JPH022520B2 - - Google Patents
Info
- Publication number
- JPH022520B2 JPH022520B2 JP19241981A JP19241981A JPH022520B2 JP H022520 B2 JPH022520 B2 JP H022520B2 JP 19241981 A JP19241981 A JP 19241981A JP 19241981 A JP19241981 A JP 19241981A JP H022520 B2 JPH022520 B2 JP H022520B2
- Authority
- JP
- Japan
- Prior art keywords
- piping
- recirculation
- radioactive fluid
- radioactive
- 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
Links
- 239000012530 fluid Substances 0.000 claims description 12
- 230000002285 radioactive effect Effects 0.000 claims description 12
- 239000002826 coolant Substances 0.000 claims description 8
- 238000005498 polishing Methods 0.000 claims description 7
- 238000000746 purification Methods 0.000 claims description 4
- 239000000941 radioactive substance Substances 0.000 description 8
- 238000005260 corrosion Methods 0.000 description 7
- 230000007797 corrosion Effects 0.000 description 7
- 230000032683 aging Effects 0.000 description 2
- 238000007689 inspection Methods 0.000 description 2
- 239000002184 metal Substances 0.000 description 2
- 230000000737 periodic effect Effects 0.000 description 2
- 230000002093 peripheral effect Effects 0.000 description 2
- 230000008439 repair process Effects 0.000 description 2
- 238000009825 accumulation Methods 0.000 description 1
- 238000009835 boiling Methods 0.000 description 1
- 238000007796 conventional method Methods 0.000 description 1
- 238000005202 decontamination Methods 0.000 description 1
- 230000003588 decontaminative effect Effects 0.000 description 1
- 230000003247 decreasing effect Effects 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 230000005855 radiation Effects 0.000 description 1
- 239000012857 radioactive material Substances 0.000 description 1
- 229910001220 stainless steel Inorganic materials 0.000 description 1
- 239000010935 stainless steel Substances 0.000 description 1
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 1
Classifications
-
- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F16—ENGINEERING ELEMENTS AND UNITS; GENERAL MEASURES FOR PRODUCING AND MAINTAINING EFFECTIVE FUNCTIONING OF MACHINES OR INSTALLATIONS; THERMAL INSULATION IN GENERAL
- F16L—PIPES; JOINTS OR FITTINGS FOR PIPES; SUPPORTS FOR PIPES, CABLES OR PROTECTIVE TUBING; MEANS FOR THERMAL INSULATION IN GENERAL
- F16L58/00—Protection of pipes or pipe fittings against corrosion or incrustation
Landscapes
- Engineering & Computer Science (AREA)
- General Engineering & Computer Science (AREA)
- Mechanical Engineering (AREA)
- Protection Of Pipes Against Damage, Friction, And Corrosion (AREA)
- Rigid Pipes And Flexible Pipes (AREA)
- Preventing Corrosion Or Incrustation Of Metals (AREA)
Description
【発明の詳細な説明】
本発明は、放射性流体を流通する放射性流体用
配管に関する。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to radioactive fluid piping through which radioactive fluid flows.
例えば、沸騰水形原子炉には、原子炉圧力容器
に冷却材を再循環する原子炉再循環系が配設さ
れ、また、この原子炉再循環系内の冷却材を浄化
するために原子炉冷却材浄化系が配設されてい
る。 For example, a boiling water reactor is equipped with a reactor recirculation system that recirculates coolant to the reactor pressure vessel, and the reactor recirculation system is installed to purify the coolant within the reactor pressure vessel. A coolant purification system is installed.
これらの系は、一般に各種機器とこれらの機器
を接続する配管とから構成されているが、従来の
配管では、時間の経過とともに、配管の内面が腐
蝕され、、この部分にいわゆる腐蝕層が形成され
る。このような腐蝕層が形成される場合には、冷
却材中のイオン状の放射性物質は、腐蝕層中の金
属と交換反応をし、腐蝕層中に取り込まれる。 These systems generally consist of various devices and piping that connects these devices, but with conventional piping, the inner surface of the piping corrodes over time, causing a so-called corrosion layer to form in this area. be done. When such a corroded layer is formed, the ionic radioactive substance in the coolant undergoes an exchange reaction with the metal in the corroded layer and is incorporated into the corroded layer.
したがつて、時間の経過とともに、配管内に
は、放射性物質が蓄積することとなり、例えば前
述した原子炉再循環系、冷却材浄化系等の定期点
検時または、補修時等における作業員の被曝量
は、年々増加することとなる。 Therefore, over time, radioactive materials accumulate in the pipes, and for example, workers may be exposed to radiation during periodic inspections or repairs of the reactor recirculation system, coolant purification system, etc. mentioned above. The amount will increase year by year.
本発明はかかる従来の事情に対処してなされた
もので、放射性流体との接触面に電解研摩加工を
施したことを特徴とする放射性流体用配管を提供
しようとするものである。 The present invention has been made in response to the conventional situation, and aims to provide a radioactive fluid piping characterized in that the surface in contact with the radioactive fluid is subjected to electrolytic polishing.
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。 DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS The details of the present invention will be described below with reference to an embodiment shown in the drawings.
第１図において、符号１は炉心２を収容する原
子炉圧力容器を示しており、炉心２の両側には、
ジエツトポンプ３が配設されている。 In FIG. 1, reference numeral 1 indicates a reactor pressure vessel housing a reactor core 2, and on both sides of the reactor core 2,
A jet pump 3 is provided.
ジエツトポンプ３の上端に形成される流入口
４、およびジエツトポンプ３の側方に形成される
流出口５には、再循環配管６が接続されており、
この再循環配管６には、再循環ポンプ７が配設さ
れている。 A recirculation pipe 6 is connected to an inlet 4 formed at the upper end of the jet pump 3 and an outlet 5 formed at the side of the jet pump 3.
A recirculation pump 7 is installed in this recirculation pipe 6 .
再循環配管６は、例えばステンレス鋼から構成
されており、その内周面は、研削加工された後、
電解研摩により鏡面仕上げされている。 The recirculation pipe 6 is made of, for example, stainless steel, and the inner circumferential surface of the recirculation pipe 6 is ground.
Mirror-finished by electrolytic polishing.
以上のように構成された再循環配管６では、こ
の配管内を放射性流体、すなわち原子炉圧力容器
１内の放射性物質を含んだ冷却材が循環すること
となるが、再循環配管６内周面が電解研摩により
鏡面仕上げされているため、従来の再循環配管に
比較して、内周面の腐蝕は、非常に小さいものと
なり、この結果イオン状の放射性物質と腐蝕層中
の金属との交換反応は減少し、再循環配管６内周
面への放射性物質の蓄積は、従来に比較して大巾
に減少する。 In the recirculation pipe 6 configured as described above, the radioactive fluid, that is, the coolant containing radioactive substances in the reactor pressure vessel 1, circulates inside the pipe. Since the pipe is polished to a mirror finish by electrolytic polishing, corrosion on the inner peripheral surface is extremely small compared to conventional recirculation piping, and as a result, the exchange of ionic radioactive substances with the metal in the corroded layer is reduced. The reaction is reduced, and the accumulation of radioactive substances on the inner circumferential surface of the recirculation pipe 6 is greatly reduced compared to the conventional method.
第２図に示す曲線ａは、以上のように構成され
た再循環配管６の腐蝕率を経過とともに示すもの
で、横軸には時間が縦軸には腐蝕率が採られてい
る。 A curve a shown in FIG. 2 shows the corrosion rate of the recirculation pipe 6 configured as described above over time, with time on the horizontal axis and corrosion rate on the vertical axis.
なお、第２図において曲線ｂは、従来の再循環
配管を、曲線ｃは、研削加工のみで電解研摩の行
なわれていない再循環配管を示している。 In FIG. 2, curve b shows a conventional recirculation pipe, and curve c shows a recirculation pipe that has been subjected to only grinding and no electrolytic polishing.
この図から明らかなように、内周面に電解研摩
の施こされた再循環配管６では、経年変化による
腐蝕率が大巾に減少している。 As is clear from this figure, the corrosion rate due to aging is significantly reduced in the recirculation pipe 6 whose inner peripheral surface has been electrolytically polished.
また第３図に示す曲線ｄは、以上のように構成
された再循環配管６の付着放射能量を時間の経過
とともに示すもので横軸には時間が縦軸には付着
放射能量が採られている。なお、第３図において
時間の単位としてEFPY（Effective Full Power
Year）が用いられている。 Further, the curve d shown in FIG. 3 shows the amount of radioactivity attached to the recirculation pipe 6 configured as described above over time, with time on the horizontal axis and the amount of radioactivity attached on the vertical axis. There is. In addition, in Figure 3, the unit of time is EFPY (Effective Full Power
Year) is used.
また、第３図において、曲線ｅは従来の再循環
配管を、曲線ｆは、研削加工のみで電解研摩の行
なわれていない再循環配管で示している。 Further, in FIG. 3, the curve e shows the conventional recirculation piping, and the curve f shows the recirculation piping that has been subjected to only grinding and no electrolytic polishing.
この図から明らかなように、内周面に電解研摩
の施こされた再循環配管６では、経年変化による
付着放射能量が大巾に減少している。さらに、鏡
面仕上げをした配管に付着する粒子状の放射性物
質は、従来の配管に比べて容易に除去できるの
で、除染を実施する際に、作業時間の短縮、すな
わち作業員の被曝量を低く抑えることができる。 As is clear from this figure, in the recirculation pipe 6 whose inner circumferential surface has been subjected to electrolytic polishing, the amount of adhering radioactivity due to aging has significantly decreased. In addition, the particulate radioactive substances that adhere to mirror-finished piping can be removed more easily than from conventional piping, so when carrying out decontamination, it is possible to shorten the work time and lower the radiation exposure of workers. It can be suppressed.
以上述べたように、本発明によれば、放射性流
体を流通する配管内の腐蝕を大巾に減少すること
ができ、この結果この腐蝕層に取り込まれるイオ
ン性の放射性物質の絶対量を非常に低く抑えるこ
とができるとともに粒子状の放射性物質の除去を
容易に行なうことができる。 As described above, according to the present invention, corrosion in piping through which radioactive fluid flows can be greatly reduced, and as a result, the absolute amount of ionic radioactive substances taken into this corroded layer can be greatly reduced. The amount of radioactive substances can be kept low, and particulate radioactive substances can be easily removed.
したがつて、配管の修理、定期点検時における
作業者の被曝量を大巾に減少することができる。 Therefore, the amount of radiation exposure to workers during pipe repair and periodic inspection can be significantly reduced.
なお、以上述べた実施例では、再循環配管に本
発明を適用した例について述べたが、本発明は、
かかる実施例に限定されるものではなく、例え
ば、原子炉冷却材浄化系を構成する配管に適用し
ても同様の効果を得られることは勿論である。 In addition, in the embodiment described above, an example was described in which the present invention was applied to recirculation piping, but the present invention
It goes without saying that the present invention is not limited to such embodiments, and that similar effects can be obtained even if the present invention is applied to, for example, piping constituting a nuclear reactor coolant purification system.
第１図は、本発明の適用される再循環配管の説
明図、第２図は、時間の経過にともなう腐蝕率の
変化を示すグラフ、第３図は、時間の経過にとも
なう付着放射能量の変化を示すグラフである。
１……原子炉圧力容器、２……炉心、３……ジ
エツトポンプ、６……再循環配管。
Figure 1 is an explanatory diagram of recirculation piping to which the present invention is applied, Figure 2 is a graph showing changes in corrosion rate over time, and Figure 3 is a graph showing changes in the amount of attached radioactivity over time. It is a graph showing changes. 1...Reactor pressure vessel, 2...Reactor core, 3...Jet pump, 6...Recirculation piping.
Claims (1)
たことを特徴とする放射性流体用配管。 ２ 放射性流体用配管は、原子炉再循環系を構成
する配管であることを特徴とする特許請求の範囲
第１項記載の放射性流体用配管。 ３ 放射性流体用配管は、原子炉冷却材浄化系を
構成する配管であることを特徴とする特許請求の
範囲第１項記載の放射性流体用配管。[Scope of Claims] 1. A radioactive fluid piping characterized in that the contact surface with the radioactive fluid is subjected to electrolytic polishing. 2. The radioactive fluid piping according to claim 1, wherein the radioactive fluid piping is a piping that constitutes a nuclear reactor recirculation system. 3. The radioactive fluid piping according to claim 1, wherein the radioactive fluid piping is a piping that constitutes a reactor coolant purification system.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP19241981A JPS5894692A (en) | 1981-11-30 | 1981-11-30 | Piping for radioactive fluid |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP19241981A JPS5894692A (en) | 1981-11-30 | 1981-11-30 | Piping for radioactive fluid |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS5894692A JPS5894692A (en) | 1983-06-04 |
| JPH022520B2 true JPH022520B2 (en) | 1990-01-18 |
Family
ID=16290999
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP19241981A Granted JPS5894692A (en) | 1981-11-30 | 1981-11-30 | Piping for radioactive fluid |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS5894692A (en) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS59126997A (en) * | 1983-01-12 | 1984-07-21 | 株式会社日立製作所 | Nuclear plant manufacturing method |
-
1981
- 1981-11-30 JP JP19241981A patent/JPS5894692A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS5894692A (en) | 1983-06-04 |
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