WO2003032324A1 - Procede de retraitement de combustible nucleaire epuise et dispositif correspondant - Google Patents

Procede de retraitement de combustible nucleaire epuise et dispositif correspondant Download PDF

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Publication number
WO2003032324A1
WO2003032324A1 PCT/RU2001/000542 RU0100542W WO03032324A1 WO 2003032324 A1 WO2003032324 A1 WO 2003032324A1 RU 0100542 W RU0100542 W RU 0100542W WO 03032324 A1 WO03032324 A1 WO 03032324A1
Authority
WO
WIPO (PCT)
Prior art keywords
snf
τβs
τeχnοlοgichesκοgο
recycling
τem
Prior art date
Application number
PCT/RU2001/000542
Other languages
English (en)
Russian (ru)
Inventor
Lev Nikolaevich Maximov
Original Assignee
Lev Nikolaevich Maximov
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by Lev Nikolaevich Maximov filed Critical Lev Nikolaevich Maximov
Publication of WO2003032324A1 publication Critical patent/WO2003032324A1/fr

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Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G21C19/42—Reprocessing of irradiated fuel
    • G21C19/44—Reprocessing of irradiated fuel of irradiated solid fuel
    • G21C19/46—Aqueous processes, e.g. by using organic extraction means, including the regeneration of these means
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G21C19/34—Apparatus or processes for dismantling nuclear fuel, e.g. before reprocessing ; Apparatus or processes for dismantling strings of spent fuel elements
    • G21C19/36—Mechanical means only
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G21C19/34—Apparatus or processes for dismantling nuclear fuel, e.g. before reprocessing ; Apparatus or processes for dismantling strings of spent fuel elements
    • G21C19/38—Chemical means only
    • 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

Definitions

  • ⁇ ⁇ aches ⁇ ve is ⁇ dny ⁇ g & z ⁇ vy ⁇ ⁇ eagen ⁇ v is ⁇ lzuyu ⁇ ⁇ , and ⁇ l ⁇ d ⁇ ugie gal ⁇ gesh ⁇ dy i ⁇ in mixtures and or i ⁇ ⁇ imiches ⁇ m s ⁇ edinensh ⁇ , na ⁇ ime ⁇ , ⁇ g ⁇ 3 and S ⁇ z and ⁇ a ⁇ same v ⁇ d ⁇ d, ⁇ sid ugle ⁇ da and d ⁇ ugie gaz ⁇ vye ⁇ isli ⁇ eli.
  • ⁇ ⁇ sn ⁇ vn ⁇ y ⁇ e ⁇ n ⁇ l ⁇ giches ⁇ y z ⁇ ne is ⁇ lzuyu ⁇ ele ⁇ is ⁇ vye ⁇ az ⁇ yady and or co- ⁇ leyuischy ele ⁇ iches ⁇ ⁇ az ⁇ yad with na ⁇ yan HAND ⁇ 100 v ⁇ l ⁇ and b ⁇ lee in zavisim ⁇ s ⁇ i ⁇ ⁇ azme ⁇ a ⁇ e ⁇ n ⁇ l ⁇ giches ⁇ g ⁇ zaz ⁇ a between ⁇ e ⁇ e ⁇ aba ⁇ yvaemymi ⁇ S and vel ⁇ miny davlesh ⁇ ya-ext ⁇ ⁇ ⁇ e ⁇ n ⁇ l ⁇ giches ⁇ g ⁇ ⁇ ea ⁇ a.
  • the section of flash welding is equipped with nodes of technical processes, for example, electric and / or ultrasound.
  • the process unit is equipped with a tangential output of basic process and / or auxiliary neutral gases in a vortex.
  • Figure 1 - shows a general view of the device at the time of ⁇ - ⁇ ;
  • SIGNIFICANT FOX (DR. 26) 4 gateways; conditionally indicated rotational movement of 45 terminals with ⁇ ; an initial 46 account with a pre-gateway; Location 47 of the terminal with the user in the intermediate gateway; The consumer of 48 pressurized is in the upper position; Turning the switch 49 on with
  • Gateway systems at the end of the switch 48 at the extreme upper 50; The punter of the container with ⁇ in the original position 51; sealing cup 44 in lower position 52; Pusher 48 at last location 53; output 54 of switch 48; room 55 of the original accommodation 54 and 49; conditionally indicated delivery 56 ⁇ at the entrance to the gateway system; The end part 57 ⁇ C from the entrance to the gateway system; receiver camera 58 of the gateway system of the left branch of the processing unit; pusher 59
  • the end part is 60 ⁇ in the first place;
  • the end part is 60 ⁇ in the first place, by transmitting it to the processing unit;
  • pusher 59 yogurt ⁇ in the original position 61;
  • the ring part 63 ⁇ in the foreign chamber of the gateway system;
  • the end part of 69 ° C is located at the exit from the gateway system;
  • Shooter 67 is located at the exit from the gateway system;
  • SIGNIFICANT FOX (DR. 26) 5 scans ⁇ cutting laser beams intensify The chemical processes of the materials supplied from the lower part of the process unit are available in the commercial 32, 46 furthermore.
  • Pe ⁇ e ⁇ aba ⁇ yvae maya ⁇ S on vy ⁇ de of sis ⁇ emy shlyuz ⁇ vashgya ( ⁇ isash ⁇ e ⁇ y dae ⁇ sya sh ⁇ zhe) ⁇ s ⁇ u ⁇ ae ⁇ in ⁇ us ⁇ iemn ⁇ y ⁇ ame ⁇ y 15 ⁇ l ⁇ zhesh ⁇ e 60, from ⁇ g ⁇ ⁇ l ⁇ a ⁇ elem 17 (is ⁇ dn ⁇ na ⁇ dyaschimsya in ⁇ l ⁇ zhenii 61) ⁇ S ⁇ e ⁇ emeschayu ⁇ in z ⁇ nu ⁇ li ⁇ v ⁇ g ⁇ node 13 ⁇ iv ⁇ d ⁇ m 14 further ⁇ dachi ⁇ S in se ⁇ tsiyu ⁇ tsev ⁇ y weld 12, equipped with nodes 11 of technical safety interruption from the previous Orient Phase ⁇ for securing the failure of processors in general.
  • the process of gateway EC in camera 15 is carried out as follows. With a recommended plug, 56 ⁇ (57) is supplied to the front camera 58 of the gateway system to catch the 13 nodes of the êt ⁇ wise ⁇ transmitter with the 14th disconnect. Further, the process of the gateway to the USC is carried out by known companies with the final process of the USC at 69. After the side flange 67, equipped with an output 70, the processed C is supplied in the original 60 and further process is carried out above.
  • a gateway system of 1 is installed for the connection to the independent part of the world, it is part of a
  • the gateway process of 46 is subject to the following process.
  • ⁇ is ⁇ dn ⁇ m ⁇ l ⁇ zhenii usl ⁇ vn ⁇ ⁇ azannym me ⁇ ashgzm ⁇ m ⁇ dachi 37 ⁇ n ⁇ eyne ⁇ ⁇ e ⁇ emeschayu ⁇ in ⁇ z ⁇ schiyu over ⁇ l ⁇ a ⁇ elem 51.
  • ⁇ iv ⁇ d ⁇ m 54 ⁇ n ⁇ eyne ⁇ s ⁇ vmes ⁇ n ⁇ with ge ⁇ me ⁇ izi ⁇ uyuschim s ⁇ a ⁇ an ⁇ m 44 ⁇ e ⁇ emeschayu ⁇ in ve ⁇ nee ⁇ l ⁇ zhenie d ⁇ s ⁇ y ⁇ v ⁇ i with u ⁇ l ⁇ neniem 42.
  • P ⁇ sle cheg ⁇ ⁇ iv ⁇ d ⁇ m 35 is ⁇ dny ⁇ n ⁇ eyne ⁇ 46 ⁇ e ⁇ e ⁇ aba ⁇ yvaemymi ma ⁇ e ⁇ ialash ⁇ ⁇ dayu ⁇ ne ⁇ s ⁇ eds ⁇ venn ⁇ in itself z ⁇ nu ⁇ e ⁇ n ⁇ l ⁇ giches ⁇ y ⁇ e ⁇ e ⁇ ab ⁇ i.
  • P ⁇ sle ⁇ imiches ⁇ y ⁇ e ⁇ e ⁇ ab ⁇ i and sam ⁇ g ⁇ ⁇ n ⁇ eyne ⁇ a and eg ⁇ s ⁇ de ⁇ zhim ⁇ g ⁇ , d ⁇ ⁇ edelenn ⁇ g ⁇ minimaln ⁇ g ⁇ ⁇ bema, ⁇ n ⁇ i ⁇ si ⁇ ue ⁇ sya uzl ⁇ m ne ⁇ dvizhn ⁇ m s ⁇ s ⁇ yanii 31 and 34 ⁇ l ⁇ a ⁇ el ⁇ us ⁇ ae ⁇ sya for ⁇ iema ⁇ che ⁇ edn ⁇ g ⁇ ⁇ n ⁇ eyne ⁇ a of sis ⁇ emy shlyuz ⁇ vaniya further schg ⁇ l ⁇ v ⁇ yae ⁇ sya.

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Chemical & Material Sciences (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • General Chemical & Material Sciences (AREA)
  • Laser Beam Processing (AREA)
  • Nitrogen And Oxygen Or Sulfur-Condensed Heterocyclic Ring Systems (AREA)

Abstract

L'invention se rapporte aux techniques de retraitement de combustible nucléaire épuisé (CNE) et peut s'utiliser également pour la fluoration et/ou la chloration de n'importe quels matériaux. Le procédé comprend le retraitement du CNE, qui utilise en tant que réactifs initiaux des gaz chimiquement actifs. Le CNE à retraiter a la forme d'assemblages combustibles déplacés les uns vers les autres à l'intérieur d'un réacteur de production le long d'un axe longitudinal commun, jusqu'à ce qu'un intervalle technique soit formé. Les réactions chimiques sont déclenchées par des processus à étincelles électriques et le rayonnement laser. Le dispositif de retraitement du CNE comprend une enveloppe de protection extérieure et des compartiments techniques ainsi que des systèmes d'acheminement de réactifs chimiques et d'évacuation de produits fabriqués. L'enveloppe étanche du réacteur de production est munie de deux branches technologiques, opposées et coaxiales, servant à piloter l'alimentation à contre-courant en CNE à traiter. L'enveloppe du réacteur de production comprend deux unités d'entrée du rayonnement laser et une unité d'introduction de containers. L'invention permet d'augmenter l'efficacité de traitement du CNE, de créer une technologie de retraitement plus propre, d'augmenter la sûreté nucléaire des processus de retraitement du CNE et d'autres matériaux et déchets radioactifs.
PCT/RU2001/000542 2001-10-08 2001-12-13 Procede de retraitement de combustible nucleaire epuise et dispositif correspondant WO2003032324A1 (fr)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
RU2001127252A RU2199162C1 (ru) 2001-10-08 2001-10-08 Способ переработки отработавшего ядерного топлива (оят) и устройство для его осуществления
RU2001127252 2001-10-08

Publications (1)

Publication Number Publication Date
WO2003032324A1 true WO2003032324A1 (fr) 2003-04-17

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Family Applications (1)

Application Number Title Priority Date Filing Date
PCT/RU2001/000542 WO2003032324A1 (fr) 2001-10-08 2001-12-13 Procede de retraitement de combustible nucleaire epuise et dispositif correspondant

Country Status (2)

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RU (1) RU2199162C1 (fr)
WO (1) WO2003032324A1 (fr)

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
RU2597874C2 (ru) * 2015-01-12 2016-09-20 Федеральное государственное унитарное предприятие "Горно-химический комбинат" (ФГУП "ГХК") Установка для переработки, отверждения и упаковки высокоактивных отходов

Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3393981A (en) * 1963-05-15 1968-07-23 Kernforschung Gmbh Ges Fuer Method of decomposing a nuclear fuel in a fused salt system by using nitric oxide
DE3420803A1 (de) * 1984-06-04 1985-12-05 Kraftwerk Union AG, 4330 Mülheim Aufbereitungsanlage fuer verbrauchte kernreaktor-brennelemente
RU2084978C1 (ru) * 1991-04-05 1997-07-20 Фраматом Способ дезактивации поверхности и устройство для дезактивации лазером поверхности
RU2106731C1 (ru) * 1996-08-12 1998-03-10 Физический институт им.П.Н.Лебедева РАН Лазер с перестраиваемыми спектральными и временными характеристиками
RU2111169C1 (ru) * 1997-02-04 1998-05-20 Сибирский химический комбинат Способ фторирования металлического урана до гексафторида урана
RU2143940C1 (ru) * 1999-01-10 2000-01-10 Сибирский химический комбинат Сублимационный аппарат

Patent Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3393981A (en) * 1963-05-15 1968-07-23 Kernforschung Gmbh Ges Fuer Method of decomposing a nuclear fuel in a fused salt system by using nitric oxide
DE3420803A1 (de) * 1984-06-04 1985-12-05 Kraftwerk Union AG, 4330 Mülheim Aufbereitungsanlage fuer verbrauchte kernreaktor-brennelemente
RU2084978C1 (ru) * 1991-04-05 1997-07-20 Фраматом Способ дезактивации поверхности и устройство для дезактивации лазером поверхности
RU2106731C1 (ru) * 1996-08-12 1998-03-10 Физический институт им.П.Н.Лебедева РАН Лазер с перестраиваемыми спектральными и временными характеристиками
RU2111169C1 (ru) * 1997-02-04 1998-05-20 Сибирский химический комбинат Способ фторирования металлического урана до гексафторида урана
RU2143940C1 (ru) * 1999-01-10 2000-01-10 Сибирский химический комбинат Сублимационный аппарат

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Publication number Publication date
RU2199162C1 (ru) 2003-02-20

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