JPS63250598A - Method of removing sodium of fast-reactor core component - Google Patents
Method of removing sodium of fast-reactor core componentInfo
- Publication number
- JPS63250598A JPS63250598A JP8528487A JP8528487A JPS63250598A JP S63250598 A JPS63250598 A JP S63250598A JP 8528487 A JP8528487 A JP 8528487A JP 8528487 A JP8528487 A JP 8528487A JP S63250598 A JPS63250598 A JP S63250598A
- Authority
- JP
- Japan
- Prior art keywords
- sodium
- inert gas
- core components
- storage container
- reactor core
- 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.)
- Granted
Links
- DGAQECJNVWCQMB-PUAWFVPOSA-M Ilexoside XXIX Chemical compound C[C@@H]1CC[C@@]2(CC[C@@]3(C(=CC[C@H]4[C@]3(CC[C@@H]5[C@@]4(CC[C@@H](C5(C)C)OS(=O)(=O)[O-])C)C)[C@@H]2[C@]1(C)O)C)C(=O)O[C@H]6[C@@H]([C@H]([C@@H]([C@H](O6)CO)O)O)O.[Na+] DGAQECJNVWCQMB-PUAWFVPOSA-M 0.000 title claims description 80
- 239000011734 sodium Substances 0.000 title claims description 80
- 229910052708 sodium Inorganic materials 0.000 title claims description 80
- 239000008358 core component Substances 0.000 title claims description 49
- 238000000034 method Methods 0.000 title claims description 16
- 239000011261 inert gas Substances 0.000 claims description 42
- 239000000463 material Substances 0.000 claims description 10
- HEMHJVSKTPXQMS-UHFFFAOYSA-M Sodium hydroxide Chemical compound [OH-].[Na+] HEMHJVSKTPXQMS-UHFFFAOYSA-M 0.000 description 18
- 239000007789 gas Substances 0.000 description 18
- 238000004140 cleaning Methods 0.000 description 9
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 5
- 230000000712 assembly Effects 0.000 description 4
- 238000000429 assembly Methods 0.000 description 4
- 239000000446 fuel Substances 0.000 description 4
- 238000001816 cooling Methods 0.000 description 3
- 238000010586 diagram Methods 0.000 description 3
- 238000001704 evaporation Methods 0.000 description 3
- 230000008020 evaporation Effects 0.000 description 3
- 238000011084 recovery Methods 0.000 description 3
- 238000001771 vacuum deposition Methods 0.000 description 3
- 230000000694 effects Effects 0.000 description 2
- 238000010438 heat treatment Methods 0.000 description 2
- 239000007788 liquid Substances 0.000 description 2
- 239000002901 radioactive waste Substances 0.000 description 2
- 238000011144 upstream manufacturing Methods 0.000 description 2
- 239000002699 waste material Substances 0.000 description 2
- QVGXLLKOCUKJST-UHFFFAOYSA-N atomic oxygen Chemical compound [O] QVGXLLKOCUKJST-UHFFFAOYSA-N 0.000 description 1
- 239000000306 component Substances 0.000 description 1
- 238000007796 conventional method Methods 0.000 description 1
- 239000003595 mist Substances 0.000 description 1
- 239000001301 oxygen Substances 0.000 description 1
- 229910052760 oxygen Inorganic materials 0.000 description 1
- 230000005855 radiation Effects 0.000 description 1
- 239000000941 radioactive substance Substances 0.000 description 1
- 108010063955 thrombin receptor peptide (42-47) Proteins 0.000 description 1
- 238000007738 vacuum evaporation Methods 0.000 description 1
Landscapes
- Manufacture And Refinement Of Metals (AREA)
- Secondary Cells (AREA)
Abstract
(57)【要約】本公報は電子出願前の出願データであるた
め要約のデータは記録されません。(57) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.
Description
【発明の詳細な説明】
（産業上の利用分野）
本発明は、高速炉プラントの炉心燃料集合体である炉心
構成要素に付着しているナトリウムを除去する方法に関
する。DETAILED DESCRIPTION OF THE INVENTION (Industrial Application Field) The present invention relates to a method for removing sodium adhering to core components, which are core fuel assemblies of fast reactor plants.
（従来の技術）
高速炉プラントの炉心燃料集合体である炉心構成要素は
、使用後炉心容器から炉外中継槽に移され、さらに洗浄
槽で洗浄された後、水ブールに移されて貯蔵される。(Prior art) Core components, which are core fuel assemblies of fast reactor plants, are transferred from the core vessel to an external relay tank after use, and after being cleaned in a cleaning tank, they are transferred to a water tank and stored. Ru.
炉心構成要素を洗浄槽で洗浄してナトリウムを除去する
方法としては、従来湿潤不活性ガス洗浄法と真空蒸発法
がある。Conventional methods for removing sodium by cleaning core components in a cleaning tank include a wet inert gas cleaning method and a vacuum evaporation method.
湿潤不活性ガス洗浄法は、第４図に示す如く洗浄槽であ
る収納容器１に炉心構成要素２を収納し、収納容器１に
設けた循、環回路３に不活性ガスを送給し、途中加熱器
４にて加熱した後水蒸気を添加し、この混合ガスを収納
容器１中の炉心構成要素２に制御しながら吹き付けて、
付着しているナトリウムを、Ｎａ＋Ｈ２０→ＮａＯＨ＋
１／２）１２反応を利用して、水酸化ナトリウム（Ｎ
ａＯＨ）に変換し、温度上昇した混合ガスは収納容器１
から循環回路３に出て、途中冷却器５にて冷却され、ミ
ストトラップ６を経て、混合ガス中に蒸散している水酸
化ナトリウムが取り除かれた後ブロワ７にて送られ、加
熱器４を経て加熱され、再び゛収納容器１内の炉心構成
要素２に吹き付けて、付着しているナトリウムを水酸化
ナトリウムに変換する。こうして混合ガスの循環により
炉心構成要素２に付着しているナトリウムを完全に水酸
化ナトリウムに変換したならば、収納容器１内に純水を
洗浄水口路８を通して循環水ポンプ９にて供給循環させ
て炉心構成要素２を洗浄し、付着している水酸化ナトリ
ウムを洗い落す。In the wet inert gas cleaning method, as shown in FIG. 4, core components 2 are stored in a storage container 1, which is a cleaning tank, and inert gas is supplied to a circulation circuit 3 provided in the storage container 1. After heating in the intermediate heater 4, steam is added, and this mixed gas is blown onto the core components 2 in the storage vessel 1 in a controlled manner.
Remove the attached sodium from Na+H20→NaOH+
1/2) Using reaction 12, sodium hydroxide (N
The mixed gas, which has been converted into aOH) and whose temperature has risen, is stored in storage container 1.
The gas flows out into the circulation circuit 3, is cooled by a cooler 5, passes through a mist trap 6, removes the sodium hydroxide that has evaporated into the mixed gas, and is sent to a blower 7, where it is heated to a heater 4. The reactor core components 2 inside the storage vessel 1 are then heated and blown again to convert the adhering sodium into sodium hydroxide. Once the sodium adhering to the core components 2 has been completely converted into sodium hydroxide through the circulation of the mixed gas, pure water is supplied and circulated into the storage container 1 through the cleaning water port 8 using the circulating water pump 9. The reactor core components 2 are then cleaned to remove adhering sodium hydroxide.
真空蒸発法は、第５図に示す如く収納容器１内に炉心構
成要素２を収納し、収納容器１に設けた吸引回路１０の
真空ポンプユニット１１を駆動して収納容器１内の不活
性気体を吸引し、収納容器１内を真空にし、炉心構成要
素２に付着しているナトリウムを蒸発させ、ナトリウム
トラップ１３を経て気体に蒸散しているナトリウムが取
り除かれた後真空ポンプユニット１１より排気される。In the vacuum evaporation method, as shown in FIG. 5, the core components 2 are stored in a storage container 1, and the vacuum pump unit 11 of the suction circuit 10 provided in the storage container 1 is driven to remove inert gas from the storage container 1. The inside of the storage container 1 is vacuumed, the sodium adhering to the core components 2 is evaporated, and the sodium that has evaporated into gas is removed through the sodium trap 13. After that, the sodium is evacuated from the vacuum pump unit 11. Ru.
こうして収納容器１内を真空にして、炉心構成要素２に
付着しているナトリウムを蒸発させるが炉心構成要素２
に付着したナトリウムの量が多い場合には蒸発ＩＡ埋に
時間がかかる為、大容量の真空槽１２を一基又は複数基
設け、この中を予め真空にしておき、弁１８を開いて収
納容器１を真空にして炉心構成要素２に付着しているナ
トリウムを蒸発させる操作を繰返し、多量のナトリウム
除去を行わせる場合もある。さらにこの場合には炉心構
成要素自体崩壊熱を出している為、この真空蒸発操作の
合い間に炉心構成要素２の冷却が必要となり、循環ブロ
ワ５、ナトリウムトラップ１６．ガス冷却器１７を有す
る冷却系を設けている。In this way, the inside of the storage container 1 is evacuated and the sodium adhering to the core components 2 is evaporated.
If there is a large amount of sodium attached to the container, it will take time to evaporate the IA, so one or more large-capacity vacuum chambers 12 are provided, the interior of which is evacuated in advance, and the valve 18 is opened to remove the storage container. In some cases, a large amount of sodium may be removed by repeating the operation of evacuating reactor core component 1 to evaporate sodium adhering to core component 2. Furthermore, in this case, since the core components themselves generate decay heat, it is necessary to cool the core components 2 between vacuum evaporation operations, and the circulation blower 5, sodium trap 16. A cooling system having a gas cooler 17 is provided.
（発明が解決しようとする問題点）
ところが、前記湿潤不活性ガス洗浄法では、放射性物質
を含有する洗浄廃液が大量に発生し、この廃液処理の為
の設備費、運転費負担が大きい。(Problems to be Solved by the Invention) However, in the wet inert gas cleaning method, a large amount of cleaning waste liquid containing radioactive substances is generated, and the equipment and operating costs for processing this waste liquid are large.
また前記の真空蒸発法では、炉心構成要素２の付着ナト
リウム量が多い場合、蒸発処理に時間がかかり、設備規
模も大きくなる。Furthermore, in the vacuum evaporation method described above, when the amount of sodium adhering to the core component 2 is large, the evaporation process takes time and the scale of the equipment becomes large.
そこで本発明は放射性廃棄物量を飛躍的に減少でき、し
かも能率良くナトリウムを分離除去できる高速炉炉心構
成要素のナトリウム除去法を提供しようとするものであ
る。Therefore, the present invention aims to provide a method for removing sodium from fast reactor core components, which can dramatically reduce the amount of radioactive waste and can efficiently separate and remove sodium.
（問題点を解決するための手段）
上記問題点を解決するための本発明の高速炉炉心構成要
素のナトリウム除去法は、収納容器内に炉心構成要素を
収納した後、高温不活性ガスにより炉心構成要素を加熱
し、構造材表面に付着している金属ナトリウムを蒸発さ
せ、そのナトリウム蒸気を同伴した不活性ガスを冷伝熱
面を有するナトリウム分離器に導入し、ナトリウムを凝
縮分離することを特徴とするものである。(Means for Solving the Problems) In order to solve the above-mentioned problems, the method for removing sodium from fast reactor core components of the present invention is to store the core components in a storage container and then remove the sodium from the core components using high-temperature inert gas. The component is heated to evaporate the metallic sodium adhering to the surface of the structural material, and the inert gas accompanied by the sodium vapor is introduced into a sodium separator with a cold heat transfer surface to condense and separate the sodium. This is a characteristic feature.
上記高温不活性ガスは、Ｎ２． Ａｒ、 Ｈｅ等をヒー
タにより加熱したものと、炉心構成要素の残留崩壊熱に
より加熱したものとがある。The high temperature inert gas is N2. There are two types: one in which Ar, He, etc. is heated by a heater, and the other in which heat is generated by residual decay heat of core components.
尚、不活性ガスの純度は、いずれも９９．９９９％以上
で、酸素、水の濃度は１ ｐｐｍ以下が望ましい。The purity of the inert gas is preferably 99.999% or more, and the concentration of oxygen and water is preferably 1 ppm or less.
（実施例）
本発明の高速炉炉心構成要素のナトリウム除去法の一実
施例を第１図によって説明する。使用済の炉心燃料集合
体である炉心構成要素２２を図示せぬ炉外中ｉ ４９か
ら取り出して収納容器２１内に収納する。次に収納容器
２１に付設した循環回路２３の循環ガスブロワ２４を駆
動して、その上流で循環回路２３の途中に接続された不
活性ガス送給通路２３ａより送給された不活性ガスをヒ
ータ２５にて３００〜５００℃まで加熱した上で収納容
器２１に送り込み、炉心構成要素２２と接触させ、その
構造材表面に付着している金属ナトリウムを蒸発させる
。その際構造材及び金属ナトリウムは約６００℃に加熱
されている。ナトリウム蒸気は不活性ガスと共に収納容
器２１より循環回路２３に出て、先ずエコノマイザ−２
６で冷却された後、ナトリウム分離器２７に人りて冷伝
熱面２８により冷却されてナトリウム蒸気が凝縮分離さ
れて、ナトリウム回収容器２９に金属ナトリウムとして
回収される。分離された不活性ガスは、前記エコノマイ
ザ−２６の吸熱側に入り、ナトリウム蒸気同伴の不活性
ガスの冷却に携わって温度上昇した後、ヒータ２５に送
られ、ここで３００〜５００℃まで加熱された上再び収
納容器２１に送り込まれて、炉心構成要素２２と接触し
、その構造材表面に付着している金属ナトリウムを蒸発
させる。以後上記の如く高温不活性ガスの循環により収
納容器２１内の炉心構成要素２２の構造材表面に付着し
ている金属ナトリウムは容易に蒸発し、ナトリウム回収
容器２９に金属ナトリウムとして回収される。(Example) An example of the method for removing sodium from fast reactor core components of the present invention will be described with reference to FIG. The core components 22, which are used core fuel assemblies, are taken out from the outside of the reactor (not shown) 49 and stored in the storage container 21. Next, the circulating gas blower 24 of the circulating circuit 23 attached to the storage container 21 is driven, and the inert gas supplied from the inert gas supply passage 23a connected midway in the circulating circuit 23 upstream thereof is supplied to the heater 25. After being heated to 300 to 500° C., it is sent into the storage container 21 and brought into contact with the core components 22 to evaporate metallic sodium adhering to the surface of the structural material. In this case, the structural material and metallic sodium are heated to approximately 600°C. Sodium vapor exits from the storage container 21 to the circulation circuit 23 together with the inert gas, and first passes through the economizer 2.
After being cooled at step 6, the sodium vapor is transferred to a sodium separator 27, cooled by a cold heat transfer surface 28, condensed and separated, and recovered as metallic sodium in a sodium recovery container 29. The separated inert gas enters the endothermic side of the economizer 26, and after being involved in cooling the inert gas accompanied by sodium vapor and increasing its temperature, it is sent to the heater 25, where it is heated to 300 to 500°C. After that, it is fed into the storage container 21 again and comes into contact with the core components 22 to evaporate the metallic sodium adhering to the surface of the structural material. Thereafter, the metallic sodium adhering to the surface of the structural material of the core component 22 in the storage container 21 is easily evaporated by the circulation of the high temperature inert gas as described above, and is recovered as metallic sodium in the sodium recovery container 29.
金属ナトリウムが蒸発し終えた炉心構成要素２２は、収
納容器２１より取り出す前に所定温度まで冷却される。The core component 22, in which the metallic sodium has been completely evaporated, is cooled to a predetermined temperature before being taken out from the storage container 21.
冷却はヒータ２５による不活性ガスの加熱を止め、不活
性ガスの循環回路２３中のバルブを切換えて、ガス冷却
器３１を通る循環回路２３ｃとヒータ２５をバイパスす
る循環回路２３ｂを不活性ガスが通るようにする。この
ように構成された循環回路によりエコノマイザ−２６を
出た不活性ガスはガス冷却器３１を通り冷却され、ヒー
タ２５をバイパスして収納容器２１に入る。ここで不活
性ガスは炉心構成要素２２と接触し冷却する。温度が上
昇した不活性ガスは収納容器２１を出て循環回路２３に
入り、エコノマイザ−２６の放熱側を通りナトリウム分
離器２フの冷伝熱面２８とガスプレクーラー３０により
冷却されブロワ２４に入る。ブロワ２４を出た不活性ガ
スはエコノマイザ−２６の吸熱側に入る。エコノマイザ
−２６を出た不活性ガスはガス冷却器３１を通り冷却さ
れ、ヒータ２５をバイパスして収納容器２１に入る。こ
こで不活性ガスは炉心構成要素２２と接触して冷却する
。以後、上記の如く冷却された不活性ガスの循環により
炉心構成要素２２が冷却される。For cooling, the heating of the inert gas by the heater 25 is stopped, the valve in the inert gas circulation circuit 23 is switched, and the inert gas is passed through the circulation circuit 23c passing through the gas cooler 31 and the circulation circuit 23b bypassing the heater 25. Let it pass. The inert gas leaving the economizer 26 passes through the gas cooler 31 and is cooled by the circulation circuit configured in this manner, bypasses the heater 25, and enters the storage container 21. Here, the inert gas contacts and cools core components 22. The inert gas whose temperature has risen leaves the storage container 21 and enters the circulation circuit 23, passes through the heat radiation side of the economizer 26, is cooled by the cold heat transfer surface 28 of the sodium separator 2F and the gas pre-cooler 30, and is sent to the blower 24. enter. The inert gas leaving the blower 24 enters the endothermic side of the economizer 26. The inert gas leaving the economizer 26 is cooled through a gas cooler 31, bypasses the heater 25, and enters the storage container 21. Here, the inert gas contacts and cools core components 22. Thereafter, the core components 22 are cooled by circulating the cooled inert gas as described above.
尚、上記実施例に於いて、第２図に示す如く循環回路２
３の途中のガスプレクーラー３０の上流にガスチラー３
２．ナトリウムトラップ３３、真空ポンプユニット３４
を有する真空排気路３５を付加して、高温不活性ガスの
循環を一定時間行った後、真空ポンプユニット３４を駆
動して収納容器１内のナトリウム蒸気を同伴した不活性
ガスを吸引し、エコノマイザ−２６で冷却し、ナトリウ
ム分離器２７でナトリウム蒸気を凝縮分離し、ナトリウ
ム回収容器２９に金属ナトリウムとして回収する。分離
された低温の不活性ガスは真空排気路３５に入り、ガス
チラー３２でン令却され、ナトリウムトラップ３３で残
余のナトリウム蒸気が取り除かれ、真空ポンプユニット
３４を経由して排気される。In the above embodiment, as shown in FIG.
Gas chiller 3 is installed upstream of gas pre-cooler 30 in the middle of 3.
2. Sodium trap 33, vacuum pump unit 34
After circulating the high-temperature inert gas for a certain period of time, the vacuum pump unit 34 is driven to suck the inert gas accompanied by the sodium vapor in the storage container 1, and the economizer -26, the sodium vapor is condensed and separated in the sodium separator 27, and recovered as metallic sodium in the sodium recovery container 29. The separated low-temperature inert gas enters the vacuum exhaust path 35, is decomposed by the gas chiller 32, residual sodium vapor is removed by the sodium trap 33, and is exhausted via the vacuum pump unit 34.
尚、収納容器２１の真空度が高くなった時点でバルブを
切換え、真空排気路３５′を用いて収納容器２１だけを
真空排気し、より真空度を高めて金属ナトリウムの蒸発
をさらに良好にする。このように真空吸引することによ
り、収納容器２１内の炉心構成要素２２の構造材表面に
付着している金属ナトリウムは高温かつ真空下での蒸発
であるのでより多く蒸発し、回収される。従ってナトリ
ウムの除去率が向上する。In addition, when the degree of vacuum in the storage container 21 becomes high, the valve is switched and only the storage container 21 is evacuated using the vacuum exhaust path 35' to further increase the degree of vacuum and improve the evaporation of metallic sodium. . By vacuum suction in this manner, more of the metallic sodium adhering to the surface of the structural material of the core component 22 in the storage container 21 is evaporated and recovered since it is evaporated at high temperature and under vacuum. Therefore, the sodium removal rate is improved.
次に本発明の高速炉炉心構成要素のナトリウム除去法の
他の実施例を第３図によフて説明する。収納容器２１内
に、使用済みの炉心燃料集合体である炉心構成要素２２
を図示せぬ炉外中ｍ槽から取り出して収納する。次に収
納容器２１内に不活性ガスを充填する。次いでこの不活
性ガスを炉心構成要素２２の残留崩壊熱により温度上昇
させると共に、収納容器１に付設した不活性ガス予熱回
路３６の循環ガスブロワ３８を駆動して予熱回路３６を
循環させ、残留崩壊熱が小さい炉心構成要素２２に付着
したナトリウムを除去する場合にはヒータ３７にて加熱
して収納容器１に戻す。Next, another embodiment of the method for removing sodium from fast reactor core components according to the present invention will be described with reference to FIG. Inside the storage container 21, there are core components 22, which are used core fuel assemblies.
is taken out from a tank outside the furnace (not shown) and stored. Next, the storage container 21 is filled with inert gas. Next, the temperature of this inert gas is raised by the residual decay heat of the core components 22, and the circulating gas blower 38 of the inert gas preheating circuit 36 attached to the storage vessel 1 is driven to circulate the inert gas through the preheating circuit 36, thereby removing the residual decay heat. When removing sodium adhering to the core components 22 having a small amount of sodium, the sodium is heated by the heater 37 and returned to the storage container 1.
こうして不活性ガスを所要の温度まで加熱すると、炉心
構成要素２２の構造材表面に付着している金属ナトリウ
ムが蒸発するので、循環ガスブロワ３８の駆動を停止す
る。When the inert gas is heated to the required temperature in this manner, the metallic sodium adhering to the surface of the structural material of the core component 22 evaporates, so the driving of the circulating gas blower 38 is stopped.
次に真空排気路３９の真空ポンプユニット４１を駆動し
て、収納容器１内にナトリウム蒸気を同伴した不活性ガ
スを吸引し、ナトリウム分離器２７でナトリウム蒸気を
凝縮分離した後の低温の不活性ガスを真空排気路３９に
導き、ナトリウムトラック４０で残余のナトリウム蒸気
を取り除き、真空ポンプユニット４１を経由して排気す
る。このように真空吸引することにより、収納容器２１
内の炉心構成要素２２の構造材表面に付着している金属
ナトリウムは高温かつ真空下での蒸発であるので、良好
に蒸発し、回収される。従って、ナトリウムの除去率が
向上する。Next, the vacuum pump unit 41 of the vacuum exhaust path 39 is driven to suck inert gas accompanied by sodium vapor into the storage container 1, and after the sodium vapor is condensed and separated in the sodium separator 27, the low-temperature inert gas is The gas is led to a vacuum exhaust path 39, residual sodium vapor is removed by a sodium truck 40, and exhausted via a vacuum pump unit 41. By vacuum suction in this way, the storage container 21
Since the metallic sodium adhering to the structural material surface of the core components 22 inside is evaporated at high temperature and under vacuum, it is well evaporated and recovered. Therefore, the sodium removal rate is improved.
（発明の効果）
以上′の説明で判るように本発明の高速炉炉心構成要素
のナトリウム除去法は、ナトリウム除去に用いる不活性
ガスを循環使用するので、放射性廃棄物を飛躍的に減少
できる。また高温の不活性ガスを炉心構成要素に接触さ
せるので、その構造材表面に付着している金属ナトリウ
ムは容易に蒸発し、しかもナトリウム蒸気を同伴した不
活性ガスを冷伝熱面を有するナトリウム分離器に導入し
、ナトリウムを凝縮分離するので、能率良くナトリウム
を炉心構成要素より分離除去できるという効果がある。(Effects of the Invention) As can be seen from the above explanation, the method for removing sodium from fast reactor core components of the present invention can dramatically reduce radioactive waste because the inert gas used for sodium removal is recycled. In addition, since high-temperature inert gas is brought into contact with the core components, the metallic sodium adhering to the structural material surface easily evaporates, and the inert gas accompanied by sodium vapor is separated from the sodium using the cold heat transfer surface. Since sodium is introduced into the reactor and condensed and separated, it has the effect of efficiently separating and removing sodium from the core components.
さらに、真空吸引を組み合せることにより、真空下での
ナトリウム蒸発率が１気圧下における蒸発率より１００
〜１０００倍も大きいという事象を利用できるので、速
やかにナトリウムを除去できる。Furthermore, by combining vacuum suction, the sodium evaporation rate under vacuum is 100 times higher than that under 1 atm.
Since the phenomenon that is ~1000 times larger can be utilized, sodium can be quickly removed.
第１図乃至第３図は夫々本発明の高速炉炉心構成要素の
ナトリウム除去法を実施する手段を示す図、第４図及び
第５図は夫々従来の高速炉炉心構成要素のナトリウム除
去法を実施する手 段を示す図である。1 to 3 are diagrams showing means for implementing the sodium removal method for fast reactor core components of the present invention, respectively, and FIGS. 4 and 5 are diagrams showing the means for implementing the sodium removal method for fast reactor core components, respectively, according to the present invention. It is a diagram showing the means for implementation.
Claims (1)
性ガスにより炉心構成要素を加熱し、構造材表面に付着
している金属ナトリウムを蒸発させ、そのナトリウム蒸
気を同伴した不活性ガスを冷伝熱面を有するナトリウム
分離器に導入し、ナトリウムを凝縮分離することを特徴
とする高速炉炉心構成要素のナトリウム除去法。 ２）高温不活性ガスがヒータにより加熱されたものであ
ることを特徴とする特許請求の範囲１）項記載の高速炉
炉心構成要素のナトリウム除去法。 ３）高温不活性ガスが炉心構成要素の残留崩壊熱により
加熱されたものであることを特徴とする特許請求の範囲
１）項記載の高速炉炉心構成要素のナトリウム除去法。[Claims] 1) After storing the core components in a storage container, the core components are heated with high-temperature inert gas to evaporate metallic sodium adhering to the surface of the structural material, and the sodium vapor is released. A method for removing sodium from fast reactor core components, characterized by introducing entrained inert gas into a sodium separator having a cold heat transfer surface and condensing and separating sodium. 2) The method for removing sodium from a fast reactor core component according to claim 1), wherein the high-temperature inert gas is heated by a heater. 3) The method for removing sodium from a fast reactor core component according to claim 1), wherein the high-temperature inert gas is heated by residual decay heat of the core component.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP62085284A JP2564132B2 (en) | 1987-04-07 | 1987-04-07 | Sodium removal treatment facility for fast reactor core components |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP62085284A JP2564132B2 (en) | 1987-04-07 | 1987-04-07 | Sodium removal treatment facility for fast reactor core components |
Related Child Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP11206896A Division JPH09178895A (en) | 1996-04-09 | 1996-04-09 | Sodium removing equipment for fast reactor core constituting element |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS63250598A true JPS63250598A (en) | 1988-10-18 |
| JP2564132B2 JP2564132B2 (en) | 1996-12-18 |
Family
ID=13854272
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP62085284A Expired - Fee Related JP2564132B2 (en) | 1987-04-07 | 1987-04-07 | Sodium removal treatment facility for fast reactor core components |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JP2564132B2 (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH01189600A (en) * | 1988-01-23 | 1989-07-28 | Power Reactor & Nuclear Fuel Dev Corp | High temperature gas blow washing of spent fuel |
| US20110222642A1 (en) * | 2008-11-19 | 2011-09-15 | Guy-Marie Gautier | Sfr nuclear reactor of the integrated type with improved compactness and convection |
Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5546122A (en) * | 1978-09-29 | 1980-03-31 | Tokyo Shibaura Electric Co | Cleaning device for sodium equipment |
| JPS5786800A (en) * | 1980-11-20 | 1982-05-29 | Tokyo Shibaura Electric Co | Cleaning device for decontaminated sodium instruments |
-
1987
- 1987-04-07 JP JP62085284A patent/JP2564132B2/en not_active Expired - Fee Related
Patent Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5546122A (en) * | 1978-09-29 | 1980-03-31 | Tokyo Shibaura Electric Co | Cleaning device for sodium equipment |
| JPS5786800A (en) * | 1980-11-20 | 1982-05-29 | Tokyo Shibaura Electric Co | Cleaning device for decontaminated sodium instruments |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH01189600A (en) * | 1988-01-23 | 1989-07-28 | Power Reactor & Nuclear Fuel Dev Corp | High temperature gas blow washing of spent fuel |
| US20110222642A1 (en) * | 2008-11-19 | 2011-09-15 | Guy-Marie Gautier | Sfr nuclear reactor of the integrated type with improved compactness and convection |
Also Published As
| Publication number | Publication date |
|---|---|
| JP2564132B2 (en) | 1996-12-18 |
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