JPH05346485A - Built-in pump of reactor - Google Patents
Built-in pump of reactorInfo
- Publication number
- JPH05346485A JPH05346485A JP4154718A JP15471892A JPH05346485A JP H05346485 A JPH05346485 A JP H05346485A JP 4154718 A JP4154718 A JP 4154718A JP 15471892 A JP15471892 A JP 15471892A JP H05346485 A JPH05346485 A JP H05346485A
- Authority
- JP
- Japan
- Prior art keywords
- reactor
- pump
- pressure vessel
- nozzle
- water
- 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
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
- Structures Of Non-Positive Displacement Pumps (AREA)
Abstract
(57)【要約】
【目的】原子炉運転中にポンプケーシングや圧力容器が
加熱され、不均一加熱に起因する熱応力の発生を抑制及
び熱変形に伴うポンプケーシングの軸振動の低減を図
る。
【構成】原子炉圧力容器１の下鏡部とポンプノズル１３
との接合部に炉水流入用間隙１４を設け、圧力容器１の
内壁側を炉水流入用ら旋状溝構造１４ａとし、圧力容器
１の下端部に炉水流出用孔構造を設け、ポンプノズル１
３の周りを炉水流れＡのある機構とした。
(57) [Abstract] [Purpose] The pump casing and the pressure vessel are heated during the operation of the nuclear reactor, which suppresses the generation of thermal stress due to uneven heating and reduces the axial vibration of the pump casing due to thermal deformation. [Structure] Lower part of reactor pressure vessel 1 and pump nozzle 13
A reactor water inflow gap 14 is provided at the joint with the reactor, a reactor water inflow spiral structure 14a is provided on the inner wall side of the pressure vessel 1, and a reactor water outflow hole structure is provided at the lower end of the pressure vessel 1. Nozzle 1
Around 3 was a mechanism with reactor water flow A.
Description
【０００１】[0001]
【産業上の利用分野】本発明は原子炉内蔵型ポンプに係
り、特に、ポンプノズルと圧力容器下部との不均一加熱
に起因する熱応力の発生及び熱変形を抑制するのに好適
なポンプノズル構造に関する。BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a pump with a built-in nuclear reactor, and more particularly to a pump nozzle suitable for suppressing the generation of thermal stress and thermal deformation due to nonuniform heating of the pump nozzle and the lower part of the pressure vessel. Regarding the structure.
【０００２】[0002]
【従来の技術】従来の原子炉内蔵型ポンプを図８に示
す。代表的なものは特開昭61−197796号及び特開平1−3
10191 号公報に示す。本発明の一実施例である図１と比
べると、ポンプノズル部１３とポンプケーシング部１２
は圧力容器下鏡部１ａと一体構造となっている。すなわ
ち、本発明のようにポンプノズル１３と圧力容器下部鏡
板１ａとの間に間隙１４が無いとポンプノズル部１３が
下鏡部に不均一配置となっているため、炉水Ａにより加
熱されたポンプノズル１３及びポンプケーシング１２が
軸方向に不均一加熱される。すなわち、図９に示すよう
に、ポンプノズル表面（ａ）と（ｂ）とでは軸方向長さ
Ｌに沿って、図示のような温度分布を形成し、下部鏡板
とポンプノズル取付部の近くで大きな温度差を生じる可
能性がある。その結果、材料表面における熱応力が発生
し、ポンプケーシングの熱変形による偏心に基づく軸振
動の発生原因となり原子炉内蔵型ポンプの信頼性，安全
性などの心配が考えられる。2. Description of the Related Art A conventional built-in nuclear reactor pump is shown in FIG. Typical examples are Japanese Patent Laid-Open No. 61-197796 and Japanese Patent Laid-Open No. 1-3.
It is shown in Japanese Patent No. 10191. Compared to FIG. 1, which is an embodiment of the present invention, the pump nozzle portion 13 and the pump casing portion 12
Has an integral structure with the pressure vessel lower mirror portion 1a. That is, when there is no gap 14 between the pump nozzle 13 and the lower end plate 1a of the pressure vessel as in the present invention, the pump nozzle portion 13 is non-uniformly arranged on the lower mirror portion and is therefore heated by the reactor water A. The pump nozzle 13 and the pump casing 12 are non-uniformly heated in the axial direction. That is, as shown in FIG. 9, a temperature distribution as shown in the figure is formed along the axial length L on the pump nozzle surfaces (a) and (b), and near the lower end plate and the pump nozzle mounting portion. A large temperature difference can occur. As a result, thermal stress is generated on the surface of the material, which may cause shaft vibration due to eccentricity due to thermal deformation of the pump casing, and there is a concern about the reliability and safety of the internal reactor pump.
【０００３】しかし、これらの原因はポンプノズル及び
ケーシングを圧力容器下部鏡板へ非対称配置したことに
よる不均一加熱に基づく熱応力の発生が支配的な原因と
考えられる。そこで、このような原子炉内蔵型ポンプの
熱応力を抑制するためには、技術課題としてポンプノズ
ル周りを均一加熱することが望まれる。However, it is considered that these causes are mainly caused by generation of thermal stress due to non-uniform heating due to asymmetrical arrangement of the pump nozzle and the casing on the lower end plate of the pressure vessel. Therefore, in order to suppress the thermal stress of such a pump with a built-in nuclear reactor, it is desired to uniformly heat the circumference of the pump nozzle as a technical problem.
【０００４】[0004]
【発明が解決しようとする課題】上記従来技術はポンプ
ノズルが原子炉圧力容器下鏡部傾斜面に不均一配置にな
っていることにより、特に、ポンプノズル部内温度分布
の不均一性に基づく熱応力の発生あるいは熱膨張による
ポンプケーシングの熱変形のための偏心や軸振動の発生
が予想される。In the above-mentioned prior art, since the pump nozzles are non-uniformly arranged on the inclined surface of the lower part of the reactor pressure vessel, heat generated based on the non-uniformity of the temperature distribution inside the pump nozzle Occurrence of stress or eccentricity or shaft vibration due to thermal deformation of the pump casing due to thermal expansion is expected.
【０００５】本発明の目的は、原子炉内蔵型ポンプにお
いて、原子炉圧力容器とポンプノズルが直接結合溶接構
造となることによる熱変形や軸振動発生を防止、または
抑制することにある。An object of the present invention is to prevent or suppress the occurrence of thermal deformation and shaft vibration due to the direct pressure welded structure of the reactor pressure vessel and the pump nozzle in the reactor built-in type pump.
【０００６】[0006]
【課題を解決するための手段】上記目的を達成するため
に、本発明はポンプノズルと原子炉圧力容器の間に炉水
が流入する間隙を設け、この構造の圧力容器側内壁を炉
水流入用ら旋状溝構造とし、さらに圧力容器下端部に炉
水流出用孔構造を設け、ポンプノズルが炉水の強制循環
により均一加熱され、熱応力や熱伸び変形を抑制するこ
とにより、原子炉運転中にポンプケーシングやノズルの
軸振動の発生を抑制するようにした。In order to achieve the above-mentioned object, the present invention provides a gap between the pump nozzle and the reactor pressure vessel into which reactor water flows, and the inner wall of the pressure vessel side of this structure is used for inflowing reactor water. It has a spiral groove structure and a reactor water outflow hole structure at the lower end of the pressure vessel.The pump nozzle is heated uniformly by the forced circulation of the reactor water, which suppresses thermal stress and thermal expansion deformation. The generation of axial vibration of the pump casing and nozzle during operation was suppressed.
【０００７】[0007]
【作用】原子炉圧力容器の下鏡部とポンプノズル接合部
に炉水流入用間隙を設け、しかも圧力容器内壁に炉水誘
導用ら旋状溝とその下端部に炉水流出孔を設けると、ポ
ンプノズル外周部は炉水が強制循環旋回流を形成して強
制対流熱伝達により均一加熱され、ポンプノズルの軸方
向温度分布が均一化される。これらの作用により、ポン
プノズル表面の熱応力及び熱変形が抑制され、その結
果、ポンプケーシングの熱変形に伴う軸振動が低減さ
れ、原子炉圧力容器及びポンプの安全性，信頼性を確保
する。[Function] When a reactor water inflow gap is provided in the lower mirror portion of the reactor pressure vessel and the pump nozzle joint, and further, a reactor water guiding spiral groove and a reactor water outflow hole are provided in the lower end portion of the pressure vessel inner wall. In the outer peripheral portion of the pump nozzle, the reactor water forms a forced circulation swirl flow and is uniformly heated by the forced convection heat transfer, and the axial temperature distribution of the pump nozzle is made uniform. By these actions, thermal stress and thermal deformation on the surface of the pump nozzle are suppressed, and as a result, axial vibration due to thermal deformation of the pump casing is reduced, and safety and reliability of the reactor pressure vessel and pump are secured.
【０００８】[0008]
【実施例】以下、本発明の一実施例を図１及び図７によ
り説明する。図１は原子炉内蔵型ポンプの縦断面図を示
す。まず、原子炉内蔵型ポンプの構成について説明す
る。ポンプシャフト１１はポンプケーシング１２内の中
心部に設置され、ポンプシャフト１１の上部には原子炉
圧力容器１の下部鏡板１ａとシュラウド２に固定された
ディフューザ１０内にポンプのインペラ９が設置されて
いる。また、インペラ９下部にはモータケーシング１６
が設置され、その内部にはモータステータ１７とモータ
ロータ１８が設置されている。また、ポンプケーシング
１２とモータケーシング１６の間には二次シール１５も
設置されている。ここで、圧力容器下部鏡板１ａとポン
プノズル１３との間に炉水Ａが流入するための間隙１４
を設ける。間隙１４はあまり狭すぎるとクレビスを形成
するため、適切な間隔を必要とする。また、図７の示す
ように、原子炉内蔵型ポンプ５は原子炉圧力容器１内の
下部鏡板１ａに数台周方向に設置されている。DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS An embodiment of the present invention will be described below with reference to FIGS. FIG. 1 shows a vertical cross-sectional view of a pump with a built-in nuclear reactor. First, the configuration of the reactor built-in type pump will be described. The pump shaft 11 is installed in the center of the pump casing 12, and the pump impeller 9 is installed in the upper part of the pump shaft 11 in the diffuser 10 fixed to the lower end plate 1a of the reactor pressure vessel 1 and the shroud 2. There is. Further, a motor casing 16 is provided below the impeller 9.
Is installed therein, and a motor stator 17 and a motor rotor 18 are installed therein. A secondary seal 15 is also installed between the pump casing 12 and the motor casing 16. Here, a gap 14 for the reactor water A to flow between the lower end plate 1a of the pressure vessel and the pump nozzle 13.
To provide. If the gap 14 is too narrow, crevices are formed, and thus a proper gap is required. In addition, as shown in FIG. 7, several reactor built-in type pumps 5 are installed in the lower end plate 1a in the reactor pressure vessel 1 in the circumferential direction.
【０００９】次に、原子炉内蔵型ポンプの動作について
説明する。まず、高温炉水Ａはポンプインペラ９により
原子炉圧力容器１内の下部鏡板１ａに沿って吐出され
て、原子炉本体へ送り込まれる。この時、炉水の吐出流
Ａは炉本体内炉心３へ流入し、ここで核反応により蒸気
を発生する。そして、熱水と蒸気は気水分離器６で二相
分離され、蒸気乾燥器７を通過して蒸気Ｂは主蒸気ノズ
ル８から蒸気タービンへ流出する。一方、気水分離器６
で二相分離された熱水Ａは圧力容器１とシュラウド２内
のダウンカマ部を下降し、再び、原子炉内蔵型ポンプ５
で循環される。一方、原子炉内蔵型ポンプ５において、
下部から低温・高圧のシールパージ水が供給され、シャ
フト軸方向を上部に向かってポンプケーシング１２とポ
ンプシャフト１１間の狭隙内へ押し込まれる。ここで、
ポンプシャフト１１は軸受特性から定まる偏心や振れ廻
りを生じる可能性がある。圧力容器下部鏡板１ａとポン
プノズル１３との間に炉水Ａが流入するための間隙１４
を設けると、下部鏡板１ａとポンプノズル１３の配置が
非対称にもかかわらず、炉水Ａによりポンプノズル１３
がほぼ均一に加熱されるので、軸方向の温度分布は、図
２に示すように、ａ側及びｂ側表面ともほぼ同一の温度
分布を形成する。すなわち、ポンプノズルの周方向及び
半径方向の熱応力は小さくなる。従って、ポンプケーシ
ング１３全体の熱応力が低減され、しかも熱変形を抑制
することができるので、偏心による軸振動等を抑制する
ことが可能となる。Next, the operation of the reactor built-in type pump will be described. First, the high temperature reactor water A is discharged by the pump impeller 9 along the lower end plate 1a in the reactor pressure vessel 1 and fed into the reactor body. At this time, the discharge flow A of the reactor water flows into the core 3 in the reactor body, where steam is generated by a nuclear reaction. Then, hot water and steam are separated into two phases by the steam separator 6, and the steam B passes through the steam dryer 7 and flows out from the main steam nozzle 8 to the steam turbine. On the other hand, steam separator 6
The hot water A separated into two phases in the pressure vessel 1 and the downcomer inside the shroud 2 descends, and again the reactor built-in pump 5
Is circulated in. On the other hand, in the reactor built-in pump 5,
Low-temperature and high-pressure seal purge water is supplied from the lower part and is pushed into the narrow gap between the pump casing 12 and the pump shaft 11 in the axial direction of the shaft toward the upper part. here,
The pump shaft 11 may cause eccentricity or whirling that is determined by the bearing characteristics. A gap 14 for the reactor water A to flow between the lower end plate 1a of the pressure vessel and the pump nozzle 13.
If the lower end plate 1a and the pump nozzle 13 are asymmetrical, the pump water 13
Is heated almost uniformly, the temperature distribution in the axial direction forms substantially the same temperature distribution on the a-side surface and the b-side surface as shown in FIG. That is, the thermal stress in the circumferential and radial directions of the pump nozzle becomes small. Therefore, the thermal stress of the entire pump casing 13 is reduced, and the thermal deformation can be suppressed, so that the shaft vibration and the like due to the eccentricity can be suppressed.
【００１０】また、本発明の他の実施例を図３，図４及
び図５により説明する。図３の本発明は図１の発明に対
し、均一加熱用に設けた間隙１４の外側の下部鏡板１ａ
の内壁側に炉水Ａが積極的に流入するようにら旋状溝構
造１４ａを設けたものである。図４の発明は図３と同じ
効果を狙い、ポンプノズル１３外表面にら旋状溝構造１
４ｂを設けたものである。また、図５はこれら強制的に
流入した炉水Ａの流出機構１４ｃを下部鏡板部１ａに少
なくとも一つ設けたものである。これら発明は図３から
図５まで単独でも設けてもよいし、これらを二つずつ、
または三つとも全て組み合わせて設けてもよい。Another embodiment of the present invention will be described with reference to FIGS. 3, 4 and 5. The present invention of FIG. 3 is different from that of FIG. 1 in that the lower end plate 1a outside the gap 14 provided for uniform heating is provided.
The spiral groove structure 14a is provided on the inner wall side of the so that the reactor water A positively flows in. The invention of FIG. 4 aims at the same effect as that of FIG. 3, and has a spiral groove structure 1 on the outer surface of the pump nozzle 13.
4b is provided. Further, in FIG. 5, at least one outflow mechanism 14c for the reactor water A forcedly inflowing is provided in the lower end plate portion 1a. These inventions may be provided singly from FIG. 3 to FIG.
Alternatively, all three may be provided in combination.
【００１１】これにより、図６に示すように図１と同様
にポンプノズル表面のａ側及びｂ側とも、ほぼ同一の温
度分布を形成し、ポンプノズルの周方向及び半径方向の
熱応力は更に低減できる。As a result, as shown in FIG. 6, similar to FIG. 1, the same temperature distribution is formed on the sides a and b of the surface of the pump nozzle, and the thermal stress in the circumferential and radial directions of the pump nozzle is further increased. It can be reduced.
【００１２】従って、本構造を設置すれば、ポンプノズ
ル部と圧力容器下鏡板部との広い空間で強制的に流入さ
れた炉水により、ポンプノズル表面は均一加熱され、非
対称配置にもかかわらず、均一な表面温度分布を形成す
る。それ故、ポンプノズル及びケーシングの周方向及び
半径方向の熱応力を低減し、しかも熱変形を抑制するこ
とができるため、ポンプの軸振動発生も抑制することが
できる。Therefore, if this structure is installed, the surface of the pump nozzle is uniformly heated by the reactor water forcedly flowed in the wide space between the pump nozzle portion and the lower end plate of the pressure vessel, and despite the asymmetrical arrangement. Form a uniform surface temperature distribution. Therefore, it is possible to reduce the thermal stress in the circumferential direction and the radial direction of the pump nozzle and the casing, and to suppress the thermal deformation, so that the axial vibration of the pump can be suppressed.
【００１３】[0013]
【発明の効果】本発明によれば、炉内のポンプノズルの
周りを炉水流れにおおわれることにより、ポンプノズル
が均一加熱されるため、従来のような不均一温度分布に
よる熱応力発生や熱変形を低減することができ、原子炉
運転中の熱変形等による軸振動の発生を抑制できるの
で、安全性，信頼性の高い原子炉圧力容器及びポンプを
提供できる。According to the present invention, since the pump nozzle is uniformly heated by being covered with the reactor water flow around the pump nozzle in the furnace, the thermal stress due to the non-uniform temperature distribution as in the conventional case is generated. Since thermal deformation can be reduced and generation of shaft vibration due to thermal deformation during reactor operation can be suppressed, it is possible to provide a reactor pressure vessel and a pump with high safety and reliability.
【図１】本発明の一実施例の原子炉内蔵型ポンプの縦断
面図。FIG. 1 is a vertical sectional view of a reactor built-in type pump according to an embodiment of the present invention.
【図２】図１の温度分布の説明図。FIG. 2 is an explanatory view of the temperature distribution of FIG.
【図３】本発明の他の実施例の原子炉内蔵型ポンプの縦
断面図。FIG. 3 is a vertical sectional view of a nuclear reactor built-in pump according to another embodiment of the present invention.
【図４】本発明の他の実施例の原子炉内蔵型ポンプの縦
断面図。FIG. 4 is a vertical cross-sectional view of a reactor built-in type pump according to another embodiment of the present invention.
【図５】本発明の他の実施例の原子炉内蔵型ポンプの縦
断面図。FIG. 5 is a vertical sectional view of a pump with a built-in reactor according to another embodiment of the present invention.
【図６】図３，図４，図５の温度分布の説明図。FIG. 6 is an explanatory view of the temperature distribution of FIGS. 3, 4, and 5.
【図７】原子炉圧力容器の縦断面図。FIG. 7 is a vertical sectional view of a reactor pressure vessel.
【図８】従来の原子炉内蔵型ポンプの縦断面図。FIG. 8 is a vertical sectional view of a conventional pump with a built-in nuclear reactor.
【図９】図８の温度分布図。9 is a temperature distribution chart of FIG.
１…原子炉圧力容器、１ａ…下部鏡板、２…シュラウ
ド、５…原子炉内蔵型ポンプ、９…ポンプインペラ、１
０…ディフューザ、１０ａ…ディフューザ外筒、１１…
ポンプシャフト、１２…ポンプケーシング、１３…ポン
プノズル、１４…間隙、１５…二次シール、１６…モー
タケーシング、１７…モータステータ、１８…モータロ
ータ。DESCRIPTION OF SYMBOLS 1 ... Reactor pressure vessel, 1a ... Lower end plate, 2 ... Shroud, 5 ... Reactor built-in pump, 9 ... Pump impeller, 1
0 ... Diffuser, 10a ... Diffuser outer cylinder, 11 ...
Pump shaft, 12 ... Pump casing, 13 ... Pump nozzle, 14 ... Gap, 15 ... Secondary seal, 16 ... Motor casing, 17 ... Motor stator, 18 ... Motor rotor.
フロントページの続き (72)発明者 井上 知昭 茨城県土浦市神立町502番地 株式会社日 立製作所機械研究所内 (72)発明者 魚住 弘人 茨城県日立市幸町三丁目１番１号 株式会 社日立製作所日立工場内 (72)発明者 遠藤 昭夫 茨城県日立市幸町三丁目１番１号 株式会 社日立製作所日立工場内 (72)発明者 近野 正伸 茨城県日立市幸町三丁目１番１号 株式会 社日立製作所日立工場内Front page continuation (72) Inventor Tomoaki Inoue 502 Jinritsucho, Tsuchiura-shi, Ibaraki Machinery Research Institute, Hiritsu Seisakusho Co., Ltd. (72) Hiroto Uozumi 3-1-1, Saiwaicho, Hitachi, Ibaraki Hitachi Hitachi, Ltd. (72) Inventor Akio Endo 3-1-1, Saiwai-cho, Hitachi-shi, Ibaraki Hitachi Ltd. Hitachi factory (72) Innovator Masanobu Konno 3-1-1, Saiwai-cho, Hitachi, Ibaraki Stock company Hitachi Ltd.Hitachi factory
Claims (2)
の下端の下鏡部に設置したポンプノズル部との間に炉水
が流入することのできる間隙を設け、炉内の前記ポンプ
ノズルの外周が前記炉水により均一に加熱されるように
し、前記ポンプノズルの熱応力の発生や熱変形を低減
し、原子炉運転中のポンプ軸の振動を抑制することを特
徴とする原子炉内蔵型ポンプ。1. In a boiling water reactor, a gap through which reactor water can flow is provided between a reactor nozzle and a pump nozzle portion installed at a lower mirror portion of a reactor pressure vessel, and the pump nozzle in the reactor is provided. The inside of the reactor is characterized in that the outer periphery of the reactor is heated uniformly by the reactor water, the occurrence of thermal stress and thermal deformation of the pump nozzle is reduced, and vibration of the pump shaft during reactor operation is suppressed. Type pump.
内壁側に炉内流入用ら旋状溝を設け、さらにら旋状溝最
下端部の前記圧力容器内に少なくとも一つの炉水流出機
構を設け、炉水が強制循環することにより間隙内に停滞
する前記炉水中の不純物の濃縮及び析出による金属表面
の粒界腐食や応力腐食割れを防止する原子炉内蔵型ポン
プ。2. A spiral groove for inflow into the reactor is provided on the inner wall side of the reactor pressure vessel, and at least one reactor water outflow into the pressure vessel at the lowermost end of the spiral groove. A reactor built-in pump that is provided with a mechanism to prevent intergranular corrosion and stress corrosion cracking of a metal surface due to concentration and precipitation of impurities in the reactor water that are stagnant in the gap due to forced circulation of the reactor water.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP4154718A JPH05346485A (en) | 1992-06-15 | 1992-06-15 | Built-in pump of reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP4154718A JPH05346485A (en) | 1992-06-15 | 1992-06-15 | Built-in pump of reactor |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH05346485A true JPH05346485A (en) | 1993-12-27 |
Family
ID=15590451
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP4154718A Pending JPH05346485A (en) | 1992-06-15 | 1992-06-15 | Built-in pump of reactor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH05346485A (en) |
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|---|---|---|---|---|
| US7665332B2 (en) | 2006-08-15 | 2010-02-23 | Whirlpool Corporation | Steam fabric treatment appliance with exhaust |
| US7681418B2 (en) | 2006-08-15 | 2010-03-23 | Whirlpool Corporation | Water supply control for a steam generator of a fabric treatment appliance using a temperature sensor |
| US7690062B2 (en) | 2007-08-31 | 2010-04-06 | Whirlpool Corporation | Method for cleaning a steam generator |
| US7707859B2 (en) | 2006-08-15 | 2010-05-04 | Whirlpool Corporation | Water supply control for a steam generator of a fabric treatment appliance |
| US7730568B2 (en) | 2006-06-09 | 2010-06-08 | Whirlpool Corporation | Removal of scale and sludge in a steam generator of a fabric treatment appliance |
| US7753009B2 (en) | 2006-10-19 | 2010-07-13 | Whirlpool Corporation | Washer with bio prevention cycle |
| US7765628B2 (en) | 2006-06-09 | 2010-08-03 | Whirlpool Corporation | Steam washing machine operation method having a dual speed spin pre-wash |
| US7841219B2 (en) | 2006-08-15 | 2010-11-30 | Whirlpool Corporation | Fabric treating appliance utilizing steam |
| US7886392B2 (en) | 2006-08-15 | 2011-02-15 | Whirlpool Corporation | Method of sanitizing a fabric load with steam in a fabric treatment appliance |
| US7918109B2 (en) | 2007-08-31 | 2011-04-05 | Whirlpool Corporation | Fabric Treatment appliance with steam generator having a variable thermal output |
| US7966683B2 (en) | 2007-08-31 | 2011-06-28 | Whirlpool Corporation | Method for operating a steam generator in a fabric treatment appliance |
| US8037565B2 (en) | 2007-08-31 | 2011-10-18 | Whirlpool Corporation | Method for detecting abnormality in a fabric treatment appliance having a steam generator |
| US8393183B2 (en) | 2007-05-07 | 2013-03-12 | Whirlpool Corporation | Fabric treatment appliance control panel and associated steam operations |
-
1992
- 1992-06-15 JP JP4154718A patent/JPH05346485A/en active Pending
Cited By (16)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US7730568B2 (en) | 2006-06-09 | 2010-06-08 | Whirlpool Corporation | Removal of scale and sludge in a steam generator of a fabric treatment appliance |
| US7765628B2 (en) | 2006-06-09 | 2010-08-03 | Whirlpool Corporation | Steam washing machine operation method having a dual speed spin pre-wash |
| US7886392B2 (en) | 2006-08-15 | 2011-02-15 | Whirlpool Corporation | Method of sanitizing a fabric load with steam in a fabric treatment appliance |
| US7904981B2 (en) | 2006-08-15 | 2011-03-15 | Whirlpool Corporation | Water supply control for a steam generator of a fabric treatment appliance |
| US7913339B2 (en) | 2006-08-15 | 2011-03-29 | Whirlpool Corporation | Water supply control for a steam generator of a fabric treatment appliance using a temperature sensor |
| US7707859B2 (en) | 2006-08-15 | 2010-05-04 | Whirlpool Corporation | Water supply control for a steam generator of a fabric treatment appliance |
| US7681418B2 (en) | 2006-08-15 | 2010-03-23 | Whirlpool Corporation | Water supply control for a steam generator of a fabric treatment appliance using a temperature sensor |
| US7841219B2 (en) | 2006-08-15 | 2010-11-30 | Whirlpool Corporation | Fabric treating appliance utilizing steam |
| US7665332B2 (en) | 2006-08-15 | 2010-02-23 | Whirlpool Corporation | Steam fabric treatment appliance with exhaust |
| US7753009B2 (en) | 2006-10-19 | 2010-07-13 | Whirlpool Corporation | Washer with bio prevention cycle |
| US8393183B2 (en) | 2007-05-07 | 2013-03-12 | Whirlpool Corporation | Fabric treatment appliance control panel and associated steam operations |
| US10844533B2 (en) | 2007-05-07 | 2020-11-24 | Whirlpool Corporation | Method for controlling a household washing machine |
| US7690062B2 (en) | 2007-08-31 | 2010-04-06 | Whirlpool Corporation | Method for cleaning a steam generator |
| US7918109B2 (en) | 2007-08-31 | 2011-04-05 | Whirlpool Corporation | Fabric Treatment appliance with steam generator having a variable thermal output |
| US7966683B2 (en) | 2007-08-31 | 2011-06-28 | Whirlpool Corporation | Method for operating a steam generator in a fabric treatment appliance |
| US8037565B2 (en) | 2007-08-31 | 2011-10-18 | Whirlpool Corporation | Method for detecting abnormality in a fabric treatment appliance having a steam generator |
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