JPH049692A - Condenser at isolation - Google Patents
Condenser at isolationInfo
- Publication number
- JPH049692A JPH049692A JP2110201A JP11020190A JPH049692A JP H049692 A JPH049692 A JP H049692A JP 2110201 A JP2110201 A JP 2110201A JP 11020190 A JP11020190 A JP 11020190A JP H049692 A JPH049692 A JP H049692A
- Authority
- JP
- Japan
- Prior art keywords
- steam
- condenser
- reactor
- isolation
- pipe
- 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
- 238000002955 isolation Methods 0.000 title claims abstract description 44
- UFHFLCQGNIYNRP-UHFFFAOYSA-N Hydrogen Chemical compound [H][H] UFHFLCQGNIYNRP-UHFFFAOYSA-N 0.000 claims abstract description 26
- 239000001257 hydrogen Substances 0.000 claims abstract description 17
- 229910052739 hydrogen Inorganic materials 0.000 claims abstract description 17
- 229910045601 alloy Inorganic materials 0.000 claims abstract description 14
- 239000000956 alloy Substances 0.000 claims abstract description 14
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 abstract description 30
- 238000009833 condensation Methods 0.000 abstract description 11
- 230000005494 condensation Effects 0.000 abstract description 11
- 239000011261 inert gas Substances 0.000 abstract description 10
- 238000001816 cooling Methods 0.000 abstract description 5
- 239000007789 gas Substances 0.000 abstract description 5
- 239000000463 material Substances 0.000 abstract description 3
- 230000005540 biological transmission Effects 0.000 abstract 3
- 238000000926 separation method Methods 0.000 abstract 1
- 239000002826 coolant Substances 0.000 description 8
- 238000003608 radiolysis reaction Methods 0.000 description 5
- KDLHZDBZIXYQEI-UHFFFAOYSA-N Palladium Chemical compound [Pd] KDLHZDBZIXYQEI-UHFFFAOYSA-N 0.000 description 4
- 230000007423 decrease Effects 0.000 description 4
- MYMOFIZGZYHOMD-UHFFFAOYSA-N Dioxygen Chemical compound O=O MYMOFIZGZYHOMD-UHFFFAOYSA-N 0.000 description 3
- 230000000694 effects Effects 0.000 description 3
- 229910000990 Ni alloy Inorganic materials 0.000 description 2
- 238000005253 cladding Methods 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 239000000446 fuel Substances 0.000 description 2
- 150000002431 hydrogen Chemical class 0.000 description 2
- 238000009434 installation Methods 0.000 description 2
- 239000002689 soil Substances 0.000 description 2
- FYYHWMGAXLPEAU-UHFFFAOYSA-N Magnesium Chemical compound [Mg] FYYHWMGAXLPEAU-UHFFFAOYSA-N 0.000 description 1
- 229910000831 Steel Inorganic materials 0.000 description 1
- 229910001069 Ti alloy Inorganic materials 0.000 description 1
- QCWXUUIWCKQGHC-UHFFFAOYSA-N Zirconium Chemical compound [Zr] QCWXUUIWCKQGHC-UHFFFAOYSA-N 0.000 description 1
- QVGXLLKOCUKJST-UHFFFAOYSA-N atomic oxygen Chemical compound [O] QVGXLLKOCUKJST-UHFFFAOYSA-N 0.000 description 1
- 238000006243 chemical reaction Methods 0.000 description 1
- 229910001882 dioxygen Inorganic materials 0.000 description 1
- 230000005484 gravity Effects 0.000 description 1
- 125000004435 hydrogen atom Chemical group [H]* 0.000 description 1
- 230000010354 integration Effects 0.000 description 1
- OTTJBKQXLHGKAI-UHFFFAOYSA-N iron nickel titanium Chemical compound [Ti][Fe][Ni][Ti] OTTJBKQXLHGKAI-UHFFFAOYSA-N 0.000 description 1
- IXQWNVPHFNLUGD-UHFFFAOYSA-N iron titanium Chemical compound [Ti].[Fe] IXQWNVPHFNLUGD-UHFFFAOYSA-N 0.000 description 1
- DOARWPHSJVUWFT-UHFFFAOYSA-N lanthanum nickel Chemical compound [Ni].[La] DOARWPHSJVUWFT-UHFFFAOYSA-N 0.000 description 1
- 229910052749 magnesium Inorganic materials 0.000 description 1
- 239000011777 magnesium Substances 0.000 description 1
- 238000004137 mechanical activation Methods 0.000 description 1
- 239000000203 mixture Substances 0.000 description 1
- 229910001000 nickel titanium Inorganic materials 0.000 description 1
- 239000001301 oxygen Substances 0.000 description 1
- 229910052760 oxygen Inorganic materials 0.000 description 1
- 229910052763 palladium Inorganic materials 0.000 description 1
- 239000002245 particle Substances 0.000 description 1
- 230000000630 rising effect Effects 0.000 description 1
- 239000010959 steel Substances 0.000 description 1
- 229910052726 zirconium Inorganic materials 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）
本発明はたとえば冷却材喪失事故時において原子炉格納
容器内を冷却するのに好適な隔離時復水器に関する。DETAILED DESCRIPTION OF THE INVENTION [Object of the Invention] (Industrial Application Field) The present invention relates to an isolation condenser suitable for cooling the inside of a nuclear reactor containment vessel, for example, in the event of a loss of coolant accident.
（従来の技術）
隔離時復水器は原子炉を隔離し７た場合、原子炉圧力容
器内の過圧防止及び冷却材喪失事故時の原子炉格納、容
器内の過圧防１−の２つの目的で用いられている。第４
図を参照しながら隔離時復水器の構造・動作例を説明す
る。(Prior art) Isolation condensers isolate the reactor, prevent overpressure inside the reactor pressure vessel, contain the reactor in the event of a loss of coolant accident, and prevent overpressure inside the vessel. It is used for one purpose. Fourth
An example of the structure and operation of an isolation condenser will be explained with reference to the drawings.
第４図は原子炉格納容器内の原子炉圧力容器と隔離時復
水器プール内の復水器との配管接続系路を示した配管系
統図である。FIG. 4 is a piping system diagram showing a piping connection system between the reactor pressure vessel in the reactor containment vessel and the condenser in the isolation condenser pool.
図中符号１は原子炉格納容器を示しＣおり、この原子炉
圧力容器内には炉心２を収容し、た原子炉圧力容器３が
格納されている。原子炉圧力容器３には主蒸気配管４が
接続され、この１蒸気配ｈ・４には主蒸気隔離弁５が設
けらオ］ている。１蒸気配管４には主蒸気隔離弁５の入
Ｉコ側から分岐］５．Ｃ蒸気配管６が接続され、この蒸
気配管６には蒸気導入弁７が接続されている。蒸気配管
６の下流側は隔離時復水器８の蒸気室９に接続さねてい
る。In the figure, reference numeral 1 indicates a reactor containment vessel, in which a reactor pressure vessel 3 containing a reactor core 2 is housed. A main steam pipe 4 is connected to the reactor pressure vessel 3, and a main steam isolation valve 5 is provided in this steam pipe 4. 1 branch to the steam piping 4 from the inlet side of the main steam isolation valve 5]5. A C steam pipe 6 is connected to the steam pipe 6, and a steam introduction valve 7 is connected to the steam pipe 6. The downstream side of the steam pipe 6 is connected to the steam chamber 9 of the isolation condenser 8.
隔離時復水器８は原子炉格納容器１−の上部に設けられ
た隔離時復水器ブール１０のブール水１１中に浸漬され
ている。隔離時復水器８の水室１２は原子炉圧力容器３
に戻り弁１４を有する凝縮水戻り管１３を介し、で接続
されている。なお、符号１５は復水器８内の伝熱管で、
１６はブール１１の蒸気排出管である。The isolation condenser 8 is immersed in boule water 11 of an isolation condenser boule 10 provided at the upper part of the reactor containment vessel 1-. The water chamber 12 of the isolation condenser 8 is connected to the reactor pressure vessel 3
The condensed water return pipe 13 having a return valve 14 is connected to the condensate water return pipe 13 . In addition, the code|symbol 15 is a heat exchanger tube in the condenser 8,
16 is a steam exhaust pipe of the boule 11.
ところで、主蒸気隔離弁５を閉じて原子炉圧力容器３を
隔離した場合、炉心２は崩壊熱を発生］、７続けるため
、放置しておくと原ｆ炉ｐ＋−力容器３内の圧力は上昇
してり、まう。ぞこで、隔離時復水器８を用いて原子炉
圧力容器３内の蒸気を凝縮Ｉ２５、圧力の１−昇を抑え
る事が行われる３３すなわち、原子炉圧力容器：３内の
圧力が上ケ１゜たら凝縮水戻り弁１４を開け、主蒸気配
管４から蒸気配管６を通して蒸気を隔離時復水器８の蒸
気室９に導く。ただし５、蒸気導入弁７は通常運転時１
．Ｓおいて開状態にある。蒸気は蒸気室９から隔離時復
水器８の伝熱管１５を下降し、その間に隔離時復水器ブ
ー、ル１０のプール水１１に熱を与えることにより一部
が凝縮し、て水になり、その水は隔離時復水器８の水室
１２内に入り、さらに重力により凝縮水戻り管１３を通
って再び原ｒ・炉圧力容器３内に戻る。By the way, if the main steam isolation valve 5 is closed and the reactor pressure vessel 3 is isolated, the reactor core 2 will continue to generate decay heat, so if left as it is, the pressure inside the reactor pressure vessel 3 will be It's rising, okay. At this point, the isolation condenser 8 is used to condense the steam in the reactor pressure vessel 3, suppressing a 1-rise in pressure.33 That is, when the pressure in the reactor pressure vessel 3 increases When the temperature reaches 1°, the condensed water return valve 14 is opened and steam is introduced from the main steam pipe 4 through the steam pipe 6 to the steam chamber 9 of the isolation condenser 8. However, 5, steam introduction valve 7 is 1 during normal operation.
．． It is in an open state at S. The steam descends from the steam room 9 through the heat transfer tube 15 of the isolation condenser 8, and during that time it gives heat to the pool water 11 of the isolation condenser 10, causing a portion to condense and turn into water. The water then enters the water chamber 12 of the isolation condenser 8 and returns to the reactor pressure vessel 3 again through the condensed water return pipe 13 due to gravity.
なお、蒸気の凝縮による潜熱の放出でゾール水１１の温
度は徐々に」−屏しやがて沸騰を開始するが、ぞの際発
生ずる蒸気は蒸気排出管１６から大気ｌｐ ｇ（７゜放
出される。Furthermore, due to the release of latent heat due to the condensation of steam, the temperature of the sol water 11 gradually decreases and eventually starts to boil, but the steam generated at this time is released from the steam exhaust pipe 16 to the atmosphere lpg (7°). .
以上が原子炉隔離時の動作であるが、冷却材喪失事故時
において、原子炉圧力容器３内の蒸気は原子炉格納容器
１内の不活性ガス雰囲気１１月Ｊ放出される１、特に主
蒸気配管４が原子炉圧力容器：３と蒸気配管６の間で破
断（、た場合を想定すると、蒸気は−ｙ１、原子炉格納
容器１の不活性ガス雰囲気中に放出され、その後、蒸気
配管６を通−）で隔離時復水器８に流入するこＪになる
１、従・ｉて、隔離時復水器８１：流入４る蒸気中１：
は不活性ガスが含まれていることになる３、また、水の
放射線分解により発生するガスも含まれる。このため、
隔離時復水器８の伝熱管１５の内側の凝縮熱伝達は劣化
ｊ１、蒸気凝縮はいちじるしく妨げられる。なお、基本
的な動作は原子炉隔離時と同様である。The above is the operation during reactor isolation. In the event of a loss of coolant accident, the steam in the reactor pressure vessel 3 is released into the inert gas atmosphere in the reactor containment vessel 1, especially the main steam. Assuming that the pipe 4 breaks between the reactor pressure vessel 3 and the steam pipe 6, steam is released into the inert gas atmosphere of the reactor containment vessel 1, and then the steam pipe 6 The steam flowing into the isolation condenser 8 through -) flows into the isolation condenser 8.
This means that inert gases are included3, and gases generated by radiolysis of water are also included. For this reason,
During isolation, condensation heat transfer inside the heat transfer tubes 15 of the condenser 8 deteriorates j1, and steam condensation is significantly hindered. The basic operation is the same as during reactor isolation.
（発明が解決しよ・）とする課題）
隔離時復水器８に流入する混合蒸気中には前述し、たよ
うに水の放射線分解により発生する水素（ｌ（、）と酸
素（０２）および燃料被覆管材のジルコニウノ、（Ｚｒ
）と水（Ｈ２Ｏ）との反応により発生ずるＨ２志Ｏ２等
が含まれでいる。とくに、水の放射線分解等で発生する
Ｈ７と０．は崩壊熱の積分により発生量が多くなる。例
えばＢＷＲ５（１１０７ｉＫＷｅ）で１時間後のＨ２の
生成モル数を考えると約１０００となる。その他、Ｚ
ｒ −ｉ４２０反応では安全審査で使用する値として
有効発熱部の燃料被覆管中のＺｒ量のうち０４７３％が
反応すると考えられている。このため、これらＮ７、Ｈ
７、Ｏ□によって隔離時復水器８の伝熱管１５０）内側
の凝縮熱伝達は劣化し、蒸気凝縮量が減少する。(Problem to be solved by the invention) As mentioned above, the mixed steam flowing into the isolation condenser 8 contains hydrogen (l(,)) and oxygen (02) generated by radiolysis of water. and zirconium for fuel cladding, (Zr
) and water (H2O). In particular, H7 and 0.0 generated by radiolysis of water, etc. The amount generated increases due to the integration of decay heat. For example, considering the number of moles of H2 produced after 1 hour in BWR5 (1107iKWe), it is approximately 1000. Others, Z
In the r-i420 reaction, it is considered that 0473% of the Zr amount in the fuel cladding in the effective exothermic part reacts, as a value used in safety examinations. Therefore, these N7, H
7. Due to O□, the condensation heat transfer inside the heat transfer tube 150) of the condenser 8 during isolation deteriorates, and the amount of steam condensed decreases.
冷却材喪失事故時においては、原子炉格納容器１内へ放
出された蒸気は原子炉格納容器Ｊ内の不活性ガスＮ、と
、水の放射線分解によって生じた１−１２、Ｏ，と混合
する。その後、これらのガスを含んだ蒸気は蒸気配管６
内を通り隔離時復水器８の蒸気室９へ流入する。−旦、
蒸気室９内へ流入【７た不活性ガスなどを含んだ混合蒸
気は隔離時復水器８の伝熱管１５内を下降しブール１０
のプール水１１に熱を与えるため凝縮して水になる。し
かＬながら、この場合、水素ガスが含まれでいるため、
隔離時復水器８の伝熱管１５内での凝縮熱伝達が悪くな
り、蒸気凝縮量が減少する。し７たが一部で、原子炉圧
力容器１及び原子炉圧力容器３内の圧力減少が悪化する
ため、水素ガスを取り除いて隔離時復水器８の伝熱管＋
５内Ｃの熱伝達率を良好に１７なければならない課題が
ある。In the event of a loss of coolant accident, the steam released into the reactor containment vessel 1 mixes with the inert gas N in the reactor containment vessel J and 1-12, O, produced by radiolysis of water. . After that, the steam containing these gases is passed through the steam pipe 6.
and flows into the steam chamber 9 of the isolation condenser 8. -dan,
The mixed steam containing inert gas, etc. flowing into the steam chamber 9 descends through the heat transfer tube 15 of the isolation condenser 8 and flows into the boiler 10.
In order to give heat to the pool water 11, it condenses and becomes water. However, in this case, hydrogen gas is included, so
During isolation, condensation heat transfer within the heat transfer tubes 15 of the condenser 8 deteriorates, and the amount of steam condensed decreases. However, in some cases, the pressure reduction inside the reactor pressure vessel 1 and the reactor pressure vessel 3 becomes worse, so hydrogen gas is removed and the heat exchanger tube + of the isolation condenser 8 is removed.
There is a problem that the heat transfer coefficient of 5C must be kept good.
本発明は上記課題を解決するためになされたもので、隔
離時復水器の蒸気室内で水素ガスを取り除いて伝熱管内
での熱伝達率を良好にし２、蒸気凝縮量を増大させ、原
子炉圧力容器および原子炉格納容器内の圧力−１−封を
低減して安全に原子炉を停止さぜることができる隔離時
復水器を提供することにある３、
［発明の構成］
（課題を解決するための手段）
本発明は原子炉格納容器のに方に設けられた隔離時復水
器プール内に設置する隔離時復水器において、前記復水
器の蒸気室内に水素（Ｈ２）を吸蔵する水素吸蔵合金を
設け−Ｃなることをと特徴とオる。The present invention was made to solve the above problems, and it improves the heat transfer coefficient in the heat transfer tubes by removing hydrogen gas in the steam chamber of the isolation condenser, increases the amount of steam condensed, and improves the heat transfer coefficient in the heat transfer tubes. An object of the present invention is to provide an isolation condenser that can safely shut down a nuclear reactor by reducing the pressure inside the reactor pressure vessel and the reactor containment vessel. Means for Solving the Problems) The present invention provides an isolation condenser installed in an isolation condenser pool provided on the side of a reactor containment vessel, in which hydrogen (H2 ) is provided with a hydrogen storage alloy that absorbs -C.
（作 用）
たとλば原子炉の冷却材喪失事故時においで、原子炉格
納容器内へ放出された蒸気は原ｒ・炉格納容器内の不活
性ガス（Ｎ、）および水の放射線分解等によ、−）で発
生ずる水素ガス（Ｈ２） 、酸素ガス（０２）の混合蒸
気となる。この混合蒸気は蒸気配管を通り隔離時復水器
の蒸気室内−・、４流れ込む。(Function) For example, in the event of a loss of coolant accident in a nuclear reactor, steam released into the reactor containment vessel undergoes radiolysis, etc. of inert gas (N) and water in the reactor containment vessel. It becomes a mixed vapor of hydrogen gas (H2) and oxygen gas (02) generated at y, -). This mixed steam flows through the steam pipe into the steam chamber of the isolation condenser.
この際、水素ガス（Ｈ７）を吸蔵する合金を冷却材喪失
事故時の雰囲気（圧力約２〜３ ｋｇ、、／ａ］ｆ ）
で水素ガス（ｉ（２）を吸蔵Ａるように蒸気室内に設け
ることによって、蒸気室に流入した水素ガスは１、記合
金に吸蔵され、混合蒸気の圧力は減少１′る。At this time, the alloy that stores hydrogen gas (H7) is placed in the atmosphere at the time of the loss of coolant accident (pressure approximately 2 to 3 kg, /a]f).
By arranging hydrogen gas (i(2)) in the steam chamber so as to store it, the hydrogen gas flowing into the steam chamber is stored in the alloy described above, and the pressure of the mixed vapor decreases by 1'.
これにより伝熱管内を流れる蒸気の凝縮熱伝達が良好と
なり、蒸気凝縮量が多くなる。この凝縮した水は自重に
より凝縮水戻り管を通り、再び原ｒ炉圧力容器内へ戻さ
れる。This improves the condensation heat transfer of the steam flowing inside the heat transfer tube, increasing the amount of steam condensed. This condensed water passes through the condensed water return pipe due to its own weight and is returned to the reactor pressure vessel.
（実施例）
第１図から第３図を参照し、なから本発明に係る隔離時
復水器の−・実施例を説明する。(Embodiment) With reference to FIGS. 1 to 3, an embodiment of the isolation condenser according to the present invention will be described.
第１−図においで符号２０は本発明の実施例における隔
離時復水器を示し、ており、この復水器２０は土部に蒸
気室２１が、中間部に多数本の伝熱管２２が、下部に氷
室２３が連結されたものからなっており、とくに蒸気室
２１内には水素を吸蔵４る水素吸蔵合金を収容し、たバ
スｂット２４が吊首さねでいる９、このバリッド２４は
第２図に部分的に拡大して示したようにたさえばスラン
レス鋼など６） ｂ、ｌ ＃ｈｌで網目状容器に形成さ
ｔｌで通気性４二有し、−１一端間１１Ｃ１取（・］け
フランジ２５が接続されている。７取付（す°フランジ
２５の上面はカバー２６ご密閉さ第１る。Ｊう（、−な
っている５、このバスゲット２４は第：３図１５示した
蒸気室２１の十部２７から吊り丁げられたボルト２８に
孔ハを挿し、込んでナツト３０で締め何重で蒸気室２１
内（。In Fig. 1, the reference numeral 20 indicates an isolation condenser in an embodiment of the present invention, and this condenser 20 has a steam chamber 21 in the soil part and a large number of heat transfer tubes 22 in the middle part. It consists of an ice chamber 23 connected to the lower part, and in particular, the steam chamber 21 houses a hydrogen storage alloy that stores hydrogen, and a bath 24 hangs thereon. Valid 24 is made of slanless steel or the like, as shown in a partially enlarged view in FIG. 11C1 take (・] flange 25 is connected. 7 Installation (the upper surface of flange 25 is sealed with cover 26). 3. Insert the hole in the bolt 28 hanging from the tenth part 27 of the steam chamber 21 shown in FIG.
Inside (.
着脱自在１、゛吊りＦげられる。上蓋２７は蒸気室２１
のフランジ３１にボルト３２で気密（、”〜ねじ止めさ
れる１、ここで、バスフット２４内に収容４る水素吸蔵
合金はたとえばパラジウＡ、パラジウム黒、鉄 チタン
合金、ランタン−ニッケル合金５マグネシウム ニッケ
ル合金、鉄−ニッケル チタン合金などの粒子または小
塊状粒子を使用」る５、吉くにパラジウム黒は水素の吸
蔵能力が高いので望まｊ、い３、しかして、」１実流側
においでは冷却材喪失事故時に原子力格納容器１内に放
出さり、 ｉ；活性ガスなどと混合された蒸気は蒸気配
管６を通り隔離時復水器２Ｇの蒸気室２１内へ流入され
る９、この蒸気室２１内には冷却材喪失事故時の原子力
内部条件と同様な圧力（２〜３ ｋｇ／ａＩ）程度で（
Ｈ２）を吸蔵する性質をも一′）ように・つくられた（
Ｈ２）吸蔵合金がバスケット２４内に収容されであるた
め、蒸気室２１内へ流入し、た不活性ガス混合蒸気中か
ら選択的ｊ、コ水素（ｉ（、）を吸蔵する。し、たが−
）て、伝熱管２２内での凝縮熱伝達は良好となり、蒸気
凝縮量が増大する。凝縮され水となったものはその自重
で凝縮水戻り管１３を通り再び原子炉圧力容器３内へ戻
される。Detachable 1. Can be hung. The upper lid 27 is the steam chamber 21
The hydrogen storage alloy housed in the bath foot 24 is, for example, palladium A, palladium black, iron titanium alloy, lanthanum-nickel alloy 5 magnesium. It is desirable to use particles or small lumps of nickel alloy, iron-nickel titanium alloy, etc. 5. It is preferable to use palladium black because it has a high hydrogen storage capacity. 3. However, 1. Cooling on the actual flow side During a material loss accident, steam is released into the nuclear containment vessel 1 and mixed with active gas etc. passes through the steam pipe 6 and flows into the steam chamber 21 of the isolation condenser 2G. The internal pressure (2 to 3 kg/aI) similar to the internal conditions of a nuclear power plant during a loss of coolant accident (
It also has the property of occluding H2).
H2) Since the storage alloy is accommodated in the basket 24, it flows into the steam chamber 21 and selectively stores hydrogen (i(,)) from the inert gas mixture vapor. −
), the condensation heat transfer within the heat transfer tube 22 becomes good, and the amount of steam condensed increases. The condensed water is returned to the reactor pressure vessel 3 through the condensed water return pipe 13 due to its own weight.
この実施例によれば、」−記効果のほかにバスケット取
付はフランジに水素吸蔵合金を収容［７たバスリットが
取りついているため、上部フランジを取り外すことによ
ってバスケットも容易に取り外ずことかできる。このこ
とによりバスケット内に収容した水素吸蔵合金の取り替
え作業を簡単に行うことができる効果もある３、
「発明の効果］
本発明によれば原子炉格納容器内で不活性ガスなどと混
合された蒸気は蒸気室内に設Ｕられｔ、−水素吸蔵合金
で水素ガス（Ｈ２）が除去されて伝熱管内での凝縮熱の
伝達が良好となり、蒸気凝縮量を増大させる。凝縮され
た水はその自重で凝縮水戻り管を通り原ｒ炉圧力容器内
へ戻される。ぞの結果、原子炉内の冷却効果が高まり、
崩壊熱を防ぎ、圧力土性をおさえることができ、しかも
、冷却材喪失事故時においでも機械的な作動もなく安全
に原子炉を停」１゛できる。According to this embodiment, in addition to the above effects, the basket is attached with a bath slit that houses the hydrogen storage alloy in the flange, so the basket can be easily removed by removing the upper flange. . This has the effect of making it easier to replace the hydrogen storage alloy housed in the basket3. ``Effects of the Invention'' According to the present invention, hydrogen storage alloys that are mixed with inert gas etc. in the reactor containment vessel can be easily replaced. The steam is installed in the steam chamber, and hydrogen gas (H2) is removed by a hydrogen storage alloy, which improves the transfer of condensation heat within the heat transfer tube and increases the amount of steam condensed.The condensed water is Under its own weight, the condensed water passes through the return pipe and returns to the reactor pressure vessel.As a result, the cooling effect inside the reactor increases,
It is possible to prevent decay heat and suppress pressure-induced soil properties, and even in the event of a loss of coolant accident, the reactor can be safely shut down without any mechanical activation.
第１図は本発明（Ｓ係る隔離時復水器の〜実施例を線図
的に示す縦断面図、第２図は第１図にお１Ｊる水素吸蔵
合金の取付は状態を示ず縦断面図、第３図は第１５図に
おりるバスケットの取イ」り金具を示す縦断面図、第４
図は従来の隔離時復水器を説明するだめの配管系統図で
ある。
１、・・・原子炉格納容器、２・・・炉心、３・・・原
子炉圧力容器、４・・・主蒸気配管、５・・・主蒸気隔
離弁、（５・・・蒸気配管、７・・・蒸気導入弁、８・
・・隔離時復水器。
９・２１・・・蒸気室、１０・・・隔離時復水器ブ・−
ル、１１・・・ブー・ル水、１２・２３・・・水室、１
３・・・凝縮水戻り管、 １４・・・戻り弁、１５・２
２・・・伝熱管、１６・・・蒸気排出管、２４・・・バ
スケット、２５・・・取付はフランジ、２６・・・カバ
ー２７・・・上蓋、２８・３２・・・ボルト、２９・・
・孔、３０・・・ナツト。
３１・・・７ランジ
（８７３３）代理人弁理士 猪 股 祥 晃（他１名）
第
図
第
図Fig. 1 is a vertical cross-sectional view diagrammatically showing an embodiment of the isolation condenser according to the present invention (S), and Fig. 2 is a longitudinal cross-sectional view diagrammatically showing the installation state of the hydrogen storage alloy 1J in Fig. 1. 3 is a vertical cross-sectional view showing the handle of the basket shown in FIG. 15, and 4 is a top view.
The figure is a piping system diagram illustrating a conventional isolation condenser. DESCRIPTION OF SYMBOLS 1...Reactor containment vessel, 2...Reactor core, 3...Reactor pressure vessel, 4...Main steam piping, 5...Main steam isolation valve, (5...Steam piping, 7...Steam introduction valve, 8.
...Isolation condenser. 9/21... Steam room, 10... Isolation condenser block -
Le, 11...Boo Le water, 12.23...Water chamber, 1
3... Condensed water return pipe, 14... Return valve, 15.2
2...Heat transfer tube, 16...Steam discharge pipe, 24...Basket, 25...Flange mounting, 26...Cover 27...Top lid, 28.32...Bolts, 29.・
・Hole, 30...Natsuto. 31...7 Ranji (8733) Representative Patent Attorney Yoshiaki Inomata (1 other person)
Figure Figure
Claims (1)
内に設置する隔離時復水器において、前記復水器の蒸気
室内に水素を吸蔵する水素吸蔵合金を設けてなることを
特徴とする隔離時復水器。An isolation condenser installed in an isolation condenser pool provided above a reactor containment vessel, characterized in that a hydrogen storage alloy for storing hydrogen is provided in the steam chamber of the condenser. condenser when isolated.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP2110201A JPH049692A (en) | 1990-04-27 | 1990-04-27 | Condenser at isolation |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP2110201A JPH049692A (en) | 1990-04-27 | 1990-04-27 | Condenser at isolation |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH049692A true JPH049692A (en) | 1992-01-14 |
Family
ID=14529615
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP2110201A Pending JPH049692A (en) | 1990-04-27 | 1990-04-27 | Condenser at isolation |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH049692A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US6129789A (en) * | 1995-12-21 | 2000-10-10 | Kabushiki Kaisha Toyoda Jidoshokki Seisakusho | Surface treatment method of hydrogen absorbing alloy |
-
1990
- 1990-04-27 JP JP2110201A patent/JPH049692A/en active Pending
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US6129789A (en) * | 1995-12-21 | 2000-10-10 | Kabushiki Kaisha Toyoda Jidoshokki Seisakusho | Surface treatment method of hydrogen absorbing alloy |
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