JPH01308999A - Storage pretreatment for spent fuel - Google Patents
Storage pretreatment for spent fuelInfo
- Publication number
- JPH01308999A JPH01308999A JP63140820A JP14082088A JPH01308999A JP H01308999 A JPH01308999 A JP H01308999A JP 63140820 A JP63140820 A JP 63140820A JP 14082088 A JP14082088 A JP 14082088A JP H01308999 A JPH01308999 A JP H01308999A
- Authority
- JP
- Japan
- Prior art keywords
- fuel
- storage
- spent fuel
- atmosphere
- sodium
- 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
- 239000002915 spent fuel radioactive waste Substances 0.000 title claims abstract description 36
- CDBYLPFSWZWCQE-UHFFFAOYSA-L Sodium Carbonate Chemical compound [Na+].[Na+].[O-]C([O-])=O CDBYLPFSWZWCQE-UHFFFAOYSA-L 0.000 claims abstract description 14
- 229910000029 sodium carbonate Inorganic materials 0.000 claims abstract description 7
- CURLTUGMZLYLDI-UHFFFAOYSA-N Carbon dioxide Chemical compound O=C=O CURLTUGMZLYLDI-UHFFFAOYSA-N 0.000 claims description 22
- 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 claims description 17
- 229910052708 sodium Inorganic materials 0.000 claims description 17
- 239000011734 sodium Substances 0.000 claims description 17
- 238000000034 method Methods 0.000 claims description 16
- 238000004140 cleaning Methods 0.000 claims description 15
- 239000001569 carbon dioxide Substances 0.000 claims description 11
- 229910002092 carbon dioxide Inorganic materials 0.000 claims description 11
- 239000000446 fuel Substances 0.000 abstract description 18
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 abstract description 15
- 239000011261 inert gas Substances 0.000 abstract description 7
- 238000006243 chemical reaction Methods 0.000 abstract description 6
- 238000001816 cooling Methods 0.000 abstract description 4
- 238000010438 heat treatment Methods 0.000 abstract description 3
- 235000017550 sodium carbonate Nutrition 0.000 abstract 2
- 239000007789 gas Substances 0.000 description 11
- 239000000126 substance Substances 0.000 description 5
- 230000000694 effects Effects 0.000 description 4
- 238000012546 transfer Methods 0.000 description 4
- 229910000831 Steel Inorganic materials 0.000 description 3
- 238000010586 diagram Methods 0.000 description 3
- 239000003758 nuclear fuel Substances 0.000 description 3
- 239000002901 radioactive waste Substances 0.000 description 3
- 239000010959 steel Substances 0.000 description 3
- XKRFYHLGVUSROY-UHFFFAOYSA-N Argon Chemical compound [Ar] XKRFYHLGVUSROY-UHFFFAOYSA-N 0.000 description 2
- 238000010276 construction Methods 0.000 description 2
- 239000002826 coolant Substances 0.000 description 2
- 238000005516 engineering process Methods 0.000 description 2
- 238000002203 pretreatment Methods 0.000 description 2
- 239000002699 waste material Substances 0.000 description 2
- 229910052778 Plutonium Inorganic materials 0.000 description 1
- 229910052786 argon Inorganic materials 0.000 description 1
- 238000007664 blowing Methods 0.000 description 1
- 238000009924 canning Methods 0.000 description 1
- 238000011161 development Methods 0.000 description 1
- 238000011156 evaluation Methods 0.000 description 1
- 238000004880 explosion Methods 0.000 description 1
- 239000007788 liquid Substances 0.000 description 1
- OYEHPCDNVJXUIW-UHFFFAOYSA-N plutonium atom Chemical compound [Pu] OYEHPCDNVJXUIW-UHFFFAOYSA-N 0.000 description 1
- 238000012545 processing Methods 0.000 description 1
- 230000001737 promoting effect Effects 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
- NASFKTWZWDYFER-UHFFFAOYSA-N sodium;hydrate Chemical compound O.[Na] NASFKTWZWDYFER-UHFFFAOYSA-N 0.000 description 1
- 230000008685 targeting Effects 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
- Fuel Cell (AREA)
Abstract
Description
【発明の詳細な説明】
［産業上の利用分野］
本発明は、ナトリウム冷却型高速増殖炉の使用済燃料を
水中裸貯蔵あるいはドライ貯蔵する場合に、洗浄済みの
使用済燃料に付着している残留ナトリウムを非活性な化
学形態に変換させる使用済燃料の貯蔵前処理方法に関す
るものである。[Detailed Description of the Invention] [Industrial Application Field] The present invention provides a method for reducing the amount of waste that adheres to cleaned spent fuel when the spent fuel of a sodium-cooled fast breeder reactor is stored naked underwater or in dry storage. The present invention relates to a method for pre-storage treatment of spent fuel that converts residual sodium into an inactive chemical form.
［従来の技術］
高速増殖炉のようにナトリウムを冷却材とする原子炉に
おける使用済燃料は、付着している冷却材ナトリウムを
洗浄除去した後、鋼鉄製の専用容器に封入され水プール
で貯蔵される。このような水封入缶詰方式を採用してい
る理由は、燃料がプルトニウム燃料で高燃焼度であり崩
壊熱が高いこと、放射性生成物インベントリ−が大きい
こと等の高速炉燃料のもつ特徴を考慮したことによる。[Conventional technology] Spent fuel in nuclear reactors that use sodium as a coolant, such as fast breeder reactors, is cleaned to remove adhering sodium coolant, then sealed in a special steel container and stored in a water pool. be done. The reason for adopting this water-filled canned method is to take into account the characteristics of fast reactor fuel, such as plutonium fuel, which has a high burnup, high decay heat, and a large inventory of radioactive products. It depends.
しかし近年、使用済燃料を対象に燃料貯蔵管理技術の見
地から一連の検討評価を行ってきた結果、専用容器内の
水質変化、貯蔵時間等の燃料健全性に及ぼす影響が極め
て小さく、貯蔵期間中の燃料健全性は十分保たれている
と言う判断が得られつつある。このような検討結果を踏
まえて、専用容器の省略、燃料取り扱い設備の簡略化、
建設コスト及び運転コストの低減等のため、使用済燃料
の水中裸貯蔵あるシ１はドライ貯蔵が提案されている。However, in recent years, as a result of a series of studies and evaluations targeting spent fuel from the perspective of fuel storage management technology, it has been found that changes in water quality within the dedicated container, storage time, etc., have an extremely small effect on fuel integrity, and that during the storage period. It is beginning to be determined that the fuel integrity of the fuel is sufficiently maintained. Based on these study results, we decided to omit special containers, simplify fuel handling equipment,
In order to reduce construction costs and operating costs, dry storage has been proposed instead of underwater naked storage of spent fuel.
［発明が解決しようとする課題］
水中裸貯蔵やドライ貯蔵を行うためには活性なナトリウ
ムの処理が不可欠である。従来この種の使用済燃料の洗
浄方法としては、脱塩水を使用しそれを循環させて洗浄
する所謂「脱塩水循環方式」が主流である。ところが燃
料の構造上の特性（例えば燃料要素の間隔を均一に保持
するランピング・ワイヤ等の圧損）が洗浄性に大きな影
響を及ぼし、そのため所定のレベルまで洗浄するにはそ
れ相当（約１〜２ｍ３）の脱塩水が必要となる。これら
はすべて放射性廃棄物（廃液）となるため、それらを処
理する設備が必要となる等の問題があった。[Problems to be Solved by the Invention] Processing of active sodium is essential for bare underwater storage and dry storage. Conventionally, the mainstream method for cleaning this type of spent fuel has been the so-called "desalinated water circulation method," which uses demineralized water and circulates it for cleaning. However, the structural characteristics of the fuel (for example, the pressure drop of ramping wires that maintain uniform spacing between fuel elements) have a significant effect on cleanability, and cleaning to a desired level requires a corresponding amount (approximately 1 to 2 m3). ) of demineralized water is required. Since all of these become radioactive waste (waste liquid), there were problems such as the need for equipment to process them.
脱塩水Ｗｉ環洗浄方式に代わるものとして昇圧した高温
の不活性ガスを使用済燃料にブローして付着ナトリウム
を吹き飛ばし除去する高温ガスブロー洗浄方法が提案さ
れた。この方法では吹き飛ばしたナトリウムをそのまま
一次系に戻すことができるため放射性廃棄物が発生せず
、コストや被曝を大幅に低減ができる優れた効果がある
が、十分な洗浄を行うためには洗浄時間の増加は避けら
れず、また完全に除去しきれない活性なナトリウムの処
理が問題となる。As an alternative to the demineralized water Wi-ring cleaning method, a high-temperature gas blow cleaning method has been proposed in which a pressurized high-temperature inert gas is blown onto the spent fuel to blow away adhering sodium. This method allows the blown sodium to be returned to the primary system as is, so no radioactive waste is generated, and it has the excellent effect of significantly reducing costs and radiation exposure.However, in order to perform sufficient cleaning, the cleaning time is An increase in sodium is unavoidable, and treatment of active sodium, which cannot be completely removed, becomes a problem.
本発明は上記のような従来技術の実情を考慮してなされ
たものであって、その目的は残留ナトリウムが水もしく
は空気雰囲気下でも反応しないか、反応したとしてもゆ
っくり反応するように化学形態を変えることにより水中
裸貯蔵又はドライ貯蔵を実現できるようにした使用済燃
料の貯蔵前処理方法を提供することにある。The present invention has been made in consideration of the above-mentioned state of the prior art, and its purpose is to change the chemical form so that residual sodium does not react even in water or air atmosphere, or reacts slowly even if it does. It is an object of the present invention to provide a method for pre-storage and pre-treatment of spent fuel, which makes it possible to realize bare underwater storage or dry storage by changing the method.
本発明は、これによって洗浄設備の大幅な合理化、鋼鉄
製の専用容器の省略、放射性廃棄物の低減、及びドライ
貯蔵時の付帯設備の削減等を図ろうとするものである。The present invention aims to significantly rationalize cleaning equipment, omit special steel containers, reduce radioactive waste, and reduce incidental equipment during dry storage.
［課題を解決するための手段］
上記の目的を達成できる本発明は、ナトリウム冷却壁高
増殖炉の使用済燃料を洗浄した後、水中裸貯蔵又はドラ
イ貯蔵を行う前に、使用済燃料に炭酸ガスを強制供給し
て、該使用済燃料に付着している残留ナトリウムを炭酸
ナトリウムという化学的に非活性な形態に変換するよう
にした使用済燃料の貯蔵前処理方法である。[Means for Solving the Problems] The present invention, which can achieve the above-mentioned objects, provides carbonation to the spent fuel after cleaning the spent fuel of a sodium-cooled wall blast breeder reactor and before performing underwater naked storage or dry storage. This is a spent fuel storage pretreatment method in which residual sodium adhering to the spent fuel is converted into a chemically inactive form of sodium carbonate by forcefully supplying gas.
このような前処理は、例えば不活性ガスセルと空気セル
との間で使用済燃料の受は渡しを行う炭酸ガス雰囲気の
セル内で行うのが望ましい。It is desirable that such pretreatment be carried out, for example, in a cell in a carbon dioxide atmosphere where spent fuel is transferred between an inert gas cell and an air cell.
［作用］
使用済燃料に炭酸ガスを強制供給すると、それに付着し
ている残留ナトリウムを炭酸ナトリウムという非活性な
化学形態に変換することができる。このため水もしくは
空気雰囲気下でも反応しないか、又は反応したとしても
ゆっくりした反応となり、洗浄済みの使用済燃料にナト
リウムが残っていたとしても本発明を適用することによ
って水中裸貯蔵あるいはドライ貯蔵が可能となる。[Operation] When carbon dioxide gas is forcibly supplied to the spent fuel, residual sodium adhering to it can be converted into an inactive chemical form called sodium carbonate. For this reason, it does not react even in water or air atmosphere, or even if it does, it is a slow reaction.By applying the present invention, even if sodium remains in the spent fuel that has been cleaned, underwater storage or dry storage is possible. It becomes possible.
（実施例］
第１図は本発明に係る使用済燃料の貯蔵前処理方法を実
施する際の装置構成例を示す概略説明図である。(Example) FIG. 1 is a schematic explanatory diagram showing an example of an apparatus configuration when carrying out the method for pre-storage treatment of spent fuel according to the present invention.
ナトリウム冷却型高速増殖炉１０内の使用済燃料は、燃
料出入機１２によって取り出され炉外中継槽１４を経て
アルゴン（Ａｒ）ガス等の不活性ガスセル１６内に入る
。そして不活性ガスセル内移送４１９１８により燃料洗
浄槽２ｏに送られ、高温ガスブロ一方式で洗浄が行われ
る。The spent fuel in the sodium-cooled fast breeder reactor 10 is taken out by a fuel inlet/output machine 12, passes through an external relay tank 14, and enters an inert gas cell 16 such as argon (Ar) gas. Then, it is sent to the fuel cleaning tank 2o by an inert gas cell transfer 41918, and cleaning is performed using a high-temperature gas blowing method.
洗浄済みの使用済燃料は、炭酸ガス雰囲気のセル２２へ
送られ、地下台車２４で運ばれ、次の空気セル２６に至
る。その使用済燃料は空気セル内移送機２８により空気
セル２６内を移送され、次いで水プール３０内の水中台
車３２により運ばれ、プール内移送機３４により貯蔵ラ
フ、り３６に送り込まれる。The cleaned spent fuel is sent to a cell 22 with a carbon dioxide gas atmosphere, transported by an underground truck 24, and delivered to the next air cell 26. The spent fuel is transferred within the air cell 26 by an intra-air cell transfer device 28, then transported by a submersible truck 32 in a water pool 30, and sent to a storage rough 36 by an intra-pool transfer device 34.
なお符号３８は破損燃料缶詰設備、符号４゜は新燃料貯
蔵ラック、符号４２はキャスク台車を示す。The reference numeral 38 indicates the damaged fuel canning equipment, the reference numeral 4° indicates the new fuel storage rack, and the reference numeral 42 indicates the cask truck.
さて本発明では、不活性ガスセル１６と空気セル２６間
の受は渡しを行う炭酸ガス雰囲気のセル２２内の地下台
車２４に貯蔵前処理機能を持たせている。その構造の詳
細を第２図に示す。In the present invention, the underground cart 24 in the carbon dioxide gas atmosphere cell 22, which transfers between the inert gas cell 16 and the air cell 26, has a storage pretreatment function. The details of its structure are shown in FIG.
地下台車２４上には使用済燃料５ｏを収納する収納容器
５２が設けられ、その収納容器５２内へ雰囲気の炭酸ガ
スを循環させるブロワ−５４及びフィルタ５６を搭載し
ている。地下台車２４によって使用済燃料５０を移送す
る間に、雰囲気の炭酸ガスをブロワ−５４によって収納
容器５２内へ強制供給することで、使用済燃料５０に付
着している活性な残留ナトリウムを非活性な炭酸ナトリ
ウムへ変化させる。A storage container 52 for storing the spent fuel 5o is provided on the underground truck 24, and a blower 54 and a filter 56 for circulating atmospheric carbon dioxide into the storage container 52 are mounted. While the spent fuel 50 is being transferred by the underground truck 24, the carbon dioxide gas in the atmosphere is forcibly supplied into the storage container 52 by the blower 54 to deactivate the active residual sodium adhering to the spent fuel 50. It is converted into sodium carbonate.
なお必要に応じて、この地下台車２４に化学反応を促進
するための加熱装置や使用済燃料の除熱を行うための冷
却装置等を付設することも可能である。その場合には、
例えば収納容器５２とブロワ−５４との間に加熱装置や
冷却装置を設置すればよい。Note that, if necessary, it is also possible to attach a heating device for promoting chemical reactions, a cooling device for removing heat from the spent fuel, etc. to this underground trolley 24. In that case,
For example, a heating device or a cooling device may be installed between the storage container 52 and the blower 54.
付着している活性な残留ナトリウムは炭酸ガスとの接触
によって炭酸ナトリウムと言う非活性な化学形態に変換
させられるため、その後の水あるいは空気雰囲気下では
反応せず、また例え反応したとしてもゆっくりした反応
であるため、第１図に示すように水プール５０内で水中
裸貯蔵を行うことができる。The attached active residual sodium is converted into an inactive chemical form called sodium carbonate by contact with carbon dioxide gas, so it does not react in the subsequent water or air atmosphere, and even if it does, it reacts slowly. Since it is a reaction, it can be stored naked underwater in a water pool 50 as shown in FIG.
［発明の効果コ
本発明は上記のようにナトリウム冷却型高速増殖炉の使
用済燃料を洗浄した後、その使用済燃料に炭酸ガスを強
制供給して残留ナトリウムを炭酸ガスに変換する貯蔵前
処理方法であるから、使用済燃料に付着している活性な
残留ナトリウムの化学形態を非活性化することができ、
そのためナトリウム・水もしくはナトリウム・空気反応
が生じず、火災や爆発等の発生を回避でき、使用済燃料
を直接水もしくは空気雰囲気下で貯蔵するいわゆる水中
裸貯蔵あるいはドライ貯蔵を実現できる効果がある。[Effects of the Invention] As described above, the present invention provides storage pretreatment in which, after cleaning the spent fuel of a sodium-cooled fast breeder reactor, carbon dioxide gas is forcibly supplied to the spent fuel to convert residual sodium into carbon dioxide gas. method, it is possible to deactivate the active residual chemical form of sodium attached to spent fuel,
Therefore, no sodium-water or sodium-air reaction occurs, and the occurrence of fires, explosions, etc. can be avoided, and spent fuel can be stored directly in water or air atmosphere, so-called underwater naked storage or dry storage.
その結果、従来必要であった鋼鉄製の専用容器を省略で
き、燃料取り扱い設備の筒略化、高速増殖炉の建設及び
運転コストの削減を図ることができるし、また使用済燃
料の洗浄設備の大幅な合理化も可能となる。As a result, it is possible to omit the dedicated steel containers that were previously required, simplify fuel handling equipment, reduce fast breeder reactor construction and operating costs, and reduce spent fuel cleaning equipment. Significant rationalization is also possible.
第１図は本発明方法を実施するのに好適な設備構成例を
示す概略説明図、第２図はその符号■で示した要部の説
明図である。
１０・・・ナトリウム冷却型高速増殖炉、１６・・・不
活性ガスセル、２０・・・燃料洗浄槽、２２・・・炭酸
ガス雰囲気のセル、２４・・・地下台車、２６・・・空
気セル、３０・・・水プール、５０・・・使用済燃料、
５２・・・収納容器、５４・・・ブロワ−１５６・・・
フィルタ。
特許出願人 動力炉・核燃料開発事業団代 理 人
茂 見 穣第１図
第２図FIG. 1 is a schematic explanatory diagram showing an example of a suitable equipment configuration for carrying out the method of the present invention, and FIG. 2 is an explanatory diagram of the main parts indicated by the symbol . DESCRIPTION OF SYMBOLS 10... Sodium-cooled fast breeder reactor, 16... Inert gas cell, 20... Fuel cleaning tank, 22... Carbon dioxide atmosphere cell, 24... Underground truck, 26... Air cell , 30...Water pool, 50...Spent fuel,
52...Storage container, 54...Blower-156...
filter. Patent applicant: Power Reactor and Nuclear Fuel Development Corporation Representative: Shigeru Miyoshi Hitoshi Figure 1 Figure 2
Claims (1)
た後、水中裸貯蔵又はドライ貯蔵を行う前に、炭酸ガス
を強制供給して使用済燃料に付着している残留ナトリウ
ムを炭酸ナトリウムに変換することを特徴とする使用済
燃料の貯蔵前処理方法。1. After cleaning the spent fuel of a sodium-cooled fast breeder reactor and before storing it underwater or dry, carbon dioxide gas is forcibly supplied to convert the residual sodium attached to the spent fuel into sodium carbonate. A method for pre-storage and treatment of spent fuel, characterized by:
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP63140820A JPH01308999A (en) | 1988-06-08 | 1988-06-08 | Storage pretreatment for spent fuel |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP63140820A JPH01308999A (en) | 1988-06-08 | 1988-06-08 | Storage pretreatment for spent fuel |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH01308999A true JPH01308999A (en) | 1989-12-13 |
Family
ID=15277483
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP63140820A Pending JPH01308999A (en) | 1988-06-08 | 1988-06-08 | Storage pretreatment for spent fuel |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH01308999A (en) |
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2011525979A (en) * | 2008-06-25 | 2011-09-29 | コミッサリア タ レネルジー アトミク エ オ エネルジー オルタネイティヴ | Method for treating a structure containing sodium and radioactive material |
| JP2016523354A (en) * | 2013-07-08 | 2016-08-08 | コミサーリャ ア レナジー アトミック エー オー エナジー アルタナティブＣｏｍｍｉｓｓａｒｉａｔ Ａ Ｌ’Ｅｎｅｒｇｉｅ Ａｔｏｍｉｑｕｅ Ｅｔ Ａｕｘ Ｅｎｅｒｇｉｅｓ Ａｌｔｅｒｎａｔｉｖｅｓ | Method for treating absorbent pins containing contaminated boron carbide and sodium |
| CN107578836A (en) * | 2017-08-30 | 2018-01-12 | 中核四0四有限公司 | MOX pellets storage system and method |
Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH01232299A (en) * | 1988-03-11 | 1989-09-18 | Kawasaki Heavy Ind Ltd | Method and device for treating sticking sodium of fast bleeder reactor constituent element |
-
1988
- 1988-06-08 JP JP63140820A patent/JPH01308999A/en active Pending
Patent Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH01232299A (en) * | 1988-03-11 | 1989-09-18 | Kawasaki Heavy Ind Ltd | Method and device for treating sticking sodium of fast bleeder reactor constituent element |
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2011525979A (en) * | 2008-06-25 | 2011-09-29 | コミッサリア タ レネルジー アトミク エ オ エネルジー オルタネイティヴ | Method for treating a structure containing sodium and radioactive material |
| JP2016523354A (en) * | 2013-07-08 | 2016-08-08 | コミサーリャ ア レナジー アトミック エー オー エナジー アルタナティブＣｏｍｍｉｓｓａｒｉａｔ Ａ Ｌ’Ｅｎｅｒｇｉｅ Ａｔｏｍｉｑｕｅ Ｅｔ Ａｕｘ Ｅｎｅｒｇｉｅｓ Ａｌｔｅｒｎａｔｉｖｅｓ | Method for treating absorbent pins containing contaminated boron carbide and sodium |
| CN107578836A (en) * | 2017-08-30 | 2018-01-12 | 中核四0四有限公司 | MOX pellets storage system and method |
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