JP2002071884A - Light water reactor nuclear power generation equipment and method using it - Google Patents
Light water reactor nuclear power generation equipment and method using itInfo
- Publication number
- JP2002071884A JP2002071884A JP2000257638A JP2000257638A JP2002071884A JP 2002071884 A JP2002071884 A JP 2002071884A JP 2000257638 A JP2000257638 A JP 2000257638A JP 2000257638 A JP2000257638 A JP 2000257638A JP 2002071884 A JP2002071884 A JP 2002071884A
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- Japan
- Prior art keywords
- steam
- water reactor
- nuclear power
- power generation
- light water
- Prior art date
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Classifications
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- 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
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- Engine Equipment That Uses Special Cycles (AREA)
Abstract
Description
【０００１】[0001]
【発明の属する技術分野】本発明は、軽水炉原子力発電
設備の出力を増加させる技術及びそれを使用する方法に
関する。[0001] The present invention relates to a technique for increasing the output of a light water reactor nuclear power plant and a method of using the same.
【０００２】[0002]
【従来の技術】従来の軽水炉原子力発電設備は、沸騰水
型又は加圧水型のいずれにおいても、飽和蒸気を蒸気タ
ービンに供給して発電しているため、過熱蒸気を蒸気タ
ービンに供給している火力発電設備に比べて、熱効率が
低かった。2. Description of the Related Art Conventional light water reactor nuclear power generation equipment, in either a boiling water type or a pressurized water type, generates power by supplying saturated steam to a steam turbine, so that thermal power that supplies superheated steam to the steam turbine is used. Thermal efficiency was lower than power generation equipment.
【０００３】従来の沸騰水型軽水炉原子力発電設備の熱
効率を数字を挙げて説明する。図３のエンタルピ・エン
トロピ線図に示すように、点ａ、ｂ、ｄ、ｅは、沸騰水
型原子炉、蒸気タービン、復水器、ブースターポンプの
入口における水又は蒸気の状態である。このとき系内を
循環する蒸気流量１ｋｇ当たりの発電量は、蒸気タービ
ンの入口と出口のエンタルピ差で与えられ、以下の計算
式から概略１０２ｋｃａｌ／ｋｇになり、発電効率は１
６．５％になる。従って、熱効率は、火力発電設備の約
４０％に比べて低い。 発電量＝６６２−５６０＝１０２ｋｃａｌ／ｋｇ 消費エネルギー＝６６２ー４５＝６１７ｋｃａｌ／ｋｇ 発電効率＝（１０２／６１７）×１００＝１６．５％[0003] The thermal efficiency of a conventional boiling water reactor nuclear power plant will be described with reference to figures. As shown in the enthalpy-entropy diagram of FIG. 3, points a, b, d, and e are states of water or steam at the inlet of a boiling water reactor, a steam turbine, a condenser, or a booster pump. At this time, the power generation amount per kg of the steam flow circulating in the system is given by the enthalpy difference between the inlet and the outlet of the steam turbine, and is approximately 102 kcal / kg from the following formula, and the power generation efficiency is 1
6.5%. Therefore, the thermal efficiency is lower than about 40% of the thermal power plant. Power generation = 662-560 = 102 kcal / kg Energy consumption = 662−45 = 617 kcal / kg Power generation efficiency = (102/617) × 100 = 16.5%
【０００４】熱効率が低い原因は、過熱蒸気を発生する
装置がないことにある。ところが、軽水炉原子力発電設
備では、運転トラブルに結びつくような装置の設置が抑
制されており、過熱蒸気発生装置として安全性を確保し
た有効なものが現状ではなかった。[0004] The cause of low thermal efficiency is that there is no device for generating superheated steam. However, in light water reactor nuclear power generation equipment, installation of equipment that may lead to operational troubles has been suppressed, and there has been no effective superheated steam generator that has ensured safety.
【０００５】[0005]
【発明が解決しようとする課題】本発明の目的は、安全
性を確保した過熱蒸気発生装置を設置した軽水炉原子力
発電設備及びそれを使用する方法を提供することであ
る。SUMMARY OF THE INVENTION An object of the present invention is to provide a light water reactor nuclear power plant equipped with a superheated steam generator ensuring safety and a method for using the same.
【０００６】[0006]
【課題を解決するための手段】請求項１記載の発明は、
電気ヒータへの通電による熱エネルギーが蓄えられた蓄
熱槽内の伝熱管に、原子炉の熱エネルギーで発生させた
蒸気を通して過熱蒸気とし、その過熱蒸気を蒸気タービ
ンに供給することを特徴とする。According to the first aspect of the present invention,
The steam generated by the heat energy of the nuclear reactor is passed through a heat transfer tube in a heat storage tank in which heat energy is stored by energizing an electric heater, and is turned into superheated steam, and the superheated steam is supplied to a steam turbine.
【０００７】これは、沸騰水型原子力発電設備、加圧水
型原子力発電設備に適用できる。This can be applied to a boiling water nuclear power plant and a pressurized water nuclear power plant.
【０００８】請求項２記載の発明は、請求項１記載の軽
水炉原子力発電設備の使用方法であって、電気ヒータへ
の通電に夜間時間帯の電力を使用することを特徴とす
る。この場合、電気ヒータへの通電には、外部の発電設
備からの電気を利用しても良いし、後述するように発電
機の発電量の一部を利用しても良い。According to a second aspect of the present invention, there is provided the method of using the light water reactor nuclear power plant according to the first aspect, wherein electric power is supplied to the electric heater in the night time zone. In this case, electricity from the external power generation equipment may be used for energizing the electric heater, or a part of the power generation amount of the generator may be used as described later.
【０００９】請求項３記載の発明は、請求項１記載の軽
水炉原子力発電設備の使用方法であって、電気ヒータへ
の通電量を発電機の発電量の一部とすることを特徴とす
る。According to a third aspect of the present invention, there is provided a method of using the light water reactor nuclear power plant according to the first aspect, wherein the amount of electricity supplied to the electric heater is a part of the amount of power generated by the generator.
【００１０】[0010]
【発明の実施の形態】本発明の軽水炉原子力発電設備の
第一実施形態は、沸騰水型であって、図１に示すよう
に、沸騰水型原子炉１、蓄熱槽２内の伝熱管Ｐ、蒸気タ
ービン３、復水器４、ブースターポンプ５を導管６で順
次接続して循環経路を形成し、蒸気タービン３によって
発電機７を駆動する。DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS A first embodiment of a light water reactor nuclear power plant according to the present invention is a boiling water type, and as shown in FIG. , A steam turbine 3, a condenser 4, and a booster pump 5 are sequentially connected by a conduit 6 to form a circulation path, and a generator 7 is driven by the steam turbine 3.
【００１１】蓄熱槽２は、内部に充填した蓄熱材８に電
気ヒータ９と伝熱管Ｐを通してある。伝熱管Ｐの伝熱面
積を十分に広く設定すれば、蓄熱槽２から発生する蒸気
温度が蓄熱材８の温度にほぼ等しくなる。従って、発生
蒸気温度を一定に保つことができ、その温度制御が容易
になる。また、蓄熱槽２は、機械運動する箇所がないこ
とから、運転トラブルは殆ど発生せず、その結果、運転
制御が容易になる。In the heat storage tank 2, an electric heater 9 and a heat transfer tube P pass through a heat storage material 8 filled therein. If the heat transfer area of the heat transfer tube P is set sufficiently wide, the temperature of the steam generated from the heat storage tank 2 becomes substantially equal to the temperature of the heat storage material 8. Therefore, the generated steam temperature can be kept constant, and the temperature control becomes easy. In addition, since the heat storage tank 2 has no mechanically moving portion, almost no operation trouble occurs, and as a result, operation control becomes easy.
【００１２】蓄熱材８は、良好な熱伝達を可能にするた
めに、マグネシアと硝酸ナトリウム・亜硝酸ナトリウム
・硝酸カリウムの混合剤を用いることが望ましい。マグ
ネシアは、複数の粒度分布を有するものを用いたり、充
填比率を高くすると、熱伝達が向上する。マグネシア
は、容積当たりの蓄熱量が大きく、熱伝導率および輻射
率が大きい特徴がある。硝酸ナトリウム・亜硝酸ナトリ
ウム・硝酸カリウムの混合剤は、約７％、約４９％、約
４４％の重量比で混合されており、６００℃以下の温度
域で安定し、粘度が低く、熱媒体としても適している。
なお、電気ヒータ９から蓄熱材８への加熱を夜間電力を
利用して行うと、電力負荷平準化を推進することが可能
となる。As the heat storage material 8, it is desirable to use a mixture of magnesia and sodium nitrate / sodium nitrite / potassium nitrate in order to enable good heat transfer. When magnesia is used having a plurality of particle size distributions or when the filling ratio is increased, heat transfer is improved. Magnesia is characterized by a large amount of heat storage per volume, and a large thermal conductivity and emissivity. The mixture of sodium nitrate / sodium nitrite / potassium nitrate is mixed at a weight ratio of about 7%, about 49%, and about 44%, is stable in a temperature range of 600 ° C or lower, has a low viscosity, and is used as a heat medium. Are also suitable.
If the electric heater 9 is used to heat the heat storage material 8 using electric power at night, power load leveling can be promoted.
【００１３】発電中に電力の需要量が低下した場合、特
に電力需要が減少する夜間時間帯にには、蓄熱槽２内の
電気ヒータ９への通電に発電機７の発電量の一部を用い
て行うと、余剰電力を有効利用できることに加え、この
軽水炉原子力発電設備の沸騰水型原子炉の出力は１００
％で連続で維持しながら、発電所から外部へ供給する電
力を変化できる。When the power demand decreases during power generation, particularly during the night time when power demand decreases, a part of the power generation of the generator 7 is supplied to the electric heater 9 in the heat storage tank 2 to supply electricity. When used, surplus power can be used effectively, and the output of the boiling water reactor of this light water reactor nuclear power plant is 100
The power supplied from the power plant to the outside can be changed while maintaining the percentage continuously.
【００１４】沸騰水型原子炉１の内部の水は、燃料の核
分裂に伴う発熱によって飽和蒸気となり、蓄熱槽２内の
伝熱管Ｐに供給され、過熱蒸気となって蒸気タービン３
に供給される。蒸気タービン３に供給された過熱蒸気は
タービン翼を回転させた後に、復水器４に供給されて水
になり、ブースターポンプ５によって沸騰水型原子炉１
に戻される。The water inside the boiling water reactor 1 becomes saturated steam due to the heat generated by the nuclear fission of the fuel, and is supplied to the heat transfer tube P in the heat storage tank 2 to become superheated steam and become the superheated steam.
Supplied to The superheated steam supplied to the steam turbine 3 is supplied to a condenser 4 to turn into water after rotating the turbine blades, and is turned into water by a booster pump 5.
Is returned to.
【００１５】沸騰水型原子炉１、蓄熱槽２、蒸気タービ
ン３、復水器４、ブースターポンプ５の各入口における
水又は蒸気の状態は、図３のエンタルピ・エントロピ線
図に示すように、点Ａ、点Ｂ、点Ｃ、点Ｄ、点Ｅで表さ
れる。例えば、点Ａは、圧力７ＭＰａ、温度約４５℃の
水であり、そのエンタルピは４５ｋｃａｌ／ｋｇ程度で
ある。点Ｂは圧力７ＭＰａの飽和蒸気であり、そのエン
タルピは６６２ｋｃａｌ／ｋｇ程度である。点Ｃは、圧
力７ＭＰａ、温度５００℃の過熱蒸気であり、そのエン
タルピは８１５ｋｃａｌである。点Ｄは、圧力０．０１
ＭＰａ、乾き度０．９の湿り蒸気であり、そのエンタル
ピは５６０ｋｃａｌである。点Ｅは、圧力０．０１ＭＰ
ａの飽和水であり、そのエンタルピは約４５ｋｃａｌで
ある。点Ｅで示される水は、ブースターポンプ５によっ
て加圧され、点Ａで示される水に戻される。The state of water or steam at each inlet of the boiling water reactor 1, the heat storage tank 2, the steam turbine 3, the condenser 4, and the booster pump 5, as shown in the enthalpy-entropy diagram of FIG. Points A, B, C, D, and E are represented. For example, point A is water at a pressure of 7 MPa and a temperature of about 45 ° C., and its enthalpy is about 45 kcal / kg. Point B is saturated vapor at a pressure of 7 MPa, and its enthalpy is about 662 kcal / kg. Point C is superheated steam at a pressure of 7 MPa and a temperature of 500 ° C., and its enthalpy is 815 kcal. Point D has a pressure of 0.01
It is wet steam having a MPa and a dryness of 0.9, and its enthalpy is 560 kcal. Point E is 0.01MPa pressure
a, the enthalpy of which is about 45 kcal. The water indicated by the point E is pressurized by the booster pump 5 and returned to the water indicated by the point A.
【００１６】循環する蒸気１ｋｇ当たりの発電量は以下
の計算式に示すように、蒸気タービン３の入口と出口の
エンタルピ差で表され、２２５ｋｃａｌ／ｋｇとなる。
この発電に使用されたエネルギーは沸騰水型原子炉１に
おける加熱量及び蓄熱槽２における加熱量の和で表さ
れ、７７０ｋｃａｌ／ｋｇとなる。このときの熱効率は
３３．１％である。 発電量＝８１５−５６０＝２５５ｋｃａｌ／ｋｇ 使用エネルギー＝（６６２−４５）＋（８１５−６６
２）＝７７０ｋｃａｌ／ｋｇ 発電効率＝（２５５／７７０）×１００＝３３．１％The amount of power generated per kg of the circulating steam is represented by the enthalpy difference between the inlet and the outlet of the steam turbine 3 and is 225 kcal / kg, as shown in the following equation.
The energy used for this power generation is represented by the sum of the heating amount in the boiling water reactor 1 and the heating amount in the heat storage tank 2, and is 770 kcal / kg. At this time, the thermal efficiency is 33.1%. Power generation = 815-560 = 255 kcal / kg Energy used = (662-45) + (815-66)
2) = 770 kcal / kg Power generation efficiency = (255/770) × 100 = 33.1%
【００１７】従って、第一実施形態は、蓄熱槽２のない
従来のものに比べて、熱効率が約２倍向上する。Therefore, in the first embodiment, the thermal efficiency is improved about twice as compared with the conventional one without the heat storage tank 2.
【００１８】本発明の軽水炉原子力発電設備の第二実施
形態は、加圧水型であって、図２に示すように、蒸気発
生器１０と蒸気タービン３の間に蓄熱槽２を配置したこ
とを特徴とする。The second embodiment of the light water reactor nuclear power plant of the present invention is a pressurized water type, and is characterized in that a heat storage tank 2 is arranged between a steam generator 10 and a steam turbine 3, as shown in FIG. And
【００１９】加圧水型原子炉１１の内部の水は、核分裂
に伴う発熱によって高温になり、加圧器１２を経た後に
蒸気発生器１０に送られ、二次冷却水を加熱し、その
後、循環ポンプ１３で加圧水型原子炉１１に戻される。
二次冷却水は蒸気発生器１０において加熱されて飽和蒸
気となり、蓄熱槽２内の伝熱管Ｐに供給されて過熱蒸気
となり、その後、蒸気タービン３に供給される。The water inside the pressurized water reactor 11 becomes high in temperature due to the heat generated by nuclear fission, and is sent to the steam generator 10 after passing through the pressurizer 12 to heat the secondary cooling water. Is returned to the pressurized water reactor 11.
The secondary cooling water is heated in the steam generator 10 to become saturated steam, supplied to the heat transfer pipe P in the heat storage tank 2 to become superheated steam, and then supplied to the steam turbine 3.
【００２０】[0020]
【実施例】蓄熱槽２の実施例を以下に記す。 蓄熱槽の仕様 この蓄熱槽は、１，０００，０００ＫＷの軽水炉原子力
発電設備に用いられる蓄熱槽の１／２０，０００の容量
である。 電気ヒータの容量＝２７ＫＷ、蓄熱量＝２７０ＫＷ、２
３２Ｍｃａｌ 発生蒸気圧力＝７ＭＰａ、有効蓄熱温度＝３００〜５０
０℃ 熱出力＝４０ＫＷ、静置時の温度低下＝０．４％／時 蓄熱材＝外径７〜１０ｍｍのマグネシア１２００ｋｇ、
外径１ｍｍ未満のマグネシア６００ｋｇ、硝酸塩４００
ｋｇ 伝熱管はステンレス鋼管であり、外径１５．９ｍｍ、肉
厚１ｍｍ、長さ８２ｍである。Embodiment An embodiment of the heat storage tank 2 will be described below. Specification of heat storage tank This heat storage tank has a capacity of 1/20000 of the heat storage tank used for a 1,000,000 KW light water reactor nuclear power plant. Electric heater capacity = 27 KW, heat storage = 270 KW, 2
32Mcal generated steam pressure = 7MPa, effective heat storage temperature = 300-50
0 ° C. Heat output = 40 KW, temperature drop during standing = 0.4% / hour Heat storage material = 1200 kg of magnesia having an outer diameter of 7 to 10 mm,
600 kg of magnesia with outer diameter of less than 1 mm, nitrate 400
The kg heat transfer tube is a stainless steel tube having an outer diameter of 15.9 mm, a wall thickness of 1 mm, and a length of 82 m.
【００２１】電気ヒータ９を１０時間通電して蓄熱した
蓄熱槽２から蒸気を取り出す時の蓄熱材温度と、発生蒸
気温度と、出熱量の変化は図４に示す通りであった。FIG. 4 shows changes in the temperature of the heat storage material, the temperature of the generated steam, and the amount of heat output when the steam is taken out from the heat storage tank 2 in which the electric heater 9 is energized for 10 hours to store the heat.
【００２２】発生蒸気温度は、出熱から４時間まで一定
に保持され、５時間まで徐々に低下し、その後急激に低
下した。蒸気温度の低下が始まる時間と、伝熱管出口近
傍の蓄熱材の温度低下が始まる時間は一致している。The temperature of the generated steam was kept constant for 4 hours from the heat output, gradually decreased until 5 hours, and then decreased rapidly. The time when the steam temperature starts to decrease and the time when the temperature of the heat storage material near the outlet of the heat transfer tube starts to coincide.
【００２３】蓄熱材の温度は、まず出熱開始と共に伝熱
管近傍の蓄熱材温度が低下し、出熱から２時間３０分後
に中央近傍の蓄熱材温度が低下を始め、４時間後に出口
近傍の蓄熱材温度が低下を始める。The temperature of the heat storage material is determined as follows. First, the temperature of the heat storage material near the heat transfer tube decreases with the start of heat output, and the temperature near the center begins to decrease 2 hours and 30 minutes after the heat output, and the temperature near the outlet 4 hours later. The heat storage material temperature starts to decrease.
【００２４】[0024]
【発明の効果】請求項１記載の発明は、機械的な運動を
せず運転トラブルが殆ど発生しない蓄熱槽を、過熱蒸気
発生装置として用いたので、安全性を確保しつつも発電
効率を向上できる。According to the first aspect of the present invention, a heat storage tank which does not cause mechanical troubles and hardly causes an operation trouble is used as the superheated steam generator, so that the power generation efficiency is improved while ensuring safety. it can.
【００２５】請求項２記載の発明は、蓄熱槽の加熱を夜
間時間帯に行い、昼間時間帯に蓄熱槽内に蓄えられた熱
を利用して発電すれば、電力負荷平準化に寄与する。According to the second aspect of the present invention, if the heat storage tank is heated during the night time and power is generated by utilizing the heat stored in the heat storage tank during the daytime, the power load can be leveled.
【００２６】請求項３記載の発明は、蓄熱槽内の電気ヒ
ータへの通電に発電機の発電量の一部を用いて行うと、
発電中に電力の需要量が低下した場合、特に電力需要が
減少する夜間時間帯の場合には、余剰電力を有効利用で
きることに加え、この軽水炉原子力発電設備の原子炉の
出力は１００％で連続で維持しながら、発電所から外部
へ供給する電力を変化できる。According to a third aspect of the present invention, when power is supplied to the electric heater in the heat storage tank by using a part of the power generation amount of the generator,
When the power demand decreases during power generation, especially in the nighttime when power demand decreases, the surplus power can be used effectively, and the reactor power of this light water nuclear power plant is 100% continuous. And the power supplied from the power plant to the outside can be changed.
【図１】本発明の軽水炉原子力発電設備の第一実施形態
を示す説明図である。FIG. 1 is an explanatory diagram showing a first embodiment of a light water reactor nuclear power plant of the present invention.
【図２】本発明の軽水炉原子力発電設備の第二実施形態
を示す説明図である。FIG. 2 is an explanatory view showing a second embodiment of the light water reactor nuclear power plant of the present invention.
【図３】第一実施形態と従来品を比較したエンタルピ・
エントロピ線図である。FIG. 3 shows an enthalpy of the first embodiment and a conventional product.
It is an entropy diagram.
【図４】蓄熱槽の特性を示すグラフである。FIG. 4 is a graph showing characteristics of a heat storage tank.
１ 沸騰水型原子炉 ２ 蓄熱槽 Ｐ 伝熱管 ３ 蒸気タービン ７ 発電機 ９ 電気ヒータ １１ 加圧水型原子炉 DESCRIPTION OF SYMBOLS 1 Boiling water reactor 2 Heat storage tank P Heat transfer tube 3 Steam turbine 7 Generator 9 Electric heater 11 Pressurized water reactor
Claims (3)
ルギーが蓄えられた蓄熱槽（２）内の伝熱管（Ｐ）に、
原子炉（１，１１）の熱エネルギーで発生させた蒸気を
通して過熱蒸気とし、その過熱蒸気を蒸気タービン
（３）に供給して発電機（７）を駆動することを特徴と
する軽水炉原子力発電設備。A heat transfer tube (P) in a heat storage tank (2) in which heat energy is supplied by energizing an electric heater (9),
A light water reactor nuclear power generation facility characterized in that superheated steam is passed through steam generated by thermal energy of the nuclear reactor (1, 11), and the superheated steam is supplied to a steam turbine (3) to drive a generator (7). .
使用方法であって、電気ヒータ（９）への通電に夜間時
間帯の電力を使用することを特徴とする軽水炉原子力発
電設備の使用方法。2. A method of using a light water reactor nuclear power plant according to claim 1, wherein electric power is supplied to the electric heater (9) during the night time. .
使用方法であって、電気ヒータ（９）への通電量を発電
機（７）の発電量の一部とすることを特徴とする軽水炉
原子力発電設備の使用方法。3. A method for using a light water reactor nuclear power plant according to claim 1, wherein the amount of electricity supplied to the electric heater (9) is a part of the amount of power generated by the generator (7). How to use nuclear power facilities.
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP2000257638A JP2002071884A (en) | 2000-08-28 | 2000-08-28 | Light water reactor nuclear power generation equipment and method using it |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP2000257638A JP2002071884A (en) | 2000-08-28 | 2000-08-28 | Light water reactor nuclear power generation equipment and method using it |
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| Publication Number | Publication Date |
|---|---|
| JP2002071884A true JP2002071884A (en) | 2002-03-12 |
Family
ID=18746067
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| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP2000257638A Pending JP2002071884A (en) | 2000-08-28 | 2000-08-28 | Light water reactor nuclear power generation equipment and method using it |
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| Country | Link |
|---|---|
| JP (1) | JP2002071884A (en) |
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