JPH06100671B2 - Reactor coolant purification system - Google Patents
Reactor coolant purification systemInfo
- Publication number
- JPH06100671B2 JPH06100671B2 JP59047249A JP4724984A JPH06100671B2 JP H06100671 B2 JPH06100671 B2 JP H06100671B2 JP 59047249 A JP59047249 A JP 59047249A JP 4724984 A JP4724984 A JP 4724984A JP H06100671 B2 JPH06100671 B2 JP H06100671B2
- Authority
- JP
- Japan
- Prior art keywords
- heat exchanger
- purification system
- pipe
- regenerative heat
- reactor
- 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
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)
- Hydrogen, Water And Hydrids (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炉補助設備に設けられている原子
炉冷却材浄化系に関する。Description: TECHNICAL FIELD OF THE INVENTION The present invention relates to a reactor coolant purification system provided in a boiling water reactor auxiliary facility.
[発明の技術的背景とその問題点] 原子炉内で生成する不純物を取り除いて冷却材を所定の
水質つまり高純度に保つために沸騰水型原子炉では原子
炉冷却材浄化系が設けられている。すなわち、第1図に
示したように沸騰水型原子炉は原子炉圧力容器1内の炉
心2で発生した熱で給水配管3から流入した冷却材の水
を加熱し、蒸気化して気水分離器4および蒸気乾燥器5
を通し主蒸気配管6から図示してないタービン系へ送り
込んでいる。また、炉心2から熱を有効にとり出し蒸気
を発生しやすくするため再循環系配管7が設けられ、再
循環ポンプ8によって圧力容器1内のジェットポンプ9
へ駆動水を供給し、冷却材を炉心2内に強制循環させて
いる。[Technical background of the invention and its problems] In order to remove impurities generated in the reactor and maintain the coolant at a predetermined water quality, that is, high purity, a boiling water reactor has a reactor coolant purification system. There is. That is, as shown in FIG. 1, in the boiling water reactor, the heat of the core 2 in the reactor pressure vessel 1 heats the coolant water flowing from the water supply pipe 3 to vaporize it to separate it from water and water. Vessel 4 and steam dryer 5
Through a main steam pipe 6 to a turbine system (not shown). Further, a recirculation system pipe 7 is provided in order to effectively extract heat from the core 2 and easily generate steam, and a jet pump 9 in the pressure vessel 1 is provided by the recirculation pump 8.
Drive water is supplied to the core 2 to forcibly circulate the coolant in the core 2.
この再循環系は2回路で形成し、炉心冷却材の流量は再
循環ポンプ8の速度調整によって行なわれる。This recirculation system is formed by two circuits, and the flow rate of the core coolant is controlled by adjusting the speed of the recirculation pump 8.
原子炉冷却材浄化系は各原子炉再循環ポンプ8の吹込側
および圧力容器1の下部ヘッドから分岐された浄化系入
口配管10,11を通り、浄化系ポンプ12から再生熱交換器1
3、非再生熱交換器14およびろ過脱塩装置15にわたる配
管系と、再生熱交換器13から給水配管3に接続する浄化
系出口配管16とからなっている。The reactor coolant cleaning system passes through the cleaning system inlet pipes 10 and 11 branched from the blow-in side of each reactor recirculation pump 8 and the lower head of the pressure vessel 1, and from the cleaning system pump 12 to the regenerative heat exchanger 1.
3, a non-regeneration heat exchanger 14 and a filtration desalination device 15, and a purification system outlet pipe 16 connected from the regeneration heat exchanger 13 to the water supply pipe 3.
ところで、原子炉の定期検査時には原子力発電プラント
の各機器の保守点検および検査が行なわれる。この場
合、原子炉冷却水浄化系の保守点検も行なわれるが、こ
の際の作業は原子力発電プラントの放射線被曝線量全体
の5〜10%程度になる。このうちの大部分はポンプの保
守点検作業である。現在被曝線量にもっとも大きな寄与
があるものは再循環系である。By the way, at the time of periodical inspection of the nuclear reactor, maintenance and inspection of each device of the nuclear power plant are performed. In this case, maintenance and inspection of the reactor cooling water purification system is also performed, but the work at this time is about 5 to 10% of the total radiation exposure dose of the nuclear power plant. Most of these are maintenance work for pumps. Currently, the recycle system has the largest contribution to the radiation dose.
しかしながら、再循環ポンプ8に代わるインターナルポ
ンプが設置された場合、再循環系は削除されるため原子
炉冷却材浄化系の被曝線量への寄与率はさらに大きくな
ることが考えられている。したがって、放射線被曝の低
減化の観点から原子炉浄化系ポンプ部の放射線量を低減
化することが重要な問題点になる。However, when an internal pump that replaces the recirculation pump 8 is installed, the recirculation system is deleted, and it is considered that the contribution rate to the exposure dose of the reactor coolant purification system is further increased. Therefore, from the viewpoint of reducing radiation exposure, it is an important problem to reduce the radiation dose of the reactor cleaning system pump section.
[発明の目的] 本発明は上記背景技術の問題点を解決するためになされ
たもので、沸騰水型原子力発電プラントにおける原子炉
冷却材浄化系において、たとえば原子炉の定期点検、保
守点検時の作業員の放射線被曝を低減できるようにした
原子炉冷却材浄化系を提供することにある。[Object of the Invention] The present invention has been made in order to solve the problems of the background art described above, and in a reactor coolant purification system in a boiling water nuclear power plant, for example, during periodic inspection and maintenance inspection of the reactor. An object of the present invention is to provide a reactor coolant purification system capable of reducing the radiation exposure of workers.
[発明の概要] 本発明は沸騰水型原子炉圧力容器のドレン系または原子
炉再循環系あるいは他の冷却材流通系から分岐された浄
化系入口配管と、この浄化系入口配管に連通された再生
熱交換器と、この再生熱交換器の下流側配管に設置され
た非再生熱交換器と、この非再生熱交換器の下流側配管
に設置されたろ過脱塩装置と、このろ過脱塩装置の下流
側に連通され前記再生熱交換器を介して前記沸騰水型原
子炉圧力容器の冷却材流通系に接続された浄化系出口配
管と、前記再生熱交換器の下流側配管または前記非再生
熱交換器の下流側配管に設置されしかも前記ろ過脱塩装
置の上流側配管に配置されプラント運転時およびプラン
ト停止時に稼動される浄化系ポンプとを有することを特
徴とする原子炉冷却材浄化系である。SUMMARY OF THE INVENTION The present invention is connected to a purification system inlet pipe branched from a drain system or a reactor recirculation system of a boiling water reactor pressure vessel or other coolant distribution system, and to this purification system inlet pipe. The regenerative heat exchanger, the non-regenerative heat exchanger installed in the downstream pipe of the regenerative heat exchanger, the filter desalting device installed in the downstream pipe of the non-regenerative heat exchanger, and the filter desalination A purification system outlet pipe connected to the downstream side of the device and connected to the coolant flow system of the boiling water reactor pressure vessel via the regenerative heat exchanger, and a downstream side pipe of the regenerative heat exchanger or the non- Reactor coolant purification, comprising: a purification system pump installed in the downstream pipe of the regenerative heat exchanger and arranged in the upstream pipe of the filter desalination apparatus, which is operated during plant operation and plant shutdown. It is a system.
[発明の実施例] 以下本発明に係る原子炉冷却材浄化系の一実施例を第2
図を参照しながら説明する。[Embodiment of the Invention] A second embodiment of the reactor coolant purification system according to the present invention will be described below.
Description will be given with reference to the drawings.
なお、第2図中、第1図と同一部分は同一符号で示し重
複する部分の説明を省略する。第2図における本発明の
実施例が第1図の従来例と異なる点は浄化系入口配管1
0,11の上流側に接続されていた駆動用浄化ポンプ12を再
生熱交換器13の出口配管13aに接続し、該浄化系ポンプ1
2の吐出側を非再生熱交換器14に接続したことにある。In FIG. 2, the same parts as those in FIG. 1 are designated by the same reference numerals, and the description of the overlapping parts will be omitted. The difference between the embodiment of the present invention shown in FIG. 2 and the conventional example shown in FIG.
The drive purification pump 12 connected to the upstream side of 0, 11 is connected to the outlet pipe 13a of the regenerative heat exchanger 13, and the purification system pump 1
The discharge side of 2 is connected to the non-regenerative heat exchanger 14.
しかして、原子炉圧力容器1内の原子炉水は再循環系配
管7の循環ポンプ8により炉心2を中心に強制的に流さ
れて加熱される。また原子炉水中の不純物を除去するた
めに原子炉水は浄化系入口配管10,11から再生熱交換器1
3で温度を低下させ、さらに非再生熱交換器14でイオン
交換樹脂が働き得る温度約80℃以下まで温度を低下させ
てからイオン交換樹脂を充填したろ過脱塩装置15を通し
て高純度化する。Then, the reactor water in the reactor pressure vessel 1 is forcibly flown around the core 2 by the circulation pump 8 of the recirculation system pipe 7 to be heated. In addition, in order to remove impurities in the reactor water, the reactor water is fed from the purification system inlet pipes 10 and 11 to the regenerative heat exchanger 1.
The temperature is lowered at 3 and further lowered to about 80 ° C. or lower at which the ion exchange resin can work in the non-regenerated heat exchanger 14, and then highly purified through a filter desalting apparatus 15 filled with the ion exchange resin.
その後、高純度化された冷却材を再生熱交換器13を通し
温度を上昇させて浄化系出口配管16から給水配管3に接
続し原子炉圧力容器1内に戻す。Then, the highly purified coolant is passed through the regenerative heat exchanger 13 to raise the temperature, connected from the purification system outlet pipe 16 to the feed water pipe 3, and returned to the reactor pressure vessel 1.
この場合、浄化系ポンプ12は従来は第1図に示したよう
に温度の高い浄化系入口配管10,11に設けられていた
が、これはポンプ12の余裕をとった揚程での設計を行な
っていたためである。しかしながら、本発明では前述し
たように浄化系ポンプ12を再生熱交換器13の出口配管13
aの間に設けているため浄化系ポンプの保守点検による
放射線被曝量を従来の1/10に低減できる。In this case, the purification system pump 12 has conventionally been provided in the purification system inlet pipes 10 and 11 having a high temperature as shown in FIG. 1, but this is designed with a head with a margin of the pump 12. Because it was. However, in the present invention, as described above, the purification system pump 12 is connected to the outlet pipe 13 of the regenerative heat exchanger 13.
Since it is provided between a and, the radiation exposure dose due to the maintenance and inspection of the purification system pump can be reduced to 1/10 of the conventional level.
第3図は従来の原子炉浄化系の系統構成において、該系
統の温度と系統表面線量率との関係を示している。FIG. 3 shows the relationship between the system temperature and the system surface dose rate in the system configuration of the conventional reactor cleaning system.
系統表面線量率は個人の被曝線量に直接関係する値であ
る。図中、縦軸は表面線量率を対数で示し、横軸はろ水
の温度である。図から明らかなように230℃近くと280℃
近くの測定値で1桁以上の差があり、230℃以下では低
い値になっている。これは、温度280℃近くに比較して
温度230℃以下になると、配管内部に酸化皮膜の形成さ
れる割合が減少し、従ってこの酸化皮膜に取り込まれる
Co-60等の放射性同位元素の割合が低下するからであ
る。The system surface dose rate is a value that is directly related to the individual radiation dose. In the figure, the vertical axis represents the surface dose rate logarithmically, and the horizontal axis represents the temperature of the filtered water. As you can see from the figure, near 230 ℃ and 280 ℃
There is a difference of one digit or more in the nearby measured values, and it is low at 230 ° C or lower. This is because when the temperature becomes 230 ° C or lower compared to the temperature near 280 ° C, the rate of oxide film formation inside the pipe decreases, and therefore it is taken into this oxide film.
This is because the ratio of radioisotopes such as Co-60 decreases.
一方、浄化系ポンプ12は280℃近くで運転されているた
め、表面線量率は高く被曝線量率を高くする要因になっ
ている。On the other hand, since the purification system pump 12 is operated near 280 ° C., the surface dose rate is high, which is a factor of increasing the exposure dose rate.
したがって、本発明は浄化系ポンプ12を再生熱交換器13
の下流側に設けて該ポンプの温度230℃以下で運転でき
るため浄化系ポンプ12の保守点検などの作業による放射
線被曝量を1桁近く低くできる。Therefore, according to the present invention, the purification system pump 12 is replaced by the regenerative heat exchanger 13.
Since it is provided on the downstream side of the pump and can be operated at a temperature of 230 ° C. or less, the radiation exposure dose due to the maintenance and inspection of the purification system pump 12 can be reduced by almost one digit.
本発明は上記第2図に示した実施例に限ることなく、下
記の例についても適用できる。The present invention can be applied not only to the embodiment shown in FIG. 2 but also to the following examples.
(1)浄化系ポンプ12は非再生熱交換器14の下流側配管
に設けること。(1) The purification system pump 12 should be provided in the downstream pipe of the non-regenerative heat exchanger 14.
(2)原子炉循環系が存在しない原子力発電プラントに
おいて、原子炉圧力容器から直接取出して系統を構成し
た場合、または他の系統から分岐して系統を構成した場
合。(2) In a nuclear power plant where a reactor circulation system does not exist, when the system is constructed by directly extracting it from the reactor pressure vessel or branching from another system to construct the system.
[発明の効果] 本発明によれば従来の浄化系ポンプの保守点検時の放射
線被曝量を1/10に低減でき、また原子力発電プラント全
体の4〜9%の被曝低減化をはかることができる。さら
に原子炉再循環系が存在しないプラントでは全体の放射
線被曝量が従来の70%程度と考えられており、本発明の
寄与率はプラント全体の5〜12%の被曝低減化ができ
る。[Advantages of the Invention] According to the present invention, the radiation exposure dose at the time of maintenance and inspection of the conventional purification system pump can be reduced to 1/10, and the radiation exposure can be reduced by 4 to 9% of the entire nuclear power plant. . Further, in a plant without a reactor recirculation system, the total radiation dose is considered to be about 70% of the conventional level, and the contribution rate of the present invention can reduce the radiation dose by 5 to 12% of the entire plant.
第1図は従来の原子炉冷却材浄化系を説明するための系
統図、第2図は本発明に係る原子炉冷却材浄化系の一実
施例を説明するための系統図、第3図は従来例と本発明
の作用効果を説明するためのグラフ図である。 1……原子炉圧力容器、2……炉心 3……給水配管、4……気水分離器 5……蒸気乾燥器、6……主蒸気配管 7……再循環系配管、8……再循環ポンプ 9……ジェットポンプ 10,11……浄化系入口配管 12……浄化系ポンプ、13……再生熱交換器 14……非再生熱交換器、15……ろ過脱塩装置 16……浄化系出口配管FIG. 1 is a system diagram for explaining a conventional reactor coolant purification system, FIG. 2 is a system diagram for explaining one embodiment of a reactor coolant purification system according to the present invention, and FIG. 3 is It is a graph figure for demonstrating the operation effect of a prior art example and this invention. 1 ... Reactor pressure vessel, 2 ... Reactor core, 3 ... Water supply pipe, 4 ... Steam separator, 5 ... Steam dryer, 6 ... Main steam pipe, 7 ... Recirculation system pipe, 8 ... Re Circulation pump 9 …… Jet pump 10,11 …… Purification system inlet piping 12 …… Purification system pump, 13 …… Regeneration heat exchanger 14 …… Non-regeneration heat exchanger, 15 …… Filtration desalination device 16 …… Purification System outlet piping
Claims (1)
原子炉再循環系あるいは他の冷却材流通系から分岐され
た浄化系入口配管と、この浄化系入口配管に連通された
再生熱交換器と、この再生熱交換器の下流側配管に設置
された非再生熱交換器と、この非再生熱交換器の下流側
配管に設置されたろ過脱塩装置と、このろ過脱塩装置の
下流側に連通され前記再生熱交換器を介して前記沸騰水
型原子炉圧力容器の冷却材流通系に接続された浄化系出
口配管と、前記再生熱交換器の下流側配管または前記非
再生熱交換器の下流側配管に設置されしかも前記ろ過脱
塩装置の上流側配管に配置されプラント運転時およびプ
ラント停止時に稼動される浄化系ポンプとを有すること
を特徴とする原子炉冷却材浄化系。1. A purification system inlet pipe branched from a drain system or a reactor recirculation system of a boiling water reactor pressure vessel or another coolant distribution system, and regenerative heat exchange communicated with this purification system inlet pipe. Unit, a non-regenerative heat exchanger installed in the downstream pipe of the regenerative heat exchanger, a filtration desalination device installed in the downstream pipe of the non-regeneration heat exchanger, and a downstream of the filtration desalination device. Side outlet pipe connected to the coolant circulation system of the boiling water reactor pressure vessel through the regenerative heat exchanger, and a downstream side pipe of the regenerative heat exchanger or the non-regenerative heat exchange And a purification system pump which is installed in a downstream side pipe of the reactor and is arranged in an upstream side pipe of the filter desalination apparatus and which is operated during plant operation and plant stoppage.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP59047249A JPH06100671B2 (en) | 1984-03-14 | 1984-03-14 | Reactor coolant purification system |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP59047249A JPH06100671B2 (en) | 1984-03-14 | 1984-03-14 | Reactor coolant purification system |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS60192297A JPS60192297A (en) | 1985-09-30 |
| JPH06100671B2 true JPH06100671B2 (en) | 1994-12-12 |
Family
ID=12769974
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP59047249A Expired - Lifetime JPH06100671B2 (en) | 1984-03-14 | 1984-03-14 | Reactor coolant purification system |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH06100671B2 (en) |
Family Cites Families (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5331097A (en) * | 1976-09-02 | 1978-03-23 | Toshiba Corp | Coolant purificating device in reactor |
-
1984
- 1984-03-14 JP JP59047249A patent/JPH06100671B2/en not_active Expired - Lifetime
Also Published As
| Publication number | Publication date |
|---|---|
| JPS60192297A (en) | 1985-09-30 |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| EXPY | Cancellation because of completion of term |