JPH0117120B2 - - Google Patents
Info
- Publication number
- JPH0117120B2 JPH0117120B2 JP55051664A JP5166480A JPH0117120B2 JP H0117120 B2 JPH0117120 B2 JP H0117120B2 JP 55051664 A JP55051664 A JP 55051664A JP 5166480 A JP5166480 A JP 5166480A JP H0117120 B2 JPH0117120 B2 JP H0117120B2
- Authority
- JP
- Japan
- Prior art keywords
- cooling water
- ammonia
- reactor
- water
- ions
- 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
Links
- QGZKDVFQNNGYKY-UHFFFAOYSA-N Ammonia Chemical compound N QGZKDVFQNNGYKY-UHFFFAOYSA-N 0.000 claims description 42
- 239000000498 cooling water Substances 0.000 claims description 26
- 229910021529 ammonia Inorganic materials 0.000 claims description 21
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 15
- 238000000034 method Methods 0.000 claims description 5
- 238000009835 boiling Methods 0.000 claims description 4
- 150000002500 ions Chemical class 0.000 description 12
- 239000000446 fuel Substances 0.000 description 9
- 230000005855 radiation Effects 0.000 description 6
- XEEYBQQBJWHFJM-UHFFFAOYSA-N Iron Chemical compound [Fe] XEEYBQQBJWHFJM-UHFFFAOYSA-N 0.000 description 5
- 238000002347 injection Methods 0.000 description 5
- 239000007924 injection Substances 0.000 description 5
- 239000000463 material Substances 0.000 description 5
- 238000000746 purification Methods 0.000 description 5
- 229910021645 metal ion Inorganic materials 0.000 description 4
- PXHVJJICTQNCMI-UHFFFAOYSA-N Nickel Chemical compound [Ni] PXHVJJICTQNCMI-UHFFFAOYSA-N 0.000 description 3
- 238000000605 extraction Methods 0.000 description 3
- 239000002184 metal Substances 0.000 description 3
- 229910052751 metal Inorganic materials 0.000 description 3
- 239000000126 substance Substances 0.000 description 3
- UQSXHKLRYXJYBZ-UHFFFAOYSA-N Iron oxide Chemical compound [Fe]=O UQSXHKLRYXJYBZ-UHFFFAOYSA-N 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 239000012535 impurity Substances 0.000 description 2
- 150000002739 metals Chemical class 0.000 description 2
- 229910052759 nickel Inorganic materials 0.000 description 2
- 230000002285 radioactive effect Effects 0.000 description 2
- 229910000859 α-Fe Inorganic materials 0.000 description 2
- NWUYHJFMYQTDRP-UHFFFAOYSA-N 1,2-bis(ethenyl)benzene;1-ethenyl-2-ethylbenzene;styrene Chemical compound C=CC1=CC=CC=C1.CCC1=CC=CC=C1C=C.C=CC1=CC=CC=C1C=C NWUYHJFMYQTDRP-UHFFFAOYSA-N 0.000 description 1
- 229910000881 Cu alloy Inorganic materials 0.000 description 1
- 229910000831 Steel Inorganic materials 0.000 description 1
- 230000004913 activation Effects 0.000 description 1
- QVGXLLKOCUKJST-UHFFFAOYSA-N atomic oxygen Chemical compound [O] QVGXLLKOCUKJST-UHFFFAOYSA-N 0.000 description 1
- 229910052804 chromium Inorganic materials 0.000 description 1
- 239000011651 chromium Substances 0.000 description 1
- 229910017052 cobalt Inorganic materials 0.000 description 1
- 239000010941 cobalt Substances 0.000 description 1
- GUTLYIVDDKVIGB-UHFFFAOYSA-N cobalt atom Chemical compound [Co] GUTLYIVDDKVIGB-UHFFFAOYSA-N 0.000 description 1
- 229910052802 copper Inorganic materials 0.000 description 1
- 239000010949 copper Substances 0.000 description 1
- 230000007423 decrease Effects 0.000 description 1
- 239000007789 gas Substances 0.000 description 1
- 230000002401 inhibitory effect Effects 0.000 description 1
- 239000003456 ion exchange resin Substances 0.000 description 1
- 229920003303 ion-exchange polymer Polymers 0.000 description 1
- 229910052742 iron Inorganic materials 0.000 description 1
- 229910052748 manganese Inorganic materials 0.000 description 1
- 239000011572 manganese Substances 0.000 description 1
- 239000001301 oxygen Substances 0.000 description 1
- 229910052760 oxygen Inorganic materials 0.000 description 1
- 239000002244 precipitate Substances 0.000 description 1
- 239000010959 steel Substances 0.000 description 1
- 229910052725 zinc Inorganic materials 0.000 description 1
- 239000011701 zinc Substances 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
-
- 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
- Preventing Corrosion Or Incrustation Of Metals (AREA)
Description
本発明は沸騰水型原子力プラント（以下、
BWRプラントと称す）の放射能低減方法に関す
るものである。
原子力プラントにおける放射能生成のメカニズ
ムは、冷却水に溶け込んだ物質が燃料要素表面や
他の炉内材料表面に付着して放射化されることに
起因する。これらの付着物は酸化鉄が主成分であ
るが、その他にコバルト、ニツケル等の金属イオ
ンが存在し、これらが中性子照射を受けて60Coや
58Co等の放射性核種となる。これらの放射性核種
は燃料要素表面への付着及び該表面からの離脱を
繰り返して冷却水中に放出され、放射線線量を増
加させている。特に、BWRプラントでは、冷却
水がタービンを含む全系統を通つて循環する構成
となつているので、循環水系全体を清浄に保つた
めに薬品の注入は極力避けるようにしていた。現
在最も管理されたBWRにおいては、冷却水中の
鉄は2ppb、その他の金属は3ppbに抑制している
が、上記のように金属イオンが存在すると中性子
照射を受けて放射性核種となり、これが系統内を
循環しつつ配管や機器の壁面などに付着し、放射
能上昇の大きな原因となつている。
本発明の目的は、放射線量を減少させるのに好
適なBWRプラントの放射能低減方法を提供する
ことにある。
本発明の放射能低減方法は、沸騰水型原子力プ
ラントの復水脱塩器と低圧ヒータとの間の冷却水
中にアンモニアを添加し、上記冷却水中のアンモ
ニア濃度を１〜50μｇ／に保持することを特徴
とする。
本発明は、Coのアンミン錯イオンが高温水中
でも化学的に安定であり、燃料要素表面や炉内材
料表面で放射化の原因となるフエライト層を形成
することがないという点に着目してなされたもの
である。
実施例
第１図は本発明の一実施例を適用したBWRプ
ラントの系統図である。１は原子炉圧力容器、２
は燃料要素であり、燃料要素２は原子炉圧力容器
１内に収容した冷却水中に浸漬されている。原子
炉圧力容器１内で発生した蒸気はタービン３を回
転させた後、復水器４に入つて水となり、他の気
体は空気抽出器５で処理される。復水器４内の水
は復水ポンプ６で復水脱塩器７に送られ、金属イ
オン等が除去される。このようにして再生された
冷却水は復水ポンプ６で低圧ヒータ９に送られて
加熱され、更に、給水ポンプ１０によつて高圧ヒ
ータ１１に送られ、加熱されて原子炉圧力容器１
に戻される。また、冷却水の一部は原子炉圧力容
器１の下部から再循環ポンプ１２で抽出されて循
環しているが、その一部は原子炉浄化系１３を通
り、ポンプ１４で上記高圧ヒータ１１より原子炉
圧力容器１に循環する冷却水と混合して原子炉圧
力容器１内に戻される。
本実施例においては復水脱塩器７の下流にアン
モニアの注入点８を設けてある。アンモニアの注
入量は冷却水中での濃度が１〜50μｇ／となる
ような量である。BWRプラントの標準型での給
水流量を5000m3／hrとすると、250ｇ／hrの微量
のアンモニアが注入される。このアンモニアは低
圧ヒータ９、給水ポンプ１０、高圧ヒータ１１を
通過する間に、冷却水中のCoとアンミン錯イオ
ン〔Co（NH3）6 3+〕を生成して原子炉圧力容器１
に入る。このCoのアンミン錯イオンは高温水中
でも化学的に安定で分解せず、そのまま冷却水中
でイオン状態を維持しながら系統内を循環する。
従つて、燃料要素表面や炉内材料表面でFeと化
合してフエライト層を形成（析出）し、放射化さ
れるという問題を生じない。上記Coのアンミン
錯イオンの一部は原子炉浄化系１３を通るときに
イオン交換樹脂によつて除去される。更に、循環
を繰り返しながら次第に除去され、減少する。ま
た、過剰のアンモニアの一部は上記原子炉浄化系
１３で除去されるが、揮発性で、しかも蒸気／水
の分配比が４程度であるので蒸気中に存在する量
が多い。この蒸気中のアンモニアはタービン３、
復水器４を経て空気抽出系５から除去されるの
で、原子炉浄化系１３に過大の負担を負わせるこ
とはない。注入したアンモニアの一部は原子炉圧
力容器１内で放射線分解により、N2とH2とを生
成するが、アンモニアと同様に空気抽出系５から
放出される。なお、H2は冷却水中の溶存酸素と
結合して水になることによつても減少する。
本発明において、冷却水中のアンモニアの濃度
の最低値は1μｇ／としたが、これは冷却水中
には不純物イオンとしてのCoの他に、Cu、Zn、
Ni、Mn、Crも含まれており、これらは100℃以
下の温度ではアンモニアと化合してアンミン錯イ
オンを生成するので、上記金属イオン全体がアン
モニアと錯イオンを形成するのに必要な量と、更
に冷却水中のCo濃度は24〜100pptと各プラント
によつて差があるが、これをアンミン錯イオンと
するのには0.07〜0.3μｇ／が必要であり、通常
は化学当量の３〜４倍のアンモニアが必要となる
ので、これらの点も考慮して上記1μｇ／を最
低値として決定したものである。一方、上限の
50μｇ／は、３×10-6当量／に相当し、冷却
水のPH値を最高8.5まで上昇させることが予想さ
れるので、冷却水の管理目標値である5.6〜8.6の
範囲内に抑えるためである。また、導電率も
0.5μS／cm以下となり、冷却水の管理目標値であ
る1.0μS／cm以下とすることができる。更に、冷
却水のPH値が９以上になると復水器４等に用いら
れている銅合金鋼を侵食する恐れがあるが、上記
濃度では問題とならない。以上の理由により50μ
ｇ／という値が決定された。
第１表はBWRプラントの冷却水中に含まれる
金属不純物の一例であり、単位はpptである。な
お、NDは検出できないことを意味する。
The present invention is a boiling water nuclear power plant (hereinafter referred to as
This article concerns methods for reducing radioactivity in BWR plants (referred to as BWR plants). The mechanism of radioactivity generation in nuclear power plants is that substances dissolved in cooling water adhere to the surfaces of fuel elements and other reactor materials and become radioactive. The main component of these deposits is iron oxide, but other metal ions such as cobalt and nickel are also present, and these become 60 Co and 60 Co when irradiated with neutrons.
It becomes radioactive nuclides such as 58 Co. These radionuclides repeatedly adhere to and separate from the surface of the fuel element and are released into the cooling water, increasing the radiation dose. In particular, in a BWR plant, cooling water is circulated through the entire system, including the turbine, so injection of chemicals was avoided as much as possible in order to keep the entire circulating water system clean. Currently, in the most controlled BWR, iron in the cooling water is suppressed to 2 ppb and other metals to 3 ppb, but as mentioned above, if metal ions are present, they will be irradiated with neutrons and become radionuclides, which will spread within the system. As it circulates, it adheres to pipes and equipment walls, becoming a major cause of increased radioactivity. An object of the present invention is to provide a method for reducing the radioactivity of a BWR plant, which is suitable for reducing the radiation dose. The radioactivity reduction method of the present invention includes adding ammonia to cooling water between a condensate desalter and a low-pressure heater of a boiling water nuclear power plant, and maintaining the ammonia concentration in the cooling water at 1 to 50 μg/. It is characterized by The present invention was made based on the fact that ammine complex ions of Co are chemically stable even in high-temperature water and do not form a ferrite layer that causes activation on the surfaces of fuel elements or reactor materials. It is something that Embodiment FIG. 1 is a system diagram of a BWR plant to which an embodiment of the present invention is applied. 1 is the reactor pressure vessel, 2
is a fuel element, and the fuel element 2 is immersed in cooling water contained in the reactor pressure vessel 1. After the steam generated in the reactor pressure vessel 1 rotates the turbine 3, it enters the condenser 4 and becomes water, and other gases are processed in the air extractor 5. The water in the condenser 4 is sent to a condensate demineralizer 7 by a condensate pump 6, where metal ions and the like are removed. The cooling water thus regenerated is sent to the low-pressure heater 9 by the condensate pump 6 and heated, and further sent to the high-pressure heater 11 by the water supply pump 10 and heated to the reactor pressure vessel 1.
will be returned to. Also, a part of the cooling water is extracted from the lower part of the reactor pressure vessel 1 by a recirculation pump 12 and circulated, but part of it passes through the reactor purification system 13 and is sent to the high pressure heater 11 by a pump 14. It is mixed with the cooling water circulating in the reactor pressure vessel 1 and returned to the reactor pressure vessel 1. In this embodiment, an ammonia injection point 8 is provided downstream of the condensate demineralizer 7. The amount of ammonia injected is such that the concentration in the cooling water is 1 to 50 μg/. If the water supply flow rate in a standard BWR plant is 5000m 3 /hr, a trace amount of ammonia of 250g/hr is injected. While passing through the low pressure heater 9, water supply pump 10, and high pressure heater 11, this ammonia generates ammine complex ions [Co(NH 3 ) 6 3+ ] with Co in the cooling water, and is transferred to the reactor pressure vessel 1.
to go into. This Co ammine complex ion is chemically stable and does not decompose even in high-temperature water, and circulates within the system while maintaining its ionic state in cooling water.
Therefore, there is no problem that Fe is combined with Fe to form (precipitate) a ferrite layer on the surface of the fuel element or the surface of the material in the reactor and is activated. A part of the Co ammine complex ions are removed by the ion exchange resin when passing through the reactor purification system 13. Furthermore, it is gradually removed and reduced through repeated circulation. Further, a portion of excess ammonia is removed by the reactor purification system 13, but since it is volatile and the steam/water distribution ratio is about 4, a large amount exists in the steam. Ammonia in this steam is transferred to turbine 3,
Since it is removed from the air extraction system 5 via the condenser 4, it does not place an excessive burden on the reactor purification system 13. A part of the injected ammonia is radiolyzed in the reactor pressure vessel 1 to generate N 2 and H 2 , which are released from the air extraction system 5 like ammonia. Note that H 2 also decreases by combining with dissolved oxygen in the cooling water and becoming water. In the present invention, the minimum concentration of ammonia in the cooling water was set to 1 μg/, which means that in addition to Co as impurity ions, the cooling water contains Cu, Zn,
Ni, Mn, and Cr are also included, and these combine with ammonia to form ammine complex ions at temperatures below 100°C, so the total amount of the above metal ions is equal to the amount required to form complex ions with ammonia. Furthermore, the Co concentration in the cooling water varies from 24 to 100 ppt depending on the plant, but 0.07 to 0.3 μg/ is required to convert this into ammine complex ions, and usually 3 to 4 of the chemical equivalent. Since twice as much ammonia is required, the above-mentioned 1 μg/ was determined as the minimum value in consideration of these points. On the other hand, the upper limit
50 μg/ is equivalent to 3 x 10 -6 equivalent/, and it is expected that the PH value of the cooling water will rise up to 8.5, so in order to keep it within the range of 5.6 to 8.6, which is the target value for cooling water management. It is. Also, the conductivity
It becomes 0.5μS/cm or less, which can be set to 1.0μS/cm or less, which is the cooling water management target value. Furthermore, if the pH value of the cooling water is 9 or higher, there is a risk that it will corrode the copper alloy steel used in the condenser 4 and the like, but this does not pose a problem at the above concentration. Due to the above reasons, 50μ
A value of g/ was determined. Table 1 shows an example of metal impurities contained in cooling water of a BWR plant, and the unit is ppt. Note that ND means not detectable.
【表】
第１表から明らかなように、Fe以外の金属は
イオンとして存在する方が圧倒的に多いが、これ
らのイオンは合計でもせいぜい3ppb程度である
ので、アンモニアの濃度は前記の範囲で十分であ
る。
第２表はBWRプラントにおける再循環配管の
放射線線量率に関与する核種の一例を示すもので
ある。[Table] As is clear from Table 1, metals other than Fe exist overwhelmingly as ions, but the total amount of these ions is about 3 ppb at most, so the concentration of ammonia is within the above range. It is enough. Table 2 shows an example of nuclides that are involved in the radiation dose rate of recirculation piping in a BWR plant.
【表】
再循環配管の放射線線量率に関与している核種
の中でも60Coと58Coだけで86％を占めている。こ
のことはCoイオンの燃料要素表面や他の炉内材
料表面への付着を防止すれば大幅な放射線線量率
の低減ができることを示すものである。
本発明において、アンモニアの注入点を復水脱
塩器と低圧ヒータの間に設定した理由は、復水脱
塩器の前ではアンモニアが該脱塩器により捕捉さ
れてしまうこと、また、低圧ヒータの下流では冷
却水が高温、高圧の状態となつているために注入
条件が過酷であり、装置構成上不利となるからで
ある。
本発明のBWRプラントの放射能低減方法によ
れば、復水脱塩器と低圧ヒータとの間において冷
却水に１〜50μｇ／の濃度となるようにアンモ
ニアを注入することによつてCoイオンの燃料要
素や他の材料表面への付着を抑制することによ
り、放射線線量率を大幅に減少させることができ
る。[Table] Of the nuclides that are involved in the radiation dose rate of recirculation piping, 60 Co and 58 Co alone account for 86%. This indicates that the radiation dose rate can be significantly reduced by preventing Co ions from adhering to the surfaces of fuel elements and other reactor materials. In the present invention, the reason why the ammonia injection point is set between the condensate demineralizer and the low-pressure heater is that ammonia is captured by the condensate demineralizer before the condensate demineralizer, and the low-pressure heater This is because the cooling water is in a high temperature and high pressure state downstream of the system, so the injection conditions are severe, which is disadvantageous in terms of the equipment configuration. According to the method for reducing radioactivity in a BWR plant of the present invention, Co ions are removed by injecting ammonia into the cooling water between the condensate demineralizer and the low pressure heater to a concentration of 1 to 50 μg/. By inhibiting adhesion to fuel elements and other material surfaces, radiation dose rates can be significantly reduced.
第１図は本発明の一実施例であるBWRプラン
トの系統図である。
１……原子炉圧力容器、２……燃料要素、３…
…タービン、４……復水器、５……空気抽出系、
６……復水ポンプ、７……復水脱塩器、８……ア
ンモニア注入点、９……低圧ヒータ、１０……給
水ポンプ、１１……高圧ヒータ、１２……再循環
ポンプ、１３……原子炉浄化系、１４……ポン
プ。
FIG. 1 is a system diagram of a BWR plant that is an embodiment of the present invention. 1... Reactor pressure vessel, 2... Fuel element, 3...
...Turbine, 4...Condenser, 5...Air extraction system,
6... Condensate pump, 7... Condensate demineralizer, 8... Ammonia injection point, 9... Low pressure heater, 10... Water supply pump, 11... High pressure heater, 12... Recirculation pump, 13... ...Reactor purification system, 14...pump.
Claims (1)
ヒータとの間の冷却水中にアンモニアを添加し、
上記冷却水中のアンモニア濃度を１〜50μｇ／
に保持することを特徴とする沸騰水型原子力プラ
ントの放射能低減方法。1 Adding ammonia to the cooling water between the condensate demineralizer and the low-pressure heater of a boiling water nuclear power plant,
The ammonia concentration in the above cooling water is 1 to 50μg/
A method for reducing radioactivity in a boiling water nuclear power plant, characterized by maintaining
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP5166480A JPS56148099A (en) | 1980-04-21 | 1980-04-21 | Method of reducing ra-dioactivity of bwr type reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP5166480A JPS56148099A (en) | 1980-04-21 | 1980-04-21 | Method of reducing ra-dioactivity of bwr type reactor |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS56148099A JPS56148099A (en) | 1981-11-17 |
| JPH0117120B2 true JPH0117120B2 (en) | 1989-03-29 |
Family
ID=12893139
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP5166480A Granted JPS56148099A (en) | 1980-04-21 | 1980-04-21 | Method of reducing ra-dioactivity of bwr type reactor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS56148099A (en) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS60183595A (en) * | 1984-03-01 | 1985-09-19 | 株式会社日立製作所 | Method of operating boiling-water type nuclear power plant |
-
1980
- 1980-04-21 JP JP5166480A patent/JPS56148099A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS56148099A (en) | 1981-11-17 |
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