JPH0327879B2 - - Google Patents
Info
- Publication number
- JPH0327879B2 JPH0327879B2 JP58240534A JP24053483A JPH0327879B2 JP H0327879 B2 JPH0327879 B2 JP H0327879B2 JP 58240534 A JP58240534 A JP 58240534A JP 24053483 A JP24053483 A JP 24053483A JP H0327879 B2 JPH0327879 B2 JP H0327879B2
- Authority
- JP
- Japan
- Prior art keywords
- gas
- exhaust gas
- gaseous waste
- activated carbon
- hydrogen
- 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
- 239000007789 gas Substances 0.000 claims description 73
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 claims description 62
- UFHFLCQGNIYNRP-UHFFFAOYSA-N Hydrogen Chemical compound [H][H] UFHFLCQGNIYNRP-UHFFFAOYSA-N 0.000 claims description 31
- 239000010795 gaseous waste Substances 0.000 claims description 28
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 25
- QVGXLLKOCUKJST-UHFFFAOYSA-N atomic oxygen Chemical compound [O] QVGXLLKOCUKJST-UHFFFAOYSA-N 0.000 claims description 18
- 239000001301 oxygen Substances 0.000 claims description 18
- 229910052760 oxygen Inorganic materials 0.000 claims description 18
- 230000006798 recombination Effects 0.000 claims description 11
- 238000005215 recombination Methods 0.000 claims description 11
- 239000001257 hydrogen Substances 0.000 claims description 9
- 229910052739 hydrogen Inorganic materials 0.000 claims description 9
- MYMOFIZGZYHOMD-UHFFFAOYSA-N Dioxygen Chemical compound O=O MYMOFIZGZYHOMD-UHFFFAOYSA-N 0.000 claims description 8
- 229910001882 dioxygen Inorganic materials 0.000 claims description 8
- 230000002285 radioactive effect Effects 0.000 claims description 8
- 239000000284 extract Substances 0.000 claims description 2
- 238000007599 discharging Methods 0.000 claims 1
- 238000003608 radiolysis reaction Methods 0.000 description 4
- 238000009835 boiling Methods 0.000 description 3
- 238000006243 chemical reaction Methods 0.000 description 3
- 238000010586 diagram Methods 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 230000002238 attenuated effect Effects 0.000 description 1
- 238000009833 condensation Methods 0.000 description 1
- 230000005494 condensation Effects 0.000 description 1
- 239000000498 cooling water Substances 0.000 description 1
- 230000008878 coupling Effects 0.000 description 1
- 238000010168 coupling process Methods 0.000 description 1
- 238000005859 coupling reaction Methods 0.000 description 1
- 230000003247 decreasing effect Effects 0.000 description 1
- 238000001514 detection method Methods 0.000 description 1
- 230000006866 deterioration Effects 0.000 description 1
- 238000010438 heat treatment Methods 0.000 description 1
- 238000005259 measurement Methods 0.000 description 1
- 238000012544 monitoring process Methods 0.000 description 1
- 238000002360 preparation method Methods 0.000 description 1
- 230000003134 recirculating effect Effects 0.000 description 1
- 238000001179 sorption measurement Methods 0.000 description 1
- 230000001988 toxicity Effects 0.000 description 1
- 231100000419 toxicity Toxicity 0.000 description 1
- 238000011144 upstream manufacturing Methods 0.000 description 1
- 239000002912 waste gas Substances 0.000 description 1
- 239000002699 waste material Substances 0.000 description 1
Landscapes
- Separation Using Semi-Permeable Membranes (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Description
【発明の詳細な説明】
［発明の技術分野］
本発明は、沸騰水型原子力発電所において、復
水器から抽出した気体廃棄物を処理する気体廃棄
物処理装置に関する。DETAILED DESCRIPTION OF THE INVENTION [Technical Field of the Invention] The present invention relates to a gaseous waste treatment device for treating gaseous waste extracted from a condenser in a boiling water nuclear power plant.
［背景技術の問題点］
沸騰水型原子力発電所の気体廃棄物処理系にて
処理対象となる気体廃棄物は、主に原子炉１次系
からの放射性ガス、すなわち主復水器から抽出さ
れたものであり、従来第１図に示すような気体廃
棄物処理装置により減害処理された後、環境へ放
出されていた。[Problems in the background art] The gaseous waste to be treated in the gaseous waste treatment system of a boiling water nuclear power plant is mainly radioactive gas from the reactor primary system, that is, extracted from the main condenser. Conventionally, waste gases have been treated to reduce their toxicity using gaseous waste treatment equipment as shown in Figure 1, and then released into the environment.
すなわち、原子炉で発生した非凝縮性ガスや主
復水器にリークインした空気等の気体廃棄物は、
主復水器１から排ガス抽出器２により大部分を占
める水蒸気と共に抽出され、加熱後排ガス再結合
装置３において、炉心で放射線分解により発生し
た水素ガスと酸素ガスとの反応が行なわれ、水蒸
気とともに凝縮減容される。 In other words, gaseous waste such as non-condensable gas generated in a nuclear reactor and air leaked into the main condenser is
It is extracted from the main condenser 1 by the exhaust gas extractor 2 along with the water vapor that makes up the majority of the water vapor, and after heating, in the exhaust gas recombination device 3, a reaction between hydrogen gas generated by radiolysis in the core and oxygen gas is carried out, and together with the water vapor. The volume is reduced by condensation.
一方減容されて放射性希ガスと主復水器１へリ
ークインした空気のみとなつた気体廃棄物は、除
湿冷却された後、複数の活性炭式希ガスホールド
アツプ塔４からなる活性炭式希ガスホールドアツ
プ装置５に送られここで放射性希ガスが減衰除去
される。 On the other hand, the gaseous waste whose volume has been reduced to only the radioactive rare gas and the air that has leaked into the main condenser 1 is dehumidified and cooled, and then the activated carbon rare gas hold up tower 4 consists of multiple activated carbon rare gas hold up towers 4. The radioactive rare gas is sent to the upstream device 5, where the radioactive rare gas is attenuated and removed.
次いで後置フイルター６により濾過処理され
て、最終的には主復水器１にリークインした空気
のみが排ガスエジエクタ７を経て排気筒８から大
気中に放出される。 The air is then filtered by a post-filter 6, and finally only the air leaking into the main condenser 1 is discharged into the atmosphere from an exhaust stack 8 via an exhaust gas ejector 7.
［背景技術の問題点］
このような従来の気体廃棄物処理装置において
は、活性炭式希ガスホールドアツプ装置５に充填
される活性炭量は、例えば110万KWe級の沸騰水
型原子力発電所では、安全分を含んで70t程度、
容積では140m3にもなり、活性炭式希ガスホール
ドアツプ装置５は極めて大規模な設備となつてお
り、経済性の向上、設備の合理化が強く求められ
ている原子力施設においてその改善が求められて
いる。[Problems with Background Art] In such conventional gas waste treatment equipment, the amount of activated carbon charged into the activated carbon rare gas hold-up device 5 is, for example, in a 1.1 million KWe class boiling water nuclear power plant. Approximately 70 tons including safety.
With a volume of 140 m 3 , the activated carbon rare gas hold-up device 5 is an extremely large-scale facility, and its improvements are required in nuclear facilities where there is a strong demand for improved economic efficiency and equipment rationalization. There is.
一方、このような活性炭式希ガスホールドアツ
プ装置５における放射性希ガスのホールドアツプ
時間（Th）とガス流量(F)、活性炭量（Ｍ）との
間には次の関係式が成立することが知られてい
る。式中Ｋは活性炭の吸着係数である。 On the other hand, the following relational expression can be established between the radioactive rare gas hold-up time (Th), gas flow rate (F), and activated carbon amount (M) in the activated carbon type rare gas hold-up device 5. Are known. In the formula, K is the adsorption coefficient of activated carbon.
Th＝Ｋ・Ｍ／Ｆ
上式は活性炭式希ガスホールドアツプ装置５へ
の排ガス流入量が減少すれば、活性炭量を減少さ
せてもホールドアツプ時間を保持することができ
ることを意味している。 Th=K.M/F The above equation means that if the amount of exhaust gas flowing into the activated carbon type rare gas hold up device 5 is reduced, the hold up time can be maintained even if the amount of activated carbon is decreased.
［発明の目的］
本発明はこのような従来の事情に対処してなさ
れたもので、活性炭式希ガスホールドアツプ装置
への排ガス流入量を減少させることにより必要活
性炭量を減少させて、経済的かつ合理的な気体廃
棄物処理装置を提供しようとするものである。[Objective of the Invention] The present invention has been made in response to the above-mentioned conventional circumstances, and reduces the amount of activated carbon required by reducing the amount of exhaust gas flowing into the activated carbon rare gas hold-up device, thereby achieving an economical and economical solution. The present invention also aims to provide a rational gaseous waste treatment device.
［発明の概要］
すなわち本発明の気体廃棄物処理装置は、原子
炉圧力容器で発生した蒸気をタービンに導く主蒸
気ラインと、前記タービンを通過した蒸気を復水
とする主復水器と、前記復水を前記原子炉圧力容
器に導く給水ラインとを備えた原子炉１次系の、
前記主復水器より気体廃棄物を抽出する排ガス抽
出器と、この排ガス抽出器により抽出された前記
気体廃棄物中の水素ガスと酸素ガスとを再結合さ
せる排ガス再結合装置と、この排ガス再結合装置
を通過した気体廃棄物中の放射性希ガスをホール
ドアツプする活性炭式希ガスホールドアツプ装置
と、この活性炭式希ガスホールドアツプ装置によ
り処理された残留排ガスを排気筒より大気中へ放
出する排ガスエジエクタとを備えてなる気体廃棄
物処理装置において、前記活性炭式希ガスホール
ドアツプ装置出口にこの装置を通過した残留排ガ
ス中の酸素濃度を監視する酸素モニタを配設する
とともにこの酸素モニタの出力信号を受けて所定
量の水素ガスを前記原子炉１次系の給水ラインに
供給する水素ガス供給ラインとを配設したことを
特徴としている。[Summary of the Invention] That is, the gaseous waste treatment apparatus of the present invention includes: a main steam line that guides steam generated in a reactor pressure vessel to a turbine; a main condenser that condenses the steam that has passed through the turbine; a reactor primary system comprising a water supply line that guides the condensate to the reactor pressure vessel;
an exhaust gas extractor for extracting gaseous waste from the main condenser; an exhaust gas recombination device for recombining hydrogen gas and oxygen gas in the gaseous waste extracted by the exhaust gas extractor; An activated carbon rare gas hold-up device that holds up the radioactive rare gas in the gaseous waste that has passed through the coupling device, and an exhaust gas that releases the residual exhaust gas treated by the activated carbon rare gas hold up device into the atmosphere from the exhaust stack. In a gaseous waste treatment device comprising a gas ejector, an oxygen monitor for monitoring the oxygen concentration in the residual exhaust gas that has passed through the activated carbon rare gas hold-up device is disposed at the outlet of the activated carbon rare gas hold-up device, and an output signal of the oxygen monitor is provided. The present invention is characterized in that a hydrogen gas supply line is provided to supply a predetermined amount of hydrogen gas to the water supply line of the primary system of the nuclear reactor.
［発明の実施例］
以下本発明の詳細を図面に示す一実施例につい
て説明する。[Embodiment of the Invention] The details of the present invention will be described below with reference to an embodiment shown in the drawings.
第２図は本発明の一実施例を示すもので、図中
第１図と同一部分には同一符号が付されている。 FIG. 2 shows an embodiment of the present invention, in which the same parts as in FIG. 1 are given the same reference numerals.
第２図において、符号９は炉心１０を収容する
原子炉圧力容器を示しており、この原子炉圧力容
器９の上部側方にはタービン１１に接続される主
蒸気ライン１２が開口している。タービン１１の
下流に設けられた主復水器１には、復水を原子炉
圧力容器９に再循環させる給水ポンプ１３が介挿
された給水ライ１４が接続されている。 In FIG. 2, reference numeral 9 indicates a reactor pressure vessel housing a reactor core 10, and a main steam line 12 connected to a turbine 11 opens at the upper side of the reactor pressure vessel 9. A feed water lie 14 is connected to the main condenser 1 provided downstream of the turbine 11, in which a feed water pump 13 for recirculating condensate to the reactor pressure vessel 9 is inserted.
本発明の気体廃棄物処理装置はこのように構成
された原子炉１次系の主復水器１に前記給水ライ
ン１４とは別に配設され、以下のように構成され
ている。 The gaseous waste treatment apparatus of the present invention is disposed separately from the water supply line 14 in the main condenser 1 of the primary system of the nuclear reactor constructed as described above, and is constructed as follows.
すなわち主復水器１より気体廃棄物を水蒸気と
共に抽出する排ガス抽出器２と、この排ガス抽出
器２により抽出された気体廃棄物中の水素ガスお
よび酸素ガスを再結合させる排ガス再結合装置３
と、この排ガス再結合装置３を経た残留排ガス中
の放射性希ガスを減衰除去する複数の活性炭式希
ガスホールドアツプ塔４からなる活性炭式希ガス
ホールドアツプ装置５と、ホールドアツプ中に生
成した娘核種を捕獲する後置フイルター６と、以
上の処理装置により減害処理された排ガスを最終
的に排気筒８より大気中へ放出するための排ガス
エジエクタ７、およびこれらを順に接続する配管
P1〜P6とからその基本構成がなされている。 That is, an exhaust gas extractor 2 extracts gaseous waste together with water vapor from the main condenser 1, and an exhaust gas recombiner 3 that recombines hydrogen gas and oxygen gas in the gaseous waste extracted by the exhaust gas extractor 2.
, an activated carbon rare gas hold up device 5 consisting of a plurality of activated carbon rare gas hold up towers 4 that attenuate and remove the radioactive rare gas in the residual exhaust gas that has passed through the exhaust gas recombination device 3; A post-filter 6 that captures nuclides, an exhaust gas ejector 7 that ultimately releases the exhaust gas that has been abated by the above treatment device into the atmosphere from the exhaust stack 8, and piping that connects these in sequence.
Its basic structure is made up of P 1 to P 6 .
さらに本発明においては、活性炭式希ガスホー
ルドアツプ装置５出口に、活性炭式希ガスホール
ドアツプ装置５を通過した排ガス（前述したよう
に主復水器１にリークインした空気のみと考えら
れる）中の酸素濃度を監視する酸素モニタ１５
と、この酸素モニタ１５の出力信号を受けて流量
調節弁１６を備えた水素ガスボンベ１７から流量
調節弁１６の開閉度を調節して、所定量の水素ガ
スを前記原子炉１次系の給水ライン１４の給水ポ
ンプ１３下流に、配管P7を通じて供給する水素
供給制御器１８を備えた水素ガス供給ライン１９
が設けられている。 Furthermore, in the present invention, the exhaust gas that has passed through the activated carbon rare gas hold up device 5 (which is considered to be only the air that has leaked into the main condenser 1 as described above) is sent to the outlet of the activated carbon rare gas hold up device 5. Oxygen monitor 15 that monitors oxygen concentration
Then, in response to the output signal of the oxygen monitor 15, a predetermined amount of hydrogen gas is supplied from a hydrogen gas cylinder 17 equipped with a flow rate control valve 16 to the water supply line of the reactor primary system by adjusting the opening/closing degree of the flow rate control valve 16. 14 downstream of the water supply pump 13, a hydrogen gas supply line 19 equipped with a hydrogen supply controller 18 for supplying through pipe P 7
is provided.
また排ガス再結合装置３には水素ガスの過剰供
給等による未反応の水素ガスが流出することに備
えて、排ガス再結合装置３出口側の水素ガスを監
視する水素モニタ２０が設けられている。 Further, the exhaust gas recombination device 3 is provided with a hydrogen monitor 20 that monitors the hydrogen gas on the exit side of the exhaust gas recombination device 3 in preparation for the outflow of unreacted hydrogen gas due to excessive supply of hydrogen gas.
すなわち、酸素モニタ１５により検出された酸
素ガス量に化学量論的に見合う水素ガス量を原子
炉１次系の給水ライン１４に供給しても、排ガス
再結合装置３の反応条件等により未反応の水素ガ
スが流出するおそれがあり、水素モニタ２０によ
り活性炭式希ガスホールドアツプ装置５入口にお
いて水素濃度が0.1％を越えないように監視する。 That is, even if an amount of hydrogen gas stoichiometrically commensurate with the amount of oxygen gas detected by the oxygen monitor 15 is supplied to the water supply line 14 of the reactor primary system, there may be no reaction due to the reaction conditions of the exhaust gas recombination device 3, etc. Since there is a risk of hydrogen gas leaking out, a hydrogen monitor 20 is used to monitor the hydrogen concentration at the inlet of the activated carbon rare gas hold-up device 5 to ensure that it does not exceed 0.1%.
このように構成された本発明の気体廃棄物処理
装置においては、酸素モニタ１５による活性炭式
希ガスホールドアツプ装置５出口の酸素濃度の検
出信号を受けて、水素供給制御器１８が作動し、
流量調節弁１６の開閉度を調節して、所定量の水
素ガス（通常酸素濃度の２倍以内）が給水ライン
１４を経て原子炉圧力容器９内へ供給される。こ
のようにして供給された水素ガスは炉心１０での
水の放射線分解による酸素ガスの発生を抑制する
と共に、他の気体廃棄物と共に主復水器１より気
体廃棄物処理装置へ抽出され、主復水器１へリー
クインした空気中の酸素ガスと、排ガス再結合装
置３において反応し、水となつて除去される。 In the gaseous waste treatment apparatus of the present invention configured in this way, the hydrogen supply controller 18 is activated in response to a detection signal of the oxygen concentration at the outlet of the activated carbon rare gas hold-up device 5 from the oxygen monitor 15.
A predetermined amount of hydrogen gas (within twice the normal oxygen concentration) is supplied into the reactor pressure vessel 9 through the water supply line 14 by adjusting the opening/closing degree of the flow control valve 16 . The hydrogen gas supplied in this way suppresses the generation of oxygen gas due to radiolysis of water in the reactor core 10, and is extracted together with other gaseous wastes from the main condenser 1 to the gaseous waste treatment equipment. Oxygen gas in the air that has leaked into the condenser 1 reacts in the exhaust gas recombination device 3, and is removed as water.
この結果活性炭式希ガスホールドアツプ装置５
入口の排ガス流量は、水素ガスを供給しない場合
に比べると20％程度減少することになり、活性炭
式希ガスホールドアツプ装置５における活性炭の
必要量を20％程度減少させることが可能となる。 As a result, activated carbon rare gas hold up device 5
The exhaust gas flow rate at the inlet is reduced by about 20% compared to the case where hydrogen gas is not supplied, and the amount of activated carbon required in the activated carbon rare gas hold-up device 5 can be reduced by about 20%.
なお、上記気体廃棄物処理装置において水素ガ
スの供給を給水ポンプ１３下流で行なうとしたの
は、上述したように炉心１０での、水の放射線分
解による酸素ガス発生の抑制効果を考慮したため
である。 The reason for supplying hydrogen gas downstream of the water supply pump 13 in the gaseous waste treatment device is to take into consideration the effect of suppressing the generation of oxygen gas due to radiolysis of water in the reactor core 10, as described above. .
［発明の効果］
以上の実施例からも明らかなように活性炭式希
ガスホールドアツプ装置出口に酸素モニタを配設
したので、室温程度の、しかも水分が非常に低い
値となつている条件下で測定が行なうことがで
き、これによつて高い測定精度が得られ、また酸
素モニタの点検も容易で劣化も少ない。[Effects of the Invention] As is clear from the above embodiments, an oxygen monitor was installed at the outlet of the activated carbon rare gas hold-up device, so that it could be used under conditions of room temperature and extremely low moisture content. This allows for high measurement accuracy, and the oxygen monitor is easy to inspect and suffers little deterioration.
さらに、酸素モニタの出力信号に応じて水素ガ
スを原子炉１次系の給水ラインに供給するように
したので、冷却水の放射線分解による酸素の発生
を抑制するとともに、排ガス処理装置と原子炉水
への水素供給装置をそれぞれ設置する場合と比べ
て、装置規模を縮小し、装置の数を減少させて装
置の信頼性が高められる。 Furthermore, hydrogen gas is supplied to the water supply line of the primary reactor system according to the output signal of the oxygen monitor, which suppresses the generation of oxygen due to radiolysis of the cooling water, and also prevents the exhaust gas treatment equipment and reactor water Compared to the case where a hydrogen supply device is installed for each, the scale of the device can be reduced, the number of devices can be reduced, and the reliability of the device can be improved.
第１図は従来の気体廃棄物処理装置を示す配管
系統図、第２図は本発明の一実施例を示す配管系
統図である。
１……主復水器、２……排ガス抽出器、３……
排ガス再結合装置、４……活性炭式希ガスホール
ドアツプ塔、５……活性炭式希ガスホールドアツ
プ装置、６……後置フイルター、７……排ガスエ
ジエクタ、８……排気筒、９……原子炉圧力容
器、１１……タービン、１２……主蒸気ライン、
１４……給水ライン、１５……酸素モニタ、１９
……水素ガス供給ライン、２０……水素モニタ。
FIG. 1 is a piping system diagram showing a conventional gaseous waste treatment apparatus, and FIG. 2 is a piping system diagram showing an embodiment of the present invention. 1... Main condenser, 2... Exhaust gas extractor, 3...
Exhaust gas recombination device, 4...Activated carbon rare gas hold up tower, 5...Activated carbon rare gas hold up device, 6... Post filter, 7... Exhaust gas ejector, 8... Exhaust stack, 9... Atom Furnace pressure vessel, 11...turbine, 12...main steam line,
14...Water supply line, 15...Oxygen monitor, 19
...Hydrogen gas supply line, 20...Hydrogen monitor.
Claims (1)
導く主蒸気ラインと、前記タービンを通過した蒸
気を復水とする主復水器と、前記復水を前記原子
炉圧力容器に導く給水ラインとを備えた原子炉１
次系の、前記主復水器より気体廃棄物を抽出する
排ガス抽出器と、この排ガス抽出器により抽出さ
れた気体廃棄物中の水素ガスと酸素ガスとを再結
合させる排ガス再結合装置と、この排ガス再結合
装置を通過した気体廃棄物中の放射性希ガスをホ
ールドアツプする活性炭式希ガスホールドアツプ
装置と、この活性炭式希ガスホールドアツプ装置
により処理された残留排ガスを排気筒より大気中
へ放出する排ガスエジエクタとを備えてなる気体
廃棄物処理装置において、前記活性炭式希ガスホ
ールドアツプ装置出口にこの装置を通過した残留
排ガス中の酸素濃度を監視する酸素モニタを配設
するとともにこの酸素モニタの出力信号を受けて
所定量の水素ガスを前記原子炉１次系の給水ライ
ンに供給する水素ガス供給ラインを配設したこと
を特徴とする気体廃棄物処理装置。 ２ 排ガス再結合装置出口にこの装置を通過した
気体廃棄物中の水素濃度を監視する水素モニタを
配設したことを特徴とする特許請求の範囲第１項
記載の気体廃棄物処理装置。[Scope of Claims] 1. A main steam line that guides steam generated in the reactor pressure vessel to a turbine, a main condenser that condenses the steam that has passed through the turbine, and a main condenser that condenses the steam that has passed through the turbine; A nuclear reactor 1 equipped with a water supply line leading to
an exhaust gas extractor that extracts gaseous waste from the main condenser; and an exhaust gas recombination device that recombines hydrogen gas and oxygen gas in the gaseous waste extracted by the exhaust gas extractor; An activated carbon rare gas hold-up device holds up the radioactive rare gas in the gaseous waste that has passed through this exhaust gas recombination device, and the residual exhaust gas treated by this activated carbon rare gas hold up device is released into the atmosphere from the exhaust stack. In a gaseous waste treatment device comprising an exhaust gas ejector for discharging, an oxygen monitor is disposed at the outlet of the activated carbon type rare gas hold-up device to monitor the oxygen concentration in the residual exhaust gas that has passed through the device, and the oxygen monitor 1. A gaseous waste treatment apparatus, further comprising a hydrogen gas supply line that receives an output signal and supplies a predetermined amount of hydrogen gas to the water supply line of the primary reactor system. 2. The gaseous waste treatment device according to claim 1, further comprising a hydrogen monitor disposed at the outlet of the exhaust gas recombination device to monitor the hydrogen concentration in the gaseous waste that has passed through the device.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP24053483A JPS60131499A (en) | 1983-12-20 | 1983-12-20 | Treater for gas waste |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP24053483A JPS60131499A (en) | 1983-12-20 | 1983-12-20 | Treater for gas waste |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS60131499A JPS60131499A (en) | 1985-07-13 |
| JPH0327879B2 true JPH0327879B2 (en) | 1991-04-17 |
Family
ID=17060958
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP24053483A Granted JPS60131499A (en) | 1983-12-20 | 1983-12-20 | Treater for gas waste |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS60131499A (en) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2003075307A (en) * | 2001-08-31 | 2003-03-12 | Nikkiso Co Ltd | Sampling system for sampling gas of exhaust gas having radioactive material |
Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS52104460A (en) * | 1976-03-01 | 1977-09-01 | Hitachi Ltd | Removing apparatus for oxygen gas |
| JPS54161000A (en) * | 1978-06-12 | 1979-12-20 | Toshiba Corp | Combustible-gas concentration control method |
-
1983
- 1983-12-20 JP JP24053483A patent/JPS60131499A/en active Granted
Patent Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS52104460A (en) * | 1976-03-01 | 1977-09-01 | Hitachi Ltd | Removing apparatus for oxygen gas |
| JPS54161000A (en) * | 1978-06-12 | 1979-12-20 | Toshiba Corp | Combustible-gas concentration control method |
Also Published As
| Publication number | Publication date |
|---|---|
| JPS60131499A (en) | 1985-07-13 |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| EXPY | Cancellation because of completion of term |