JPH0194294A - Plugging device - Google Patents
Plugging deviceInfo
- Publication number
- JPH0194294A JPH0194294A JP62251914A JP25191487A JPH0194294A JP H0194294 A JPH0194294 A JP H0194294A JP 62251914 A JP62251914 A JP 62251914A JP 25191487 A JP25191487 A JP 25191487A JP H0194294 A JPH0194294 A JP H0194294A
- Authority
- JP
- Japan
- Prior art keywords
- plugging device
- circulating water
- high temperature
- fuel
- adsorbent
- 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
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 24
- 239000003463 adsorbent Substances 0.000 claims abstract description 23
- 239000000446 fuel Substances 0.000 claims abstract description 13
- 239000000463 material Substances 0.000 claims abstract description 8
- 239000000919 ceramic Substances 0.000 claims description 5
- 229910003077 Ti−O Inorganic materials 0.000 claims description 3
- 238000001179 sorption measurement Methods 0.000 abstract description 7
- 230000002285 radioactive effect Effects 0.000 abstract description 6
- 230000000694 effects Effects 0.000 abstract description 5
- 230000007423 decrease Effects 0.000 abstract description 4
- 230000004992 fission Effects 0.000 abstract description 2
- 238000003780 insertion Methods 0.000 abstract description 2
- 230000037431 insertion Effects 0.000 abstract description 2
- 239000002250 absorbent Substances 0.000 abstract 1
- 230000002745 absorbent Effects 0.000 abstract 1
- 239000002826 coolant Substances 0.000 abstract 1
- 230000003247 decreasing effect Effects 0.000 abstract 1
- 239000003758 nuclear fuel Substances 0.000 abstract 1
- 230000009467 reduction Effects 0.000 description 7
- 238000000429 assembly Methods 0.000 description 5
- 230000000712 assembly Effects 0.000 description 5
- 238000000746 purification Methods 0.000 description 5
- 238000006243 chemical reaction Methods 0.000 description 4
- 239000000498 cooling water Substances 0.000 description 3
- 238000000034 method Methods 0.000 description 3
- 230000005855 radiation Effects 0.000 description 3
- 239000000126 substance Substances 0.000 description 3
- 239000011248 coating agent Substances 0.000 description 2
- 238000000576 coating method Methods 0.000 description 2
- 229910017052 cobalt Inorganic materials 0.000 description 2
- 239000010941 cobalt Substances 0.000 description 2
- GUTLYIVDDKVIGB-UHFFFAOYSA-N cobalt atom Chemical compound [Co] GUTLYIVDDKVIGB-UHFFFAOYSA-N 0.000 description 2
- 238000005260 corrosion Methods 0.000 description 2
- 230000007797 corrosion Effects 0.000 description 2
- 239000000284 extract Substances 0.000 description 2
- 239000003456 ion exchange resin Substances 0.000 description 2
- 229920003303 ion-exchange polymer Polymers 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
- 238000010521 absorption reaction Methods 0.000 description 1
- 238000005229 chemical vapour deposition Methods 0.000 description 1
- 239000000470 constituent Substances 0.000 description 1
- 229910052802 copper Inorganic materials 0.000 description 1
- 230000001419 dependent effect Effects 0.000 description 1
- 238000010612 desalination reaction Methods 0.000 description 1
- 238000000605 extraction Methods 0.000 description 1
- 150000002500 ions Chemical class 0.000 description 1
- 239000002184 metal Substances 0.000 description 1
- 229910052751 metal Inorganic materials 0.000 description 1
- 229910021645 metal ion Inorganic materials 0.000 description 1
- 239000004033 plastic Substances 0.000 description 1
- 229920003023 plastic Polymers 0.000 description 1
- 230000002250 progressing effect Effects 0.000 description 1
- 230000001737 promoting effect Effects 0.000 description 1
- 230000002787 reinforcement Effects 0.000 description 1
- 230000002441 reversible effect Effects 0.000 description 1
- 238000002336 sorption--desorption measurement Methods 0.000 description 1
- 239000002915 spent fuel radioactive waste Substances 0.000 description 1
- 238000007740 vapor deposition Methods 0.000 description 1
- 239000002699 waste material 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
- Y02E30/30—Nuclear fission reactors
Landscapes
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
Description
【発明の詳細な説明】
（産業上の利用分野）
本発明はＰＷＲ（加圧水型原子炉）の燃料に内挿して使
用するプラッギングデバイスに関するものである。DETAILED DESCRIPTION OF THE INVENTION (Field of Industrial Application) The present invention relates to a plugging device used by being inserted into the fuel of a PWR (pressurized water reactor).
（従来の技術）
原子力発電所では従業員の被爆低減化対策は最も重要な
課題の１つであり、そのための方策として１次冷却水中
に含まれる極く微量の放射性腐食生成物、とくにコバル
）−５８，−６０核種濃度をより低くすること、即ち炉
水の浄化を強化することが講ぜられている。(Conventional technology) One of the most important issues at nuclear power plants is to reduce the exposure of employees to radiation, and one of the measures to achieve this is to reduce the amount of radioactive corrosion products contained in the primary cooling water, especially Kobal). Efforts are being made to lower the concentration of -58 and -60 nuclides, that is, to strengthen the purification of reactor water.
ところで、現在、行われているＰＷＲの炉水浄化システ
ムは１次系循環炉水の一部を抽出して減圧・減温し、こ
れを脱塩塔に通し、ここで、コバルトを始めとする腐食
生成物をイオン交換樹脂に吸着させる方式である。By the way, the current PWR reactor water purification system extracts a portion of the primary circulating reactor water, reduces its pressure and temperature, and passes it through a desalination tower, where it extracts cobalt and other substances. This method allows corrosion products to be adsorbed onto ion exchange resin.
しかし、このシステムはその減圧・減温のための設備増
強やプラント熱効率低下などによりコストアップを考え
れば炉水浄化の強化（抽出流量の増加）に限度がある。However, this system has a limit to how much it can strengthen reactor water purification (increase in extraction flow rate), considering the cost increase due to increased equipment for depressurization and temperature reduction, and a decrease in plant thermal efficiency.
そこで、近時、上記システムに対し、減圧・滅温の制約
がなくなり、少ないコストで浄化の強化、即ち、被爆低
減化が可能になる方式が研究され、ＰＷＲＩ次系冷却水
の温度、圧力、水質環境下（−３００°Ｃ、１６０ｋｇ
／ ｃｔＭ Ｇ・はう酸水）で、その中に含まれるコバ
ルトを効率よく吸着する機能を有する材料の開発が進め
られ、現在、かかる吸着材としてＦｅ−Ｔｉ−Ｏセラミ
ックスが選定されている。Therefore, recently, research has been conducted on a method that eliminates the restrictions on depressurization and temperature reduction for the above system, and enables enhanced purification at low cost, that is, reduced exposure. Under water quality environment (-300°C, 160kg
The development of materials that have the ability to efficiently adsorb cobalt contained therein has been progressing, and currently Fe-Ti-O ceramics have been selected as such adsorbents.
（発明が解決しようとする問題点）
本発明は畝上の如き実状に鑑み、特に上記吸着材の効果
的な適用化を課題とし、ＰＷＲで燃料集合体の内挿物と
して使用されているプラツギングデバイスに上記高温吸
着材を適用して１次系循環水の浄化を実施し、従業員の
被爆低減をはかることを目的とするものである。(Problems to be Solved by the Invention) In view of the actual situation of ridges, the present invention aims to effectively apply the above-mentioned adsorbent, and aims to effectively apply the above-mentioned adsorbent to plastics used as an interpolant of fuel assemblies in PWR. The purpose of this project is to apply the above-mentioned high-temperature adsorbent to a tugging device to purify primary circulating water and reduce the exposure of employees to radiation.
プラッギングデバイスは云うまでもなく燃料集合体にお
いて可燃吸収棒集合体と共に燃料内挿物と呼ばれている
もので、原子炉運転時に制御棒集合体の挿入操作の予定
されていない燃料集合体に対してその制御棒案内管の上
部に挿入されてこれを塞ぐものである。Needless to say, plugging devices are called fuel inserts together with combustible absorption rod assemblies in fuel assemblies, and are inserted into fuel assemblies for which insertion of control rod assemblies is not planned during reactor operation. It is inserted into the upper part of the control rod guide tube and closes it.
これは空の制御棒案内管を通って１次冷却水が必要以上
に流れてしまうと、燃料棒に対する有効冷却水量が確保
できなくなるためで、プラッギングデバイスによって制
御棒案内管をプラグすることによってこれを防止するの
である。This is because if the primary cooling water flows through the empty control rod guide tube more than necessary, it becomes impossible to secure an effective amount of cooling water for the fuel rods, so by plugging the control rod guide tube with a plugging device, this can be prevented. This is to prevent
しかし、かかる役割を有するプラッギングデバイスは従
来、一般に金属で作られており、上述の如く放射性核種
を吸着し、被爆低下に寄与するという効果は全く考えら
れていなかった。However, plugging devices that have such a role have conventionally been generally made of metal, and as described above, the effect of adsorbing radionuclides and contributing to a reduction in radiation exposure has not been considered at all.
本発明はかかるプラッギングデバイスに対し、前記吸着
材効果を適用しようとするものである。The present invention attempts to apply the adsorbent effect to such a plugging device.
（問題点を解決するための手段）
即ち、上記目的に適合する本発明の特徴とするところは
、前記放射性核種を原子炉の雰囲気中で吸着する高温吸
着材をＰＷＲの燃料に内挿して使用されるプラッギング
デバイスの少なくとも表面に使用する点にある。(Means for Solving the Problems) That is, the feature of the present invention that meets the above objectives is that a high-temperature adsorbent that adsorbs the radionuclides in the atmosphere of a nuclear reactor is used by inserting it into the PWR fuel. at least the surface of the plugging device to be used.
ここで、少なくとも表面に使用するとはプラッギングデ
バイスの材料として使用してもよ（、又表面にコーティ
ングして使用してもよいとの両者を含むことを意味する
。なお、コーティングの方法としては物理蒸着法、化学
的蒸着法など既知の手段が適用される。Here, "used at least on the surface" means that it may be used as a material for a plugging device (and may also be used by coating it on the surface). Known methods such as vapor deposition and chemical vapor deposition can be applied.
用いられる高温吸着材としては、例えばさきに述べた如
きＦｅ−Ｔｉ−Ｏセラミックスが選定される。As the high-temperature adsorbent used, for example, Fe--Ti--O ceramics as mentioned above are selected.
（作用）
上記の如く高温吸着材を用いたブラッギングデバイスを
ＰＷＲの燃料の内挿物として原子炉の炉心へ装荷し、原
子炉を運転すると、燃料は核分裂を起こし、また炉心構
成材料は放射化するために炉心を流れる１次系循環水は
放射性の核種を含むようになるが、循環水の通路に上記
プラッギングデバイスがあるので、放射性核種は高温吸
着材に吸着されることになる。(Function) When a bragging device using a high-temperature adsorbent as described above is loaded into the core of a nuclear reactor as an interpolant of PWR fuel and the reactor is operated, the fuel undergoes nuclear fission and the core constituent materials emit radiation. The primary circulating water flowing through the reactor core comes to contain radioactive nuclides, but since the plugging device is present in the circulating water passage, the radioactive nuclides are adsorbed by the high-temperature adsorbent.
そのため、循環水に含まれる放射性核種の量が減り、放
射能濃度が小さくなる。Therefore, the amount of radionuclides contained in the circulating water is reduced, and the radioactivity concentration is reduced.
従って、循環水の流れている配管付近の線量率が低くな
り配管付近で作業を行っている作業員の被爆が低減され
る。Therefore, the dose rate near the pipes through which the circulating water flows is lowered, and the exposure of workers working near the pipes is reduced.
なお、吸着される放射性核種の形態としては、Ｇｏ ＋
Ｎｉ ＋ Ｍｎ ＋ ＣｕおよびＦｅ（２価イオン）
であり、吸着の原理としては上記金属イオンが吸着材で
あるＦｅ−Ｔｉ−Ｏセラミックスに対し、化学吸着反応
を起こし、その表面に化学的結合力によって保持される
ことによる！この場合、高温というのは炉心内の環境で
吸着反応を起こすことから、又、吸着性能は温度依存性
を有し、高温の方が吸着量が大きいことからである。The form of the adsorbed radionuclide is Go +
Ni + Mn + Cu and Fe (divalent ions)
The principle of adsorption is that the metal ions cause a chemical adsorption reaction on the adsorbent, Fe-Ti-O ceramics, and are held on the surface by chemical bonding force! In this case, the high temperature is because an adsorption reaction occurs in the environment within the reactor core, and also because the adsorption performance is temperature dependent and the amount of adsorption is larger at higher temperatures.
一方、高温水中で吸着されたものはイオン交換樹脂にお
ける可逆的吸・脱着反応とは対照的な極めて強固な化学
吸着反応が起こっていることから容易に再溶離すること
はない。On the other hand, those adsorbed in high-temperature water are not easily re-eluted because an extremely strong chemisorption reaction occurs, which is in contrast to the reversible adsorption/desorption reaction in ion exchange resins.
（実施例）
以下、添付図面を参照し、本発明のプラッギングデバイ
スの実施例を説明する。(Embodiments) Hereinafter, embodiments of the plugging device of the present invention will be described with reference to the accompanying drawings.
図は本発明において、前記高温吸着材を材料として使用
したプラッギングデバイス（１）の１例であり、プラッ
ギングデバイス（１）としては図系構造に限られるもの
ではないが、何れも前記Ｆｅ−Ｔｉ−Ｏセラミックスの
如き高温吸着材を材料として使用す６一
るか、又は上記高温吸着材をその表面に既知の手段によ
りコーティングすることによって１次系循環水が接触す
る部位に上記高温吸着材が用いられていることが肝要で
ある。The figure is an example of a plugging device (1) using the above-mentioned high-temperature adsorbent as a material in the present invention, and the plugging device (1) is not limited to the diagrammatic structure, - By using a high-temperature adsorbent such as O ceramics as a material, or by coating the surface of the high-temperature adsorbent by known means, the high-temperature adsorbent is placed in the area where the primary circulating water comes into contact. It is important that it is used.
従って、原子炉を運転するとき、１次系循環水の通路に
プラッギングデバイスの高温吸着材が存在することにな
り、放射性核種の吸着が達成される。Therefore, when operating a nuclear reactor, the high-temperature adsorbent of the plugging device is present in the path of the primary circulating water, and adsorption of radionuclides is achieved.
（発明の効果）
本発明は以上の如く放射性核種を原子炉の雰囲気中で吸
着する高温吸着材をプラツギングデバイスの材料として
使用し、又は、その表面にコーティングしたものであり
、従来の炉水浄化システムでは減圧・減温のための設備
増強、プラント熱効率低下などによるコストアップを始
め種々の問題があったが、プラツギングデバイスに上記
の如く高温吸着材を使用したことにより従来における減
圧・減温の制約がなくなり、設備の増強、熱効率低下な
どを要することなく炉水の浄化を実施することができ、
循環水の配管などのまわりで作業する従業員の被爆低減
が可能となり、原子カプラントの高度化推進に顕著な効
果が期待される。(Effects of the Invention) As described above, the present invention uses a high-temperature adsorbent that adsorbs radionuclides in the atmosphere of a nuclear reactor as a material for a plugging device, or coats the surface of the plugging device. Water purification systems have had various problems, including increased costs due to increased equipment for pressure reduction and temperature reduction, and reduced plant thermal efficiency. - Restrictions on temperature reduction are eliminated, and reactor water can be purified without the need for equipment reinforcement or reductions in thermal efficiency.
This will make it possible to reduce radiation exposure for employees working around circulating water piping, and is expected to have a significant effect on promoting the advancement of nuclear couplants.
又、放射性核種はプラッギングデバイスに吸着されるが
、燃料集合体とは別体であるために使用済燃料の放射能
レベルを上げることもなく、廃棄物としての処理もプラ
ッギングデバイスは別個に行えるので頗る好都合である
。In addition, radionuclides are adsorbed by the plugging device, but since it is separate from the fuel assembly, it does not increase the radioactivity level of the spent fuel, and the plugging device can be disposed of as waste separately. This is extremely convenient.
図は本発明の適用に係るプラッギングデバイスの１例を
示す正面図である。
（１）・・・プラッギングデバイスThe figure is a front view showing an example of a plugging device to which the present invention is applied. (1)...Plugging device
Claims (1)
ングデバイスにおいて、少なくとも１次系循環水に接す
るその表面を放射性核種を原子炉の雰囲気中で吸着する
高温吸着材により形成せしめたことを特徴とするプラッ
ギングデバィス。 ２、高温吸着材が、Ｆｅ−Ｔｉ−Ｏセラミックスである
特許請求の範囲第１項記載のプラッギングデバイス。 ３、高温吸着材をプラッギングデバイスの材料として使
用する特許請求の範囲第１又は第２項記載のプラッギン
グデバイス。 ４、高温吸着材をプラッギングデバイスの表面にコーテ
ィングする特許請求の範囲第１項又は第２項記載のプラ
ッギングデバイス。[Claims] 1. In a plugging device used by being inserted into the fuel of a pressurized water reactor, at least its surface in contact with the primary circulating water is covered with a high-temperature adsorbent that adsorbs radionuclides in the atmosphere of the reactor. A plugging device characterized by forming a plugging device. 2. The plugging device according to claim 1, wherein the high temperature adsorbent is Fe-Ti-O ceramics. 3. The plugging device according to claim 1 or 2, which uses a high-temperature adsorbent as a material of the plugging device. 4. The plugging device according to claim 1 or 2, wherein the surface of the plugging device is coated with a high temperature adsorbent.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP62251914A JPH0194294A (en) | 1987-10-05 | 1987-10-05 | Plugging device |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP62251914A JPH0194294A (en) | 1987-10-05 | 1987-10-05 | Plugging device |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH0194294A true JPH0194294A (en) | 1989-04-12 |
Family
ID=17229840
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP62251914A Pending JPH0194294A (en) | 1987-10-05 | 1987-10-05 | Plugging device |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH0194294A (en) |
-
1987
- 1987-10-05 JP JP62251914A patent/JPH0194294A/en active Pending
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