JPH0644076B2 - Method and apparatus for thermal oxidation treatment of spent nuclear fuel cladding tube - Google Patents
Method and apparatus for thermal oxidation treatment of spent nuclear fuel cladding tubeInfo
- Publication number
- JPH0644076B2 JPH0644076B2 JP167786A JP167786A JPH0644076B2 JP H0644076 B2 JPH0644076 B2 JP H0644076B2 JP 167786 A JP167786 A JP 167786A JP 167786 A JP167786 A JP 167786A JP H0644076 B2 JPH0644076 B2 JP H0644076B2
- Authority
- JP
- Japan
- Prior art keywords
- nuclear fuel
- fuel cladding
- furnace
- spent nuclear
- cladding tube
- 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 - Fee Related
Links
- 238000000034 method Methods 0.000 title claims description 34
- 238000007254 oxidation reaction Methods 0.000 title claims description 27
- 238000005253 cladding Methods 0.000 title claims description 21
- 230000003647 oxidation Effects 0.000 title claims description 20
- 239000002915 spent fuel radioactive waste Substances 0.000 title claims description 15
- 239000007789 gas Substances 0.000 claims description 35
- 230000001590 oxidative effect Effects 0.000 claims description 30
- 239000011261 inert gas Substances 0.000 claims description 17
- 239000003758 nuclear fuel Substances 0.000 claims description 15
- 229910001093 Zr alloy Inorganic materials 0.000 claims description 13
- 238000010438 heat treatment Methods 0.000 claims description 10
- 229910052751 metal Inorganic materials 0.000 claims description 7
- 239000002184 metal Substances 0.000 claims description 7
- 230000008021 deposition Effects 0.000 claims description 4
- IJGRMHOSHXDMSA-UHFFFAOYSA-N Atomic nitrogen Chemical compound N#N IJGRMHOSHXDMSA-UHFFFAOYSA-N 0.000 claims description 3
- 229910001873 dinitrogen Inorganic materials 0.000 claims description 2
- 239000000463 material Substances 0.000 claims description 2
- 239000010410 layer Substances 0.000 description 19
- 239000002775 capsule Substances 0.000 description 5
- 238000012958 reprocessing Methods 0.000 description 5
- YZCKVEUIGOORGS-NJFSPNSNSA-N Tritium Chemical compound [3H] YZCKVEUIGOORGS-NJFSPNSNSA-N 0.000 description 4
- 238000003860 storage Methods 0.000 description 4
- 229910052722 tritium Inorganic materials 0.000 description 4
- 230000009471 action Effects 0.000 description 3
- QVGXLLKOCUKJST-UHFFFAOYSA-N atomic oxygen Chemical compound [O] QVGXLLKOCUKJST-UHFFFAOYSA-N 0.000 description 3
- 230000000052 comparative effect Effects 0.000 description 3
- 238000011038 discontinuous diafiltration by volume reduction Methods 0.000 description 3
- 230000000694 effects Effects 0.000 description 3
- 238000005516 engineering process Methods 0.000 description 3
- 239000001301 oxygen Substances 0.000 description 3
- 229910052760 oxygen Inorganic materials 0.000 description 3
- RVTZCBVAJQQJTK-UHFFFAOYSA-N oxygen(2-);zirconium(4+) Chemical compound [O-2].[O-2].[Zr+4] RVTZCBVAJQQJTK-UHFFFAOYSA-N 0.000 description 3
- 230000008569 process Effects 0.000 description 3
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 3
- 229910001928 zirconium oxide Inorganic materials 0.000 description 3
- XKRFYHLGVUSROY-UHFFFAOYSA-N Argon Chemical compound [Ar] XKRFYHLGVUSROY-UHFFFAOYSA-N 0.000 description 2
- 239000002253 acid Substances 0.000 description 2
- 239000003054 catalyst Substances 0.000 description 2
- 239000000919 ceramic Substances 0.000 description 2
- 238000004090 dissolution Methods 0.000 description 2
- 239000000446 fuel Substances 0.000 description 2
- 230000007246 mechanism Effects 0.000 description 2
- VNWKTOKETHGBQD-UHFFFAOYSA-N methane Chemical compound C VNWKTOKETHGBQD-UHFFFAOYSA-N 0.000 description 2
- -1 pyroferrite Substances 0.000 description 2
- 230000002285 radioactive effect Effects 0.000 description 2
- 238000005245 sintering Methods 0.000 description 2
- 239000002900 solid radioactive waste Substances 0.000 description 2
- 239000002910 solid waste Substances 0.000 description 2
- 230000002269 spontaneous effect Effects 0.000 description 2
- 239000000126 substance Substances 0.000 description 2
- 206010000117 Abnormal behaviour Diseases 0.000 description 1
- GRYLNZFGIOXLOG-UHFFFAOYSA-N Nitric acid Chemical compound O[N+]([O-])=O GRYLNZFGIOXLOG-UHFFFAOYSA-N 0.000 description 1
- XLYOFNOQVPJJNP-PWCQTSIFSA-N Tritiated water Chemical compound [3H]O[3H] XLYOFNOQVPJJNP-PWCQTSIFSA-N 0.000 description 1
- QCWXUUIWCKQGHC-UHFFFAOYSA-N Zirconium Chemical compound [Zr] QCWXUUIWCKQGHC-UHFFFAOYSA-N 0.000 description 1
- 230000004913 activation Effects 0.000 description 1
- 229910052786 argon Inorganic materials 0.000 description 1
- 229910052792 caesium Inorganic materials 0.000 description 1
- TVFDJXOCXUVLDH-UHFFFAOYSA-N caesium atom Chemical compound [Cs] TVFDJXOCXUVLDH-UHFFFAOYSA-N 0.000 description 1
- 238000006243 chemical reaction Methods 0.000 description 1
- 239000003245 coal Substances 0.000 description 1
- 238000002485 combustion reaction Methods 0.000 description 1
- 238000007906 compression Methods 0.000 description 1
- 230000006835 compression Effects 0.000 description 1
- 238000001816 cooling Methods 0.000 description 1
- 230000008878 coupling Effects 0.000 description 1
- 238000010168 coupling process Methods 0.000 description 1
- 238000005859 coupling reaction Methods 0.000 description 1
- 230000007547 defect Effects 0.000 description 1
- 238000001514 detection method Methods 0.000 description 1
- 230000018109 developmental process Effects 0.000 description 1
- 238000009792 diffusion process Methods 0.000 description 1
- 239000000428 dust Substances 0.000 description 1
- 230000007613 environmental effect Effects 0.000 description 1
- 238000001914 filtration Methods 0.000 description 1
- 239000010419 fine particle Substances 0.000 description 1
- 230000004992 fission Effects 0.000 description 1
- 239000012530 fluid Substances 0.000 description 1
- 239000003517 fume Substances 0.000 description 1
- 239000004519 grease Substances 0.000 description 1
- 229910000856 hastalloy Inorganic materials 0.000 description 1
- 238000001513 hot isostatic pressing Methods 0.000 description 1
- 230000002706 hydrostatic effect Effects 0.000 description 1
- 239000000395 magnesium oxide Substances 0.000 description 1
- CPLXHLVBOLITMK-UHFFFAOYSA-N magnesium oxide Inorganic materials [Mg]=O CPLXHLVBOLITMK-UHFFFAOYSA-N 0.000 description 1
- AXZKOIWUVFPNLO-UHFFFAOYSA-N magnesium;oxygen(2-) Chemical compound [O-2].[Mg+2] AXZKOIWUVFPNLO-UHFFFAOYSA-N 0.000 description 1
- 238000002844 melting Methods 0.000 description 1
- 230000008018 melting Effects 0.000 description 1
- 239000000203 mixture Substances 0.000 description 1
- 239000006060 molten glass Substances 0.000 description 1
- 239000003345 natural gas Substances 0.000 description 1
- 229910017604 nitric acid Inorganic materials 0.000 description 1
- 239000003921 oil Substances 0.000 description 1
- 230000003287 optical effect Effects 0.000 description 1
- 239000007800 oxidant agent Substances 0.000 description 1
- UTDLAEPMVCFGRJ-UHFFFAOYSA-N plutonium dihydrate Chemical compound O.O.[Pu] UTDLAEPMVCFGRJ-UHFFFAOYSA-N 0.000 description 1
- FLDALJIYKQCYHH-UHFFFAOYSA-N plutonium(IV) oxide Inorganic materials [O-2].[O-2].[Pu+4] FLDALJIYKQCYHH-UHFFFAOYSA-N 0.000 description 1
- 239000000843 powder Substances 0.000 description 1
- 239000002901 radioactive waste Substances 0.000 description 1
- 230000008929 regeneration Effects 0.000 description 1
- 238000011069 regeneration method Methods 0.000 description 1
- 230000001105 regulatory effect Effects 0.000 description 1
- 238000007789 sealing Methods 0.000 description 1
- 238000007711 solidification Methods 0.000 description 1
- 230000008023 solidification Effects 0.000 description 1
- 230000006641 stabilisation Effects 0.000 description 1
- 238000011105 stabilization Methods 0.000 description 1
- 230000000087 stabilizing effect Effects 0.000 description 1
- 239000002344 surface layer Substances 0.000 description 1
- 239000000454 talc Substances 0.000 description 1
- 229910052623 talc Inorganic materials 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
-
- 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
- Y02W—CLIMATE CHANGE MITIGATION TECHNOLOGIES RELATED TO WASTEWATER TREATMENT OR WASTE MANAGEMENT
- Y02W30/00—Technologies for solid waste management
- Y02W30/50—Reuse, recycling or recovery technologies
Landscapes
- Furnace Details (AREA)
- Devices And Processes Conducted In The Presence Of Fluids And Solid Particles (AREA)
Description
【発明の詳細な説明】 〔産業上の利用分野〕 本発明は、使用済核燃料の再処理工程において、内部の
使用済核燃料を除去した後の核燃料被覆管の短尺物、詳
しくはジルカロイ金属でつくられた被覆管の短尺物(以
下、ハルと略記する)を空気などの酸化性雰囲気中で酸
化させ、酸化ジルコニウムを主体とする酸化物に転換
し、安定化する方法ならびにそれに用いられる装置に関
する。DETAILED DESCRIPTION OF THE INVENTION [Industrial field of application] The present invention relates to a short length of a nuclear fuel cladding tube after removing the spent nuclear fuel inside, in the spent nuclear fuel reprocessing step, more specifically, it is made of zircaloy metal. The present invention relates to a method of stabilizing a coated tube having a short length (hereinafter abbreviated as "hull") by oxidizing it in an oxidizing atmosphere such as air to convert it into an oxide mainly containing zirconium oxide, and an apparatus used therefor.
石炭、石油、天然ガスなどの在来燃料に代わるものとし
ての核燃料の平和利用は着実な伸びを続けているが、原
子力に対する危惧や世界的な環境運動の中で、放射性廃
棄物の処理は今や重大な関心事である。While peaceful use of nuclear fuels as an alternative to traditional fuels such as coal, oil and natural gas continues to grow steadily, amid the fear of nuclear power and the global environmental movement, the disposal of radioactive waste is now. This is a serious concern.
使用済核燃料の再処理過程では、燃料集合体中の核燃料
を被覆管から分離するために核燃料被覆管はおよそ30
〜50mmの長さの短尺物に切断され、硝酸などによる酸
溶解が行われる。During the reprocessing process of spent nuclear fuel, the nuclear fuel cladding tube is separated by about 30 to separate the nuclear fuel in the fuel assembly from the cladding tube.
It is cut into short pieces with a length of up to 50 mm, and acid dissolution with nitric acid or the like is performed.
その結果、酸溶解により内部の核燃料が除去された短尺
被覆管すなわちハルが固体廃棄物として発生する。固体
放射性廃棄物としてのハルは、 (1)ハル自体が高放射化されていること、 (2)ハル内面には二酸化プルトニウムなどの超ウラン元
素およびセシウム等の核分裂生成物が未溶解物として付
着していること、および (3)その材質、すなわちジルカロイは自然発火の危険性
があること、 などの特色からして、特殊なハンドリングと貯蔵技術と
が強く要求され、従来、その取扱いの困難さから、ドラ
ム缶中に収納し、ステンレスライニングした水槽中に沈
めて保管されていた。As a result, a short cladding tube or hull from which the internal nuclear fuel has been removed by acid dissolution is generated as solid waste. Hulls as solid radioactive waste are (1) the hull itself is highly activated, and (2) transuranium elements such as plutonium dioxide and fission products such as cesium adhere to the inner surface of the hull as undissolved substances. And (3) its material, that is, Zircaloy has a risk of spontaneous combustion, and special handling and storage technology are strongly required, and it has been difficult to handle in the past. Therefore, it was stored in a drum and submerged in a stainless steel-lined water tank for storage.
しかしながら、この方法はハル等が約1.1g/cm3とい
う低密度であるため必要な貯蔵空間が膨大なものとなる
こと、また万一の外乱の対して安定な結合体となってい
ない等の問題点を有しており、従来からその減容化と安
定化とに関し種々の研究努力が払われて来た。However, this method requires a huge storage space due to the low density of hulls of about 1.1 g / cm 3 , and it is not a stable combination in case of disturbance. However, various research efforts have been made in the past regarding volume reduction and stabilization.
このような減容化を有効に達成し得る技術として、近
年、熱間静水圧プレス(以下、HIPと略記する)が頓
に注目を集めている。HIPは元素、アルゴン等の不活
性ガスまたは耐熱グリース,溶融ガラス等の耐熱性非圧
縮性流体,BN粉末,パイロフェライト,タルク,酸化
ジルコニウム,酸化マグネシウム等の耐熱性粉粒体等を
圧力媒体として被処理体に高温下で三次元的静水圧を加
えて等方圧縮し、金属やセラミックス等の焼結,拡散接
合、または鋳造品の欠陥除去等を行う方法である。In recent years, hot isostatic pressing (hereinafter abbreviated as HIP) has attracted attention as a technique capable of effectively achieving such volume reduction. HIP is an element, inert gas such as argon or heat-resistant grease, heat-resistant incompressible fluid such as molten glass, BN powder, pyroferrite, talc, zirconium oxide, magnesium oxide, etc. This is a method in which a three-dimensional hydrostatic pressure is applied to an object to be processed at a high temperature to perform isotropic compression, and sintering of metal or ceramics, diffusion bonding, or defect removal of a cast product is performed.
本出願人も早くからこの技術に着目し、放射性固体廃棄
物の減容固化への応用について研究を行い、既にその成
果の幾つかを提案して来た。The applicant of the present invention also paid attention to this technology from an early stage, studied the application to the volume reduction and solidification of radioactive solid waste, and has already proposed some of the results.
例えば、ハル等を収納したカプセルをHIP処理に付す
る際に、特にハル等を構成するジルカロイの自然発火を
防止するため、カプセルを密封するに先立って脱気する
等の対策を講じた方法を発表した。またジルカロイハル
の融点温度の約60%程度の温度迄昇温するとトリチウム
がジルカロイハルより放出される。これについてはHI
P処理を施すに際し、金属カプセルを脱気密封し昇温処
理に付し、ハルから放出されるトリチウムガスをカプセ
ル外に配置した酸化剤の作用により必要に応じて酸化触
媒の扶けをかりてトリチウム水に転換し、しかる後にカ
プセルをその内容に水を閉じ込めた状態で脱気密封する
方法を特願昭58−182598号公報に提案した。For example, when subjecting a capsule containing a hull or the like to a HIP treatment, in particular, in order to prevent spontaneous ignition of zircaloy constituting the hull or the like, a method of taking measures such as deaeration prior to sealing the capsule is used. Announced. When the temperature is raised to about 60% of the melting point of Zircaloy-hal, tritium is released from Zircaloy-hal. HI about this
When the P treatment is performed, the metal capsule is degassed and sealed and subjected to a temperature rise treatment, and tritium gas released from the hull is removed by the action of the oxidant placed outside the capsule to remove the oxidation catalyst if necessary. A method was proposed in Japanese Patent Application No. 58-182598, in which tritium water was converted, and then the capsule was degassed and hermetically sealed with water contained therein.
上述の状況において、本発明者等は固体放射性廃棄物、
特にハル等の減容と貯蔵安定性の向上を達成するにはジ
ルカロイ金属はこれを加熱条件下で酸素と接触させるこ
とによって酸化物すなわち酸化ジルコニウムへ改質可能
なこと、またかかる酸化物を粉砕し、HIP処理によっ
てセラミック質の緻密な安定固化体へ安全確実に転換し
得ることを究明した。In the situation described above, we have found that solid radioactive waste,
In particular, in order to reduce the volume of hulls and improve storage stability, zircaloy metal can be reformed into an oxide, that is, zirconium oxide, by contacting it with oxygen under heating conditions, and crushing such oxide. However, it has been clarified that the HIP treatment can be safely and surely converted into a ceramic dense and stable solidified body.
ところで、核燃料の再処理工程で発生するハルの量はそ
の処理量にもよるが、一度にハルの個数量にして数千個
から数万個に達する。このように多量のハルを商業的規
模で加熱条件下に酸化媒体例えば空気と接触させるに
は、多くのハルを容器に一括収容し、電気炉などで加熱
するのであるが、その際殊に容器底部に存在するハルは
空気との接触不良のため充分に酸化されないという問題
点があり、更にジルカロイハルはジルコニウム金属が化
学組成重量比で95%以上を占めており、特に高温度に
おける酸素の存在下での酸化に際しては、既述の通り発
火の危険性をも伴う。By the way, the amount of hulls generated in the nuclear fuel reprocessing step can reach from several thousand to several tens of thousands at a time, depending on the amount of processed hulls. To bring such a large amount of hulls into contact with an oxidizing medium such as air under heating conditions on a commercial scale, a large number of hulls are put together in a container and heated in an electric furnace or the like. The bottom hull has a problem that it is not sufficiently oxidized due to poor contact with air. Furthermore, zircaloy hull has a zirconium metal content of 95% or more in terms of chemical composition weight ratio, and especially the presence of oxygen at high temperature. In the oxidation below, there is a risk of ignition as described above.
このような問題点に鑑み、先ず本発明の第1の目的は、
核燃料再処理工程から排出される大量のハルを商業的規
模において均一かつ確実容易に酸化する方法ならびに装
置を提供するにあり、本発明の第2の目的はそのような
方法を発火の危険を伴うことなく安全に遂行するための
方法ならびに装置を提供するにある。In view of these problems, the first object of the present invention is to
A second object of the present invention is to provide a method and a device for uniformly and easily oxidising a large amount of hulls discharged from a nuclear fuel reprocessing process on a commercial scale, and the second object of the present invention involves the risk of ignition of such a method. It is to provide a method and an apparatus for safely performing the operation.
また、本発明の究極の目的はハルを安定化し且つ減容固
定化して安全に隔離処分することである。Further, an ultimate object of the present invention is to stabilize and reduce the volume of the hull, and to secure and safely dispose of the hull.
上述の第1及び第2の目的を達成するための本発明方法
は、ジルカロイ金属を主体としてなるハルの堆積層を収
容した無蓋容器を加熱炉中に装填し、炉内を酸化性ガス
雰囲気となすとともに上記堆積層の下層部に酸化性ガス
を送入しつつ加熱処理を施し、併せて更にハルの過激な
酸化反応を抑制するために不活性ガスを炉内に供給し得
るようになしたことを特徴とするものである。更にまた
これらの方法に適用される装置の特徴は冒頭の特許請求
の範囲の項において述べた通りであり、以下の説明によ
って明瞭に理解されよう。According to the method of the present invention for achieving the above-mentioned first and second objects, a lidless container accommodating a deposited layer of hull mainly composed of zircaloy metal is loaded into a heating furnace, and the inside of the furnace is exposed to an oxidizing gas atmosphere. At the same time, heat treatment was performed while feeding oxidizing gas to the lower layer of the above-mentioned deposited layer, and at the same time, inert gas could be supplied into the furnace to suppress the radical oxidation reaction of the hull. It is characterized by that. Furthermore, the features of the apparatus which apply to these methods are as set out in the preambles of the claims and will be clearly understood by the following description.
そこで、本発明の構成を以下添付図面に基づいて説明す
る。Therefore, the configuration of the present invention will be described below with reference to the accompanying drawings.
先ず、多量のハルを酸化させる場合、第1図にその概要
を示したように無蓋容器(1)にハル(2)の堆積層を収容
し、それを電気炉(3)に装填して加熱ヒータ(4)によって
所定温度に加熱する。First, when oxidizing a large amount of hull, as shown in the outline of Fig. 1, the accumulated layer of the hull (2) is housed in the open container (1) and loaded into an electric furnace (3) and heated. It is heated to a predetermined temperature by the heater (4).
このとき、電気炉(3)には酸化性ガス(5)例えば、空気を
送給機(6)を用いて炉内に供給するか、あるいは排気フ
ァン(7)によって炉内を負圧状態にして吸引する方法に
より、炉内を酸化性ガス雰囲気となしてハル(2)を酸化
させる。At this time, the electric furnace (3) is supplied with an oxidizing gas (5), for example, air into the furnace by using a feeder (6), or a negative pressure state is created in the furnace by an exhaust fan (7). The hull (2) is oxidized by making the inside of the furnace an oxidizing gas atmosphere by a suction method.
ところが、このようにして酸化した場合には、第2図に
示すように、無蓋容器(1)に供給堆積されたハルの表層
部から上層部Aにある部分は酸化を受けているが、下層
部Bに存在する部分は未酸化状態のまま残され、長時間
の加熱を施しても安全酸化は困難である。However, when the oxidization is performed in this way, as shown in FIG. 2, the portion from the surface layer of the hull supplied and deposited in the open container (1) to the upper layer A is oxidized, but the lower layer is The part existing in the part B is left in an unoxidized state, and safe oxidation is difficult even if it is heated for a long time.
そこで、本発明方法は、上記のハル堆積層の下層部に直
接酸化性ガスを送入しつつ加熱処理を施し堆積層全体を
万遍なく迅速に酸化させることを必須の要点とするもの
であって、第3図に本発明方法に適用される無蓋容器の
基本的構造を示す。Therefore, the method of the present invention has an essential point of performing a heat treatment while directly feeding an oxidizing gas to the lower layer portion of the hull deposition layer to oxidize the entire deposition layer uniformly and uniformly. FIG. 3 shows the basic structure of the lidless container applied to the method of the present invention.
第3−A図はその側面概要図、第3−B図は平面図であ
り、第3−C図はそれらの変形された態様の一例を示す
平面図である。FIG. 3-A is a schematic side view thereof, FIG. 3-B is a plan view, and FIG. 3-C is a plan view showing an example of a modified mode thereof.
これらの図において、容器(1)の底部には空気等の酸化
性ガスを効率よく供給することができる多孔管(9)が配
設され、この多孔管には多数の吹出孔(10)が穿設されて
おり、またその一端(11)は容器(1)の外方へ突出してい
る。In these figures, a porous pipe (9) capable of efficiently supplying an oxidizing gas such as air is arranged at the bottom of the container (1), and a large number of blow holes (10) are provided in this porous pipe. It is perforated, and one end (11) thereof projects to the outside of the container (1).
多孔管(9)の配設の状況は、第3−C図に示すように複
数本を並設すれば酸化効率を高めることができるのでよ
り好ましい。It is more preferable that the perforated pipes (9) are arranged, as shown in FIG. 3-C, by arranging a plurality of pipes in parallel because the oxidation efficiency can be increased.
第4図は上記無蓋容器を電気炉に装入した本発明装置を
示す縦断面概要図である。FIG. 4 is a schematic vertical sectional view showing an apparatus of the present invention in which the above-mentioned lidless container is loaded in an electric furnace.
同図において電気炉(3)は気密に閉止し得る扉(12)を有
し、ハルの堆積層を搭載した無蓋容器(1)は扉(12)を開
閉して炉内に装入される。また、電気炉(3)は、それぞ
れ炉内に開口し且つ送給機(6)(6)に通ずる複数個の給気
管路(18)(18)・・・と、炉内の排気孔(19)から排気ファ
ン(7)及び高性能フィルター(8)を経て外気に開放される
排気管路(20)とを具える。In the figure, the electric furnace (3) has a door (12) that can be closed in an airtight manner, and an open container (1) equipped with a accumulated layer of hull is loaded into the furnace by opening and closing the door (12). . Further, the electric furnace (3) has a plurality of air supply conduits (18) (18) ... Each of which is opened in the furnace and communicates with the feeders (6) (6), and an exhaust hole in the furnace ( The exhaust pipe (20) is opened to the outside air from the exhaust fan (7) and the high performance filter (8) from the exhaust pipe (7).
高性能フィルターでは高温で昇華したヒューム等の微粒
子を除くものであり、ハルの含有するトリチウムガスは
高性能フィルターで濾過した後の排ガス酸化触媒を用い
てトリチウム水に変化させ回収する。A high-performance filter removes fine particles such as fumes that have sublimated at high temperatures, and the tritium gas contained in the hull is converted into tritiated water using an exhaust gas oxidation catalyst after filtering with a high-performance filter and collected.
このような電気炉(3)に装入された無蓋容器(1)は第4−
A図に示す如くその多孔管(9)の一端部(11)が炉体(13)
から炉内へ突出する給気管路(18)の端部で形成される酸
化性ガス供給孔(14)と嵌合し互いに連結する。この際、
供給孔(14)にはストッパ(15)が設けられており、それに
よって多孔管(9)の端部(11)と供給孔(14)とはカップリ
ングして密に嵌合する。The lidless container (1) loaded in such an electric furnace (3) is
As shown in Fig. A, one end (11) of the perforated tube (9) is a furnace body (13).
It is fitted and connected to the oxidizing gas supply hole (14) formed at the end of the air supply pipe (18) protruding from the inside to the furnace. On this occasion,
The supply hole (14) is provided with a stopper (15) so that the end (11) of the perforated pipe (9) and the supply hole (14) are coupled and tightly fitted.
このようにして第4−B図に示すようにハル堆積層の下
層部にも多孔管(9)を通して空気などの酸化性ガスの供
給が可能となる。In this way, as shown in FIG. 4-B, it becomes possible to supply an oxidizing gas such as air to the lower layer of the hull deposition layer through the perforated pipe (9).
第5図はハル自体が酸化性ガス中の酸素と急激に反応し
発火することを抑制し、また発火したときに直ちに消火
するための酸化反応制御手段を具えた装置を示す縦断面
概要図である。FIG. 5 is a schematic longitudinal sectional view showing an apparatus equipped with an oxidation reaction control means for suppressing the ignition of the hull itself by abruptly reacting with oxygen in the oxidizing gas and for immediately extinguishing the ignition. is there.
同図において、窒素ガスなどの不活性ガスのボンベ(17)
(17)・・・は、それぞれ開閉弁(21)(21)・・・を介して
不活性ガス供給管(22)(22)・・・により炉内に連通し得
るようにされている。In the figure, a cylinder of an inert gas such as nitrogen gas (17)
(17) ... Can be communicated with the inside of the furnace by inert gas supply pipes (22) (22) ..
不活性ガス供給管(22)(22)は直接炉体(13)に接続されて
もよく、また、給気管路(18)(18)へ接続されてもよい。The inert gas supply pipes (22) (22) may be directly connected to the furnace body (13) or may be connected to the air supply pipe lines (18) (18).
一方、炉内には炉内温度および発火現象を検知する検知
器(16)、例えば熱電対あるいは光学式温度計などが設け
られ、発火現象などに伴う異常な炉内温度の挙動信号に
よって前記開閉弁(21)(21)・・・を作動させ、ボンベ(1
7)よりの不活性ガスの供給量を制御して酸化速度を調節
し、または不活性ガスを急激に噴出させて消火させる。On the other hand, a detector (16) for detecting the temperature inside the furnace and the ignition phenomenon, such as a thermocouple or an optical thermometer, is provided in the furnace, and the opening and closing is performed by the abnormal behavior signal of the temperature inside the furnace accompanying the ignition phenomenon. Operate the valves (21) (21) ...
The supply rate of the inert gas from 7) is controlled to adjust the oxidation rate, or the inert gas is rapidly ejected to extinguish the fire.
このとき、酸化性ガスの送給機(6)(6)をも同時に制御し
たり、停止させることは好ましいことであり、また、吸
込方式で外部から酸化性ガスを取り入れている場合は同
様に吸込量を制御する。それらの動作を検知器(16)の検
知信号によって行わせるためには周知,慣用の手段を適
宜に応用することが可能である。At this time, it is preferable to control or stop the oxidizing gas feeders (6) and (6) at the same time, and the same applies when the oxidizing gas is taken in from the outside by the suction method. Control the suction volume. In order to perform those operations by the detection signal of the detector (16), well-known and commonly used means can be appropriately applied.
上記本発明方法に適用される酸化温度は1000℃以
上、好ましくは1200℃以上である。The oxidation temperature applied to the above-mentioned method of the present invention is 1000 ° C or higher, preferably 1200 ° C or higher.
本発明は叙上の通りであり、次いで本発明の作用につい
て説明する。The present invention is as described above, and then the operation of the present invention will be described.
再処理工程から排出されたハル(2)は無蓋容器(1)に積載
され、電気炉(3)内に装入され扉(12)を密閉する。The hull (2) discharged from the reprocessing step is loaded on the lidless container (1) and loaded into the electric furnace (3) to seal the door (12).
そのとき容器(1)の姿勢は炉内でレールなどにより規制
され、容器底部から突出している多孔管(9)の端部(11)
が第4−A図に示したように酸化性ガスの供給孔(14)と
互いに嵌挿し、ストッパ(15)の作用によって密に連結す
る。この状態で電気炉の加熱ヒータ(4)に通電し炉内温
度を昇温するとともに送給機(6)(6)・・・を作動して、
空気などの酸化性ガスを送入し、同時に排気ファン(7)
を運転し炉内ガスを排気管路を経て排出する。At that time, the attitude of the container (1) is regulated by rails in the furnace, and the end (11) of the perforated pipe (9) protruding from the bottom of the container
As shown in FIG. 4-A, the holes are fitted into the oxidizing gas supply holes (14) and tightly connected by the action of the stopper (15). In this state, the heater (4) of the electric furnace is energized to raise the temperature inside the furnace and the feeders (6) (6) ...
Injects oxidizing gas such as air, and at the same time, exhaust fan (7)
To discharge the gas in the furnace through the exhaust pipe.
排ガスは高性能フィルター(8)においてその中に含まれ
る微小な塵埃などの放射化生成物や放射性核種を除かれ
る。The exhaust gas is filtered by the high-performance filter (8) to remove activation products such as minute dust and radionuclides contained therein.
このようにして炉内には約1000℃以上,好ましくは
12000℃以上の高温酸化性ガス雰囲気が形成される
と共に、多孔管(9)よりハル堆積層の下層部分に送入さ
れる酸化性ガスによって堆積層の下部から上部に及ぶ隅
々まで万遍なく酸化性ガスが行き亘りハルを構成するジ
ルカロイの均一な酸化が短時間に達成され、未酸化部分
が残ることがない。In this way, a high-temperature oxidizing gas atmosphere of about 1000 ° C. or higher, preferably 12000 ° C. or higher is formed in the furnace, and the oxidizing gas sent to the lower part of the hull deposit layer through the perforated pipe (9). As a result, the oxidizing gas is evenly distributed from the lower part to the upper part of the deposited layer to uniformly oxidize the zircaloy forming the hull in a short time and no unoxidized part remains.
給気管路(18)を経て供給される酸化性ガスを予熱してお
くことは好ましいことである。また、上記の説明におい
ては酸化性ガスを給気管路より送給機により強制送入す
る場合を示したが、排気ファン(7)により排気して炉内
を負圧となし、空気などの酸化性ガスを吸入する方式を
とることも勿論可能である。It is preferable to preheat the oxidizing gas supplied via the air supply line (18). Further, in the above description, the case where the oxidizing gas is forcibly fed from the air supply line by the feeder is shown, but the exhaust fan (7) exhausts it to make the inside of the furnace a negative pressure, and to oxidize air etc. Of course, it is also possible to adopt a method of inhaling the characteristic gas.
更にハルを構成するジルカロイは既述の如く急激な酸化
により発火の危険性があるため、第5図に示した本発明
装置により反応速度を調節すればその危険を未然に防止
し、また迅速に消火を行い危険を排除することができ
る。Further, since the zircaloy constituting the hull has a risk of ignition due to rapid oxidation as described above, if the reaction rate is adjusted by the device of the present invention shown in FIG. You can extinguish the fire and eliminate the danger.
即ち、検知器(16)によって炉内の異常高温を検知した信
号は電子的プロセッサまたはニューマティック作動機構
を経て開閉弁(21)の作動力に変換され、弁(21)を作動し
てボンベ(17)からの不活性ガス供給量を調節する。それ
によって酸化反応速度は適度に制御されると共に、緊急
消火の際は弁(21)を全開し不活性ガスを大量に噴出する
と同時に酸化性ガスの供給を遮断して即時に消火するこ
とができる。That is, the signal that detects the abnormally high temperature in the furnace by the detector (16) is converted into the operating force of the on-off valve (21) through the electronic processor or the pneumatic operation mechanism, and the valve (21) is operated to operate the cylinder ( Adjust the amount of inert gas supplied from 17). As a result, the oxidation reaction rate is controlled appropriately, and in the case of emergency fire extinguishing, the valve (21) is fully opened to eject a large amount of inert gas and at the same time the supply of oxidizing gas can be cut off to immediately extinguish the fire. .
また、不活性ガスを給気管路(18)を通じて供給すること
もできるようにしたから、迅速な酸化反応の停止が確実
に達成される。Further, since the inert gas can be supplied through the air supply line (18), the rapid termination of the oxidation reaction can be surely achieved.
(比較例) 核燃料被覆管と実質的に同一である外径14mm,厚さ0.
8mm,長さ30〜50mmのジルカロイ短尺管の3kgを3
00mmW×300mmL×100mmHのハステロイX製無
蓋箱型容器に充填積載した。この容器は第3−B図に示
すような1本の多孔管(管径10mmΦ,吹出孔径2mm
Φ,孔数20)が底部に配設されたものを用いた。(Comparative Example) The outer diameter is 14 mm and the thickness is 0.1, which is substantially the same as the nuclear fuel cladding tube.
3 mm of Zircaloy short tube 8 mm long and 30-50 mm long
It was filled and loaded in an open box type container made of Hastelloy X of 00 mmW × 300 mmL × 100 mmH. This container consists of a single perforated pipe (tube diameter 10 mmΦ, blow hole diameter 2 mm as shown in Fig. 3-B.
Φ, the number of holes 20) was used at the bottom.
この容器を内径500mmW×400mmL×500mmHの
電気炉内に装入し扉と密閉した。This container was placed in an electric furnace having an inner diameter of 500 mmW × 400 mmL × 500 mmH and sealed with a door.
電気炉は第5図に示すような構造を有しており、空気供
給孔と容器の多孔管端部とは嵌合しカップリング機構に
より連結された。The electric furnace has a structure as shown in FIG. 5, and the air supply hole and the end of the perforated tube of the container were fitted and connected by a coupling mechanism.
先ず多孔管へ空気を供給する給気管路を閉じ、電気炉上
部への給気管路からのみ空気0.5m3/minの流量速度で送
入すると共に排気管路から排出することによって炉内に
空気流を形成しつつ加熱ヒータに通電した。前記給気管
路は排気管路中を対向して通過させることにより熱交換
され、供給空気は予熱された。First, the air supply pipe that supplies air to the perforated tube is closed, and air is introduced into the furnace only at the top of the electric furnace at a flow rate of 0.5 m 3 / min and discharged from the exhaust pipe. The heater was energized while forming a stream. The air supply line was heat-exchanged by passing through the exhaust line in an opposed manner, and the supply air was preheated.
炉内温度は80分後に1200℃に到達し、その温度に
保持して120分間運転を継続したのち、通電及び空気
流を停止した。降温後、ジルカロイ短尺管堆積層の酸化
状態を調べたところ、堆積層表面より約70mmの厚さの
層はよく酸化されたジルカロイ短尺管は脆い淡黄色酸化
物に変性していたが底部より約30mmの厚さの下層部分
の短尺物は一部酸化を受けジルカロイ特有の黒色金属を
呈しているものが混在していた。The temperature in the furnace reached 1200 ° C. after 80 minutes, the temperature was maintained at that temperature and the operation was continued for 120 minutes, and then the energization and the air flow were stopped. After cooling, the oxidation state of the Zircaloy short tube deposited layer was examined. A layer with a thickness of about 70 mm from the surface of the deposited layer was well oxidized. The short length of the lower layer having a thickness of 30 mm was partially oxidized and mixed with a black metal peculiar to Zircaloy.
(本実施例) 次に本発明例として下部の給気管路を開き、容器底部多
孔管からも空気を0.4m3/minの流量速度で送入し、上部
給気量を0.3m3/minに絞った他はすべて上記比較例と同
一条件でジルカロイ短尺管の酸化処理を行った。(Embodiment) Next, as an embodiment of the present invention, the lower air supply conduit is opened, air is also fed from the container bottom perforated pipe at a flow rate of 0.4 m 3 / min, and the upper air supply is 0.3 m 3 / min The zircaloy short tube was oxidized under the same conditions as in the comparative example except for the above.
処理後の酸化状態を観察したところ、堆積層全体に亘
り、深部に至る迄、均一に酸化物に変性していることが
確認された。As a result of observing the oxidation state after the treatment, it was confirmed that the entire surface of the deposited layer was uniformly transformed into an oxide up to the deep part.
かくして上記比較例及び本発明例により本発明方法並び
に装置の優れた効果が確認された。Thus, the excellent effects of the method and apparatus of the present invention were confirmed by the above comparative example and the present invention example.
本発明は上述のような構成と作用とを有するものである
から、使用済核燃料の再生工程から大量に排出されるハ
ルを商業的規模で安全,迅速、且つ確実に酸化して取扱
容易に放射性核種を閉じ込め安定な減容固化体に焼結
し、緻密化することができるという優れた効果がある。INDUSTRIAL APPLICABILITY Since the present invention has the above-described structure and operation, it is possible to safely, quickly and reliably oxidize a large amount of hulls discharged from the spent nuclear fuel regeneration process on a commercial scale to make it radioactive. There is an excellent effect that the nuclide can be densified by sintering into a stable volume-reduced solidified body.
第1図は一般的態様のハルを加熱酸化処理する方法なら
びに装置の概要を示す説明図、第2図は第1図の方法に
よって得られたハルの酸化状態を示す説明図、第3−A
図は本発明に用いられる無蓋容器の縦断面概要図、第3
−B図はその平面図、第3−C図はその別の態様の平面
図、第4図は本発明装置の縦断面概要図、第4−A図は
その要部説明図、第4−B図は同装置による方法の作用
説明図、第5図は本発明の改良された方法ならびに装置
を示す縦断面概要図、第5−A図はその要部説明図であ
る。 (1)……無蓋容器, (2)……核燃料被覆管短尺物, (3)……電気炉,(4)……加熱ヒータ, (5)……酸化性ガス,(6)……送給機, (7)……排気ファン, (8)……高性能フィルター, (9)……多孔管,(10)……吹出孔, (11)……端部,(12)……扉, (13)……炉体,(14)……供給孔, (15)……ストッパ,(16)……検知器, (17)……ボンベ,(18)……給気管路、 (19)……排気孔,(20)……排気管路, (21)……開閉弁, (22)……不活性ガス供給管,FIG. 1 is an explanatory view showing an outline of a method and an apparatus for heat-oxidizing a hull of a general mode, FIG. 2 is an explanatory view showing an oxidation state of the hull obtained by the method of FIG. 1, and 3-A.
FIG. 3 is a schematic vertical sectional view of a lidless container used in the present invention,
-B is a plan view thereof, FIG. 3-C is a plan view of another mode thereof, FIG. 4 is a schematic vertical sectional view of the device of the present invention, FIG. FIG. 5B is an explanatory view of the operation of the method by the same apparatus, FIG. 5 is a schematic vertical sectional view showing an improved method and apparatus of the present invention, and FIG. (1) …… Uncovered container, (2) …… Short length of nuclear fuel cladding, (3) …… Electric furnace, (4) …… Heating heater, (5) …… Oxidizing gas, (6) …… Sending Feeder, (7) …… Exhaust fan, (8) …… High performance filter, (9) …… Perforated tube, (10) …… Blowout hole, (11) …… End, (12) …… Door , (13) …… Furnace body, (14) …… Supply hole, (15) …… Stopper, (16) …… Detector, (17) …… Cylinder, (18) …… Air supply line, (19 ) …… Exhaust hole, (20) …… Exhaust pipe, (21) …… Open / close valve, (22) …… Inert gas supply pipe,
───────────────────────────────────────────────────── フロントページの続き (72)発明者 塩月 正雄 茨城県東茨城郡大洗町成田町4002 動力 炉・核燃料開発事業団大洗工学センター内 (72)発明者 小松 史明 兵庫県神戸市北区筑紫が丘6丁目2の11 (56)参考文献 特開 昭59−73040(JP,A) 特開 昭60−198498(JP,A) ─────────────────────────────────────────────────── ─── Continuation of the front page (72) Masao Shiotsuki Inventor Masao Shiotsuki 4002 Narita-machi, Oarai-cho, Higashi-Ibaraki-gun, Ibaraki Oarai Engineering Center, Power Reactor and Nuclear Fuel Development Corporation (72) Fumiaki Komatsu Chikugaoka, Kita-ku, Kobe-shi, Hyogo 6-2 / 11 (56) Reference JP-A-59-73040 (JP, A) JP-A-60-198498 (JP, A)
Claims (10)
燃料被覆管短尺物の堆積層を収容した無蓋容器を電気炉
中に装入し、炉内を酸化性ガス雰囲気となすとともに上
記堆積層の下層部に酸化性ガスを送入しつつ加熱処理を
施し、さらに上記処理による前記核燃料被覆管の過激な
酸化反応を抑制するために不活性ガスを炉内に供給する
ことを特徴とする使用済核燃料被覆管の加熱酸化処理方
法。1. An open-ended container containing a deposited layer of a spent nuclear fuel cladding short piece mainly composed of zircaloy metal is placed in an electric furnace to create an oxidizing gas atmosphere in the furnace and a lower layer of the deposited layer. Spent nuclear fuel, which is characterized by performing a heat treatment while feeding an oxidizing gas to the section, and further supplying an inert gas into the reactor in order to suppress the radical oxidation reaction of the nuclear fuel cladding tube by the above treatment. Thermal oxidation treatment method for cladding.
1項記載の使用済核燃料被覆管の加熱酸化処理方法。2. The method for thermal oxidation treatment of a spent nuclear fuel cladding tube according to claim 1, wherein the oxidizing gas is air.
行われる特許請求の範囲第1項または第2項記載の使用
済核燃料被覆管の加熱酸化処理方法。3. The method for heat-oxidizing a spent nuclear fuel cladding tube according to claim 1 or 2, wherein the heat treatment is performed at a temperature of at least 1000 ° C.
行われる特許請求の範囲第3項記載の使用済核燃料被覆
管の加熱酸化処理方法。4. The method for heat-oxidizing a spent nuclear fuel cladding tube according to claim 3, wherein the heat treatment is performed at a temperature of at least 1200 ° C.
配設された多孔管を通じて行われる前記特許請求の範囲
第1項乃至第4項のいずれかの項に記載の使用済核燃料
被覆管の加熱酸化処理方法。5. The used gas according to any one of claims 1 to 4, wherein the oxidizing gas is introduced through a perforated pipe provided in a lower layer portion inside the deposition layer. Method for thermal oxidation treatment of nuclear fuel cladding.
性ガス雰囲気が不活性ガス雰囲気に置換される前記特許
請求の範囲第1項乃至第5項のいずれかの項に記載の使
用済核燃料被覆管の加熱酸化処理方法。6. The used gas according to any one of claims 1 to 5, wherein the oxidizing gas atmosphere in the furnace is replaced with an inert gas atmosphere by supplying the inert gas. Method for thermal oxidation treatment of nuclear fuel cladding.
の範囲第1項乃至第6項のいずれかの項に記載の使用済
核燃料被覆管の加熱酸化処理方法。7. The method for thermal oxidation treatment of a spent nuclear fuel cladding tube according to any one of claims 1 to 6, wherein the inert gas is nitrogen gas.
れる前記特許請求の範囲第1項乃至第7項のいずれかの
項に記載の使用済核燃料被覆管の加熱酸化処理方法。8. The method for thermal oxidation treatment of a spent nuclear fuel cladding tube according to claim 1, wherein the inert gas is supplied to a lower layer portion of the deposited layer.
容する無蓋容器と、該無蓋容器を出し入れするための扉
を有する電気炉とよりなり、該電気炉は、炉内に酸化性
ガスを送入するための送給機にそれぞれ通ずる複数個の
給気管路と、排気ファン及び高性能フィルターをそれぞ
れ設けた排気管路とを具え、また、前記無蓋容器はその
底部に多孔管を具えており、該容器が電気炉内に装入さ
れた状態において前記多孔管の一端が前記給気管路の一
端と連結されるようになっていることを特徴とする使用
済核燃料被覆管の加熱酸化処理装置。9. An open-ended container for accommodating a deposited layer of a short piece of a spent nuclear fuel cladding tube, and an electric furnace having a door for inserting and removing the open-ended container, wherein the electric furnace is oxidizable in the furnace. It comprises a plurality of air supply pipes each communicating with a feeder for introducing gas, and an exhaust pipe having an exhaust fan and a high-performance filter, respectively, and the lidless container has a perforated pipe at its bottom. Heating the spent nuclear fuel cladding tube, characterized in that one end of the perforated tube is connected to one end of the air supply line when the container is loaded in an electric furnace. Oxidation treatment equipment.
収容する無蓋容器と、該無蓋容器を出し入れするための
扉を有する電気炉とよりなり、該電気炉は、炉内に酸化
性ガスを送入するための送給機にそれぞれ通ずる複数個
の給気管路と、排気ファンおよび高性能フィルターをそ
れぞれ設けた排気管路とを具え、また前記無蓋容器はそ
の底部に多孔管を具えており、該容器が電気炉内に装入
された状態において前記多孔管の一端が前記給気管路の
一端と連結されるようになすとともに、開閉弁を介して
路内に連通する不活性ガス供給管を付設し、さらに電気
炉内温度検知器を設けて該検知器よりの信号によって上
記開閉弁を作動せしめ炉内の酸化反応速度を制御し得る
ようになしたことを特徴とする使用済核燃料被覆管の加
熱酸化処理装置。10. An open-ended container for accommodating a deposited layer of a short material of a spent nuclear fuel cladding tube, and an electric furnace having a door for inserting and removing the open-ended container, wherein the electric furnace is oxidizable in the furnace. It comprises a plurality of air supply conduits each communicating with a feeder for feeding gas, an exhaust conduit provided with an exhaust fan and a high-performance filter, and the lidless container has a perforated pipe at the bottom thereof. In addition, one end of the perforated pipe is connected to one end of the air supply pipe in a state where the container is placed in an electric furnace, and an inert gas communicating with the inside of the pipe via an on-off valve is provided. A supply pipe is additionally provided, and an electric furnace temperature detector is further provided so that the on-off valve can be operated by a signal from the detector to control the oxidation reaction rate in the furnace. Thermal oxidation treatment equipment for nuclear fuel cladding.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP167786A JPH0644076B2 (en) | 1986-01-07 | 1986-01-07 | Method and apparatus for thermal oxidation treatment of spent nuclear fuel cladding tube |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP167786A JPH0644076B2 (en) | 1986-01-07 | 1986-01-07 | Method and apparatus for thermal oxidation treatment of spent nuclear fuel cladding tube |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS62159099A JPS62159099A (en) | 1987-07-15 |
| JPH0644076B2 true JPH0644076B2 (en) | 1994-06-08 |
Family
ID=11508140
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP167786A Expired - Fee Related JPH0644076B2 (en) | 1986-01-07 | 1986-01-07 | Method and apparatus for thermal oxidation treatment of spent nuclear fuel cladding tube |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH0644076B2 (en) |
Families Citing this family (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH03235100A (en) * | 1990-02-13 | 1991-10-21 | Mitsubishi Heavy Ind Ltd | Volume reduction method for sheared segment of cladding tube of spent nuclear fuel |
| US7876906B2 (en) | 2006-05-30 | 2011-01-25 | Sonitus Medical, Inc. | Methods and apparatus for processing audio signals |
| US7682303B2 (en) * | 2007-10-02 | 2010-03-23 | Sonitus Medical, Inc. | Methods and apparatus for transmitting vibrations |
| US8433082B2 (en) | 2009-10-02 | 2013-04-30 | Sonitus Medical, Inc. | Intraoral appliance for sound transmission via bone conduction |
Family Cites Families (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5973040A (en) * | 1982-10-21 | 1984-04-25 | Mitsubishi Heavy Ind Ltd | Fluidized bed type solid-gas catalytic reaction apparatus |
| JPS60198498A (en) * | 1984-03-21 | 1985-10-07 | 動力炉・核燃料開発事業団 | Method of treating spent fuel coated tube, etc. |
-
1986
- 1986-01-07 JP JP167786A patent/JPH0644076B2/en not_active Expired - Fee Related
Also Published As
| Publication number | Publication date |
|---|---|
| JPS62159099A (en) | 1987-07-15 |
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