプである構成を付加す
るようにしている。Further, between the primary cooling water outlet plenum portion and the core inlet plenum portion, a pump for transferring the primary cooling water toward the core inlet plenum portion is arranged in an intervening state, and the pump is
A drive section for driving the primary cooling water sucked from the inside of the plenum section for the primary cooling water outlet, a nozzle connected to the drive section for ejecting the primary cooling water in a driven state, and a jet flow of the nozzle for ejecting the primary cooling water. A jet pump having a spreading pipe portion that is transferred to the core inlet plenum portion is added.
「作用」 原子炉の運転状態にあっては、炉心で加熱された一次冷
却水が、炉心、ライザ管、熱交換器の上部まで上昇し、
熱交換器で冷却された一次冷却水が、熱交換器、一次冷
却水出口用プレナム部、炉心入り口プレナム部まで下降
する。したがって、自然対流とポンプの移送とによる循
環が行なわれる。"Operation" In the operating state of the reactor, the primary cooling water heated in the core rises to the upper part of the core, riser pipe, heat exchanger,
The primary cooling water cooled by the heat exchanger descends to the heat exchanger, the primary cooling water outlet plenum portion, and the core inlet plenum portion. Therefore, circulation is performed by natural convection and transfer by the pump.
その際に、ポンプがジェットポンプである場合には、一
次冷却水出口用プレナム部の一次冷却水の一部が、駆動
部によって駆動されてノズルから拡がり管部に噴出させ
られ、この際に一次冷却水出口用プレナム部の一次冷却
水をともなって拡がり管部から炉心入り口プレナム部に
移送される。At that time, when the pump is a jet pump, a part of the primary cooling water of the plenum portion for the primary cooling water outlet is driven by the driving unit and ejected from the nozzle to the spreading pipe portion, at which time the primary cooling water is ejected. The primary cooling water for the cooling water outlet plenum is transferred from the spreading pipe to the core inlet plenum.
一方、原子炉の停止時、ポンプ停止時にあっては、炉
心、ライザ管の上部まで上昇した一次冷却水が、上部境
界からプール水中に混入し、プール水中の下降流が、下
部境界を経由して炉心入り口プレナム部に混入する自然
対流による循環流が形成されて、ほう酸水が炉心に送り
込まれて原子炉が自然停止状態に導かれる。On the other hand, when the reactor is stopped or the pump is stopped, the primary cooling water that has risen to the top of the core and riser pipes mixes into the pool water from the upper boundary, and the downward flow in the pool water passes through the lower boundary. A natural convection mixed with the core inlet plenum forms a circulating flow, and boric acid water is sent to the core to guide the reactor to a natural shutdown state.
そして、ポンプがジェットポンプであって、これが停止
した場合には、一次冷却水出口用プレナム部から拡がり
管部を経由して炉心入り口プレナム部に至る流路の存在
によって、熱交換器を経由する循環路が残されたままと
なり、原子炉の冷却が促進される。If the pump is a jet pump and it stops, it passes through the heat exchanger due to the existence of a flow path from the primary cooling water outlet plenum portion to the core inlet plenum portion via the expansion pipe portion. The circulation path remains and the cooling of the reactor is accelerated.
「実施例」 第１図及び第２図に示すように、本実施例における軽水
冷却型原子炉は、圧力容器１が、鋼製とされるとともに
その上部に、胴部よりも直径を狭めた状態の機器搬入口
２が設けられている点、熱交換器（蒸気発生器）３の一
次冷却水入り口４が上部に、また、一次冷却水出口５が
下部に位置をずらして配設されている点、熱交換器３の
一次冷却水出口５と炉心６の上部との間に、これらを連
通するとともに一次冷却水出口５よりも下方に位置する
一次冷却水出口用プレナム部７が連設されている点、一
次冷却水出口用プレナム部７に一次冷却水を下方に付勢
するジェットポンプ（ポンプ）８が配設されている点、
炉心６の上部に一次冷却水入り口４に連通するライザ管
９が設けられるとともに、該ライザ管９の開口上部に、
熱交換器３と分離した状態とされ、かつ、上方に引き抜
き可能な上部プレナム用ケーシング10が配設されている
点等が、第３図及び第４図の従来例と著しく相異するも
のである。[Example] As shown in Figs. 1 and 2, in the light water cooling-type nuclear reactor in this example, the pressure vessel 1 was made of steel, and the diameter thereof was narrower in the upper portion than in the body portion. In this state, the heat exchanger (steam generator) 3 has a primary cooling water inlet 4 on the upper side, and a primary cooling water outlet 5 on the lower side. That is, between the primary cooling water outlet 5 of the heat exchanger 3 and the upper part of the reactor core 6, a primary cooling water outlet plenum portion 7 located below the primary cooling water outlet 5 is connected to connect them. That a jet pump (pump) 8 for urging the primary cooling water downward is disposed in the primary cooling water outlet plenum portion 7.
A riser pipe 9 communicating with the primary cooling water inlet 4 is provided on the upper part of the core 6, and an upper part of the opening of the riser pipe 9 is
This is significantly different from the conventional example shown in FIGS. 3 and 4 in that it is separated from the heat exchanger 3 and that an upper plenum casing 10 that can be pulled out is provided. is there.
これらの詳細について説明すると、前記圧力容器１は、
その壁の厚さが例えば数百mmで耐圧性を有する一体構造
とされるとともに、第１図に示すように、上部にのみ配
管貫通部が設けられ、また、機器搬入口２には、これを
閉塞するための半球状の上蓋11が取り付けられるととも
に、該上蓋11と前記上部プレナム用ケーシング10との間
に、キャップ12が介在させられており、該キャップ12
は、ボルト13等により上蓋11の内面に一体に取り付けら
れて、上蓋11と一緒に前記機器搬入口２から外されると
ともに、この中の圧力ガス室14に液面レベルWL２が形成
される構造である。Explaining these details, the pressure vessel 1 is
The wall has a thickness of, for example, several hundreds mm and has a pressure-resistant integrated structure, and as shown in FIG. A hemispherical upper lid 11 for closing the above is attached, and a cap 12 is interposed between the upper lid 11 and the upper plenum casing 10.
Is integrally attached to the inner surface of the upper lid 11 by a bolt 13 and the like, is removed from the equipment carry-in port 2 together with the upper lid 11, and a liquid level WL2 is formed in the pressure gas chamber 14 therein. Is.
前記熱交換器３は、圧力容器１の中に、第２図に示すよ
うにライザ管９の回りに等間隔で複数配設され、一次冷
却水と熱交換される二次冷却水の入り口15及び出口16
が、圧力容器１の上部鏡を貫通して設けられ、また、前
記一次冷却水出口用プレナム部７に挿入されたジェット
ポンプ８の出口付近と炉心６の下方との間が、炉心入り
口プレナム部17とされ、これらが下部プレナムケーシン
グ18により囲まれた構造である。なお、下部プレナムケ
ーシング18の下部開口と、圧力容器１の下鏡部付近との
間は、下部プレナム部19となっており、該下部プレナム
部19と炉心入り口プレナム部17との間は、一次系外のプ
ール水（ほう酸水）Ｗの緩やかな通過を許容するための
下部境界20とされている。A plurality of the heat exchangers 3 are arranged in the pressure vessel 1 at equal intervals around the riser pipe 9 as shown in FIG. And exit 16
Is provided so as to penetrate the upper mirror of the pressure vessel 1, and between the vicinity of the outlet of the jet pump 8 inserted in the primary cooling water outlet plenum portion 7 and the lower portion of the core 6 is a core inlet plenum portion. 17 and these are surrounded by the lower plenum casing 18. A lower plenum portion 19 is provided between the lower opening of the lower plenum casing 18 and the lower mirror portion of the pressure vessel 1, and a primary plenum portion is provided between the lower plenum portion 19 and the core inlet plenum portion 17. It is set as the lower boundary 20 for allowing the gentle passage of pool water (boric acid water) W outside the system.
前記炉心６の周囲には、炉心用ケーシング21が設けられ
て、その上部が前記ライザ管９に、その下部開口が炉心
入り口プレナム部17に、それぞれ連通状態に接続される
構造である。A core casing 21 is provided around the core 6, and an upper part of the core casing 21 is connected to the riser pipe 9 and a lower opening of the core casing 21 is connected to the core inlet plenum portion 17, respectively.
前記ポンプ８は、ジェットポンプが採用される。第１図
に示すように、下部プレナムケーシング18の外側等に
は、一次冷却水出口用プレナム部７を充満している一次
冷却水の一部を吸引し、加圧状態にしてジェットポンプ
８の駆動流として戻すための駆動部22が配される。駆動
部22は、第２図例では、各熱交換器３の間に４基設置さ
れている。さらに、ジェットポンプ８は、第１図に示す
ように、駆動部22に接続されて駆動状態の一次冷却水を
下部ケーシング18の内部において噴出するためのノズル
8aと、ノズル8aの先端近傍位置で一次冷却水出口用プレ
ナム部７と炉心入り口プレナム部17とを接続した状態の
拡がり管部8bとを有している。The pump 8 is a jet pump. As shown in FIG. 1, a part of the primary cooling water that fills the primary cooling water outlet plenum portion 7 is sucked to the outside of the lower plenum casing 18 or the like to bring the jet pump 8 into a pressurized state. A drive unit 22 is provided for returning as a drive flow. In the example of FIG. 2, four drive units 22 are installed between each heat exchanger 3. Further, as shown in FIG. 1, the jet pump 8 is a nozzle that is connected to the drive unit 22 and jets the primary cooling water in the driven state inside the lower casing 18.
8a, and a spreading pipe portion 8b in a state in which the primary cooling water outlet plenum portion 7 and the core inlet plenum portion 17 are connected at a position near the tip of the nozzle 8a.
これら拡がり管部8b等は、第２図に示すように、駆動部
22の１基当たり複数台設置されている。As shown in FIG. 2, the expanding pipe portion 8b and the like are driven by the drive portion.
22 units are installed in multiple units.
前記上部プレナム用ケーシング10は、その外径が機器搬
入口２の内径よりも小さく形成されて、機器搬入口２を
経由して上方へ引き抜き可能とされるとともに、その下
部開口付近には一次冷却水及びプール水Ｗの緩やかな通
過を許容するための上部境界23が設けられている。The casing 10 for the upper plenum has an outer diameter smaller than the inner diameter of the equipment inlet 2 and can be pulled upward through the equipment inlet 2, while primary cooling is performed near the lower opening. An upper boundary 23 is provided to allow gentle passage of water and pool water W.
なお、一次冷却水出口用プレナム部７には、圧力容器１
の上部鏡を貫通してプール水／純水置換系24が接続され
る。また、図中符号25はプール水冷却器、符号26は前記
上蓋11のエア抜き、符号27は、キャップ12・液面WL１・
液面WL２で形成される前記圧力ガス室11に外部より接続
されている圧力制御系及び蒸気逃し系統の接続管であ
る。In addition, the pressure vessel 1 is provided in the plenum 7 for the outlet of the primary cooling water.
A pool water / pure water substitution system 24 is connected through the upper mirror of the. In the figure, reference numeral 25 is a pool water cooler, reference numeral 26 is air bleeding from the upper lid 11, and reference numeral 27 is a cap 12 / liquid level WL1.
It is a connecting pipe of a pressure control system and a vapor relief system externally connected to the pressure gas chamber 11 formed by the liquid level WL2.
このような構造を有する軽水冷却型原子炉を運転状態と
すると、第１図に実線の矢印で示すような循環系とな
る。即ち、一次冷却水が炉心６、ライザ管９、一次冷却
水入り口４、熱交換器３、一次冷却水出口５、一次冷却
水出口用プレナム部７、ジェットポンプ８、炉心入り口
プレナム部17、炉心６を経由する循環流となり、このと
き、上部プレナム用ケーシング10の中に液面レベルWL１
が、また、キャップ12内の下面周辺部に液面レベルWL２
がそれぞれ形成され、液面レベルWL１は、水温に基づく
比重差により液面レベルWL２よりも若干上方に位置する
ことになる。このような循環流は、加熱状態の一次冷却
水が上昇流となるとともに、冷却された一次冷却水を下
降流とする単純な流れを構成する。When the light water cooling type reactor having such a structure is brought into an operating state, a circulation system shown by a solid arrow in FIG. 1 is formed. That is, the primary cooling water is the core 6, the riser pipe 9, the primary cooling water inlet 4, the heat exchanger 3, the primary cooling water outlet 5, the primary cooling water outlet plenum portion 7, the jet pump 8, the core inlet plenum portion 17, the core. 6 becomes the circulating flow, and at this time, the liquid level WL1
However, the liquid level WL2 around the lower surface of the cap 12
Are formed respectively, and the liquid level WL1 is located slightly above the liquid level WL2 due to the difference in specific gravity based on the water temperature. Such a circulating flow constitutes a simple flow in which the heated primary cooling water becomes an upward flow and the cooled primary cooling water becomes a downward flow.
一方、軽水冷却型原子炉を運転停止状態とすると、第１
図に破線の矢印で示すような自然循環が生じる。即ち、
一次冷却水が炉心６から、ライザ管９、上部境界23、ラ
イザ管９の周囲であるプール水Ｗ、下部プレナム部19、
下部境界20、炉心入り口プレナム部19、炉心６を経由す
る第１の循環流となるとともに、原子炉運転時と同様
に、熱交換器３を経由する第２の循環流も生じる。この
とき、ほう酸水の濃度の高いプール水Ｗが順次炉心６に
供給されて、当初の純水に混入することにより、核分裂
反応が抑制されて自然停止に導かれるのであるが、熱交
換器３を経由する循環流の存在により、圧力容器１の内
部を有効に活用した冷却が行なわれ、速やかに放射性物
質の核崩壊熱を除去し得ることになるものである。On the other hand, when the light water cooling type reactor is put into a shutdown state, the first
Natural circulation occurs as shown by the dashed arrows in the figure. That is,
Primary cooling water from the core 6, riser pipe 9, upper boundary 23, pool water W around the riser pipe 9, lower plenum portion 19,
In addition to the first circulating flow passing through the lower boundary 20, the core inlet plenum 19, and the core 6, the second circulating flow passing through the heat exchanger 3 is also generated as in the reactor operation. At this time, the pool water W having a high concentration of boric acid water is sequentially supplied to the core 6 and mixed into the initial pure water, so that the fission reaction is suppressed and the suspension is naturally stopped. Due to the existence of the circulation flow via the cooling vessel, the inside of the pressure vessel 1 is effectively used for cooling, and the nuclear decay heat of the radioactive material can be quickly removed.
また、原子炉運転時には、ジェットポンプ８による循環
の促進が行なわれるとともに、原子炉停止時には、ジェ
ットポンプ８の運転が停止しても、ジェットポンプ８に
おける拡がり管部8bが、第１図に示すように、一次冷却
水出口用プレナム部７と炉心入り口プレナム部17とを接
続しているとともに、拡がり管部8bの入口とノズル8aと
の間には、一次冷却水をともなって移送するための間隙
が空けられているので、熱交換器３を経由する循環流路
の構成を妨げることがない。Further, during the operation of the reactor, the jet pump 8 promotes the circulation, and when the reactor is stopped, even if the operation of the jet pump 8 is stopped, the expansion pipe portion 8b of the jet pump 8 is shown in FIG. As described above, the primary cooling water outlet plenum portion 7 and the core inlet plenum portion 17 are connected to each other, and the primary cooling water is transferred between the inlet of the spreading pipe portion 8b and the nozzle 8a. Since the gap is provided, the structure of the circulation flow path passing through the heat exchanger 3 is not hindered.
「発明の効果」 以上説明したように、本発明によれば、次のような優れ
た効果を奏することができる。"Effects of the Invention" As described above, according to the present invention, the following excellent effects can be achieved.
炉心の上部に接続され一次冷却水の上昇流を導くラ
イザ管と、ライザ管に上部が接続される熱交換器と、熱
交換器の下部に一次冷却水出口用プレナム部とその下方
に位置して炉心の下部に対して接続される炉心入り口プ
レナム部とを形成する下部ケーシングとを具備している
から、一次冷却水の上昇流が炉心からライザ管を経由し
て熱交換器の上部まで円滑に流れ、冷却された一次冷却
水の下降流が熱交換器から下部ケーシングの炉心入り口
プレナム部及び炉心入口プレナム部まで流れる循環路が
形成されて、原子炉運転時における一次冷却水を自然対
流作用を付加して円滑に循環させ、原子炉の構造の単純
化を図ることができる。A riser pipe connected to the upper part of the core to guide the upward flow of the primary cooling water, a heat exchanger whose upper part is connected to the riser pipe, a primary cooling water outlet plenum at the bottom of the heat exchanger and below it. And a lower casing that forms a core inlet plenum that is connected to the lower part of the core, and the upward flow of the primary cooling water flows smoothly from the core to the upper part of the heat exchanger via the riser pipe. A cooling water flowing downwardly from the heat exchanger to the core inlet plenum of the lower casing and a circulation path that flows from the heat exchanger to the core inlet plenum is formed, and the primary cooling water during the operation of the reactor undergoes natural convection. Can be added for smooth circulation and simplification of the structure of the nuclear reactor.
ポンプの停止に基づいてプール水を一次冷却水に混
入する際に、ライザ管の上部と下部ケーシングの下部と
の位置で挿通状態にし、自然対流に基づく循環によって
原子炉を自然状態に導くことができる。When the pool water is mixed into the primary cooling water due to the stop of the pump, it is inserted at the position of the upper part of the riser pipe and the lower part of the lower casing, and it is possible to guide the reactor to the natural state by circulation based on natural convection. it can.
一次冷却水出口用プレナム部と炉心入り口プレナム
部との間に、一次冷却水を下方に移送するジェットポン
プが配されるため、ポンプ停止時にあっても、拡がり管
部に基づいて熱交換器を経由する循環路が残されたまま
となり、プール水による冷却水の冷却作用に、熱交換器
を経由する循環による冷却作用が付加され、ほう酸水濃
度を高めることによる原子炉停止への誘導作用と、一次
冷却水の冷却作用との相乗作用とによって、原子炉の安
全性を向上させることができる。Since the jet pump that transfers the primary cooling water downward is arranged between the plenum part for the primary cooling water outlet and the plenum part for the core inlet, even when the pump is stopped, the heat exchanger is installed based on the expansion pipe part. The circulation path that is passed through remains, and the cooling effect of the circulation of water through the heat exchanger is added to the cooling effect of the cooling water by the pool water, and the effect of inducing reactor shutdown by increasing the concentration of boric acid water The safety of the nuclear reactor can be improved by the synergistic action with the cooling action of the primary cooling water.
第１図は本発明の軽水冷却型原子炉の一実施例を示す縦
断面図、第２図は第１図のII−II線矢視図、第３図は軽
水冷却型原子炉の従来例を示す縦断面図、第４図は第３
図のIV−IV線矢視図である。 １……圧力容器、２……機器搬入口、３……熱交換器、
４……一次冷却水入り口、５……一次冷却水出口、６…
…炉心、７……一次冷却水出口用プレナム部、８……ジ
ェットポンプ（ポンプ）、8a……ノズル、8b……拡がり
管部、９……ライザ管、17……炉心入り口プレナム部、
18……下部ケーシング、20……下部境界、22……駆動
部、23……上部境界、Ｗ……プール水。FIG. 1 is a longitudinal sectional view showing an embodiment of a light water cooling reactor of the present invention, FIG. 2 is a view taken along the line II-II of FIG. 1, and FIG. 3 is a conventional example of a light water cooling reactor. FIG. 4 is a vertical sectional view showing
FIG. 4 is a view taken along the line IV-IV in the figure. 1 ... Pressure vessel, 2 ... Equipment inlet, 3 ... Heat exchanger,
4 ... Primary cooling water inlet, 5 ... Primary cooling water outlet, 6 ...
… Core, 7 …… Primary cooling water outlet plenum, 8 …… Jet pump (pump), 8a …… Nozzle, 8b …… Spreading tube, 9 …… Riser tube, 17 …… Core inlet plenum,
18 …… Lower casing, 20 …… Lower boundary, 22 …… Driving part, 23 …… Upper boundary, W …… Pool water.
Claims (2)
プール水（Ｗ）中に、炉心（６）及び一次冷却水を隔離
状態に収納し、ほう酸水の濃度により出力を制御する軽
水冷却型原子炉であって、炉心の上部に接続され一次冷
却水の上昇流を導くライザ管（９）と、該ライザ管の上
部に一次冷却水入り口（４）を介して上部が接続される
一次冷却系用熱交換器（３）と、該一次冷却系用熱交換
器の下部に一次冷却水出口（５）を介して接続される一
次冷却水出口用プレナム部（７）とその下方に位置して
炉心の下部に対して接続される炉心入り口プレナム部
（１７）とを形成する下部ケーシング（１８）とを具備
し、ライザ管の上部と下部ケーシングの下部とに、一次
冷却水とプール水との挿通を行なう上部境界（２３）と
下部境界（２０）とが配されることを特徴とする軽水冷
却型原子炉。1. Light water in which the reactor core (6) and primary cooling water are stored in an isolated state in pool water (W) consisting of boric acid water inside a pressure vessel (1) and the output is controlled by the concentration of boric acid water. A cooling-type nuclear reactor, which is connected to an upper part of a core and is connected to an upper part of the riser pipe through a primary cooling water inlet (4) and a riser pipe (9) for guiding an ascending flow of the primary cooling water. A heat exchanger (3) for a primary cooling system, a plenum portion (7) for a primary cooling water outlet connected to a lower portion of the heat exchanger for a primary cooling system via a primary cooling water outlet (5), and below the plenum portion (7). A lower casing (18) positioned to form a core inlet plenum portion (17) connected to a lower portion of the core, the primary cooling water and the pool being provided in an upper portion of the riser pipe and a lower portion of the lower casing. An upper boundary (23) and a lower boundary (20) for inserting water Light water cooled nuclear reactor, characterized in that disposed.
プール水（Ｗ）中に、炉心（６）及び一次冷却水を隔離
状態に収納し、ほう酸水の濃度により出力を制御する軽
水冷却型原子炉であって、炉心の上部に接続され一次冷
却水の上昇流を導くライザ管（９）と、該ライザ管の上
部に一次冷却水入り口（４）を介して上部が接続される
一次冷却系用熱交換器（３）と、該一次冷却系用熱交換
器の下部に一次冷却水出口（５）を介して接続される一
次冷却水出口用プレナム部（７）とその下方に位置して
炉心の下部に対して接続される炉心入り口プレナム部
（１７）とを形成する下部ケーシング（１８）とを具備
し、ライザ管の上部と下部ケーシングの下部とに、一次
冷却水とプール水との挿通を行なう上部境界（２３）と
下部境界（２０）とが配され、一次冷却水出口用プレナ
ム部（７）と炉心入り口プレナム部（１７）との間に、
一次冷却水を炉心入り口プレナム部に向けて移送するポ
ンプ（８）が介在状態に配され、該ポンプが、一次冷却
水出口用プレナム部の内部から吸引した一次冷却水を駆
動する駆動部（２２）と、該駆動部に接続され駆動状態
の一次冷却水を噴出するノズル（８ａ）と、該ノズルの
噴出流によって一次冷却水を炉心入り口プレナム部に移
送する拡がり管部（８ｂ）とを有するジェットポンプで
あることを特徴とする軽水冷却型原子炉。2. Light water in which the core (6) and primary cooling water are stored in an isolated state in pool water (W) consisting of boric acid water inside the pressure vessel (1), and the output is controlled by the concentration of boric acid water. A cooling-type nuclear reactor, which is connected to an upper part of a core and is connected to an upper part of the riser pipe through a primary cooling water inlet (4) and a riser pipe (9) for guiding an ascending flow of the primary cooling water. A heat exchanger (3) for a primary cooling system, a plenum portion (7) for a primary cooling water outlet connected to a lower portion of the heat exchanger for a primary cooling system via a primary cooling water outlet (5), and below the plenum portion (7). A lower casing (18) positioned to form a core inlet plenum portion (17) connected to a lower portion of the core, the primary cooling water and the pool being provided in an upper portion of the riser pipe and a lower portion of the lower casing. An upper boundary (23) and a lower boundary (20) for inserting water To provided which, during the primary cooling water outlet plenum portion (7) core inlet plenum (17),
A pump (8) for transferring the primary cooling water toward the core inlet plenum is arranged in an intervening state, and the pump drives the primary cooling water sucked from the inside of the primary cooling water outlet plenum. ), A nozzle (8a) which is connected to the drive unit and ejects the primary cooling water in a driven state, and a spreading pipe portion (8b) which transfers the primary cooling water to the core inlet plenum portion by the jet flow of the nozzle. A light water cooled reactor characterized by being a jet pump.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP59241356A JPH0658424B2 (en) | 1984-11-15 | 1984-11-15 | Light water cooled reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP59241356A JPH0658424B2 (en) | 1984-11-15 | 1984-11-15 | Light water cooled reactor |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS61118694A JPS61118694A (en) | 1986-06-05 |
| JPH0658424B2 true JPH0658424B2 (en) | 1994-08-03 |
Family
ID=17073073
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP59241356A Expired - Lifetime JPH0658424B2 (en) | 1984-11-15 | 1984-11-15 | Light water cooled reactor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH0658424B2 (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO2008145542A1 (en) | 2007-05-25 | 2008-12-04 | Mann+Hummel Gmbh | Seal arrangement |
Family Cites Families (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4072563A (en) * | 1976-06-24 | 1978-02-07 | The Babcock & Wilcox Company | Industrial technique for an integral compact reactor |
-
1984
- 1984-11-15 JP JP59241356A patent/JPH0658424B2/en not_active Expired - Lifetime
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO2008145542A1 (en) | 2007-05-25 | 2008-12-04 | Mann+Hummel Gmbh | Seal arrangement |
Also Published As
| Publication number | Publication date |
|---|---|
| JPS61118694A (en) | 1986-06-05 |
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