EP2791945A2 - Traitement de déchets radioactifs carbonés comportant du chlore. - Google Patents

Traitement de déchets radioactifs carbonés comportant du chlore.

Info

Publication number
EP2791945A2
EP2791945A2 EP12816710.3A EP12816710A EP2791945A2 EP 2791945 A2 EP2791945 A2 EP 2791945A2 EP 12816710 A EP12816710 A EP 12816710A EP 2791945 A2 EP2791945 A2 EP 2791945A2
Authority
EP
European Patent Office
Prior art keywords
waste
treatment
chlorine
solution
acid solution
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.)
Withdrawn
Application number
EP12816710.3A
Other languages
German (de)
English (en)
French (fr)
Inventor
Gérard LAURENT
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Electricite de France SA
Original Assignee
Electricite de France SA
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 Electricite de France SA filed Critical Electricite de France SA
Publication of EP2791945A2 publication Critical patent/EP2791945A2/fr
Withdrawn legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21FPROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/001Decontamination of contaminated objects, apparatus, clothes, food; Preventing contamination thereof
    • G21F9/002Decontamination of the surface of objects with chemical or electrochemical processes
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21FPROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00Treating radioactively contaminated material; Decontamination arrangements therefor
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21FPROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/28Treating solids
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21FPROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/28Treating solids
    • G21F9/30Processing
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21FPROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/28Treating solids
    • G21F9/30Processing
    • G21F9/32Processing by incineration

Definitions

  • the present invention relates to the treatment of radioactive waste, in particular but not exclusively based on graphite.
  • the decontamination of an irradiated graphite matrix may be carried out using a so-called “steam reforming” technique (or “steam reforming” in Anglo-Saxon terms) as defined in particular in document US-6. , 625, 248.
  • steam reforming or “steam reforming” in Anglo-Saxon terms
  • the technique presented in this document does not ensure acceptable radioactive releases.
  • organic chlorine a form of chlorine termed "organic” chlorine, defined by C-Cl bonds specific to “aromatic carbon” (in particular of the high energy double bond type), and directly linked to the carbon of the carbon matrix usually forming graphite, and
  • chlorine a form of chlorine
  • inorganic chlorine in the form of oxychlorides of undetermined composition, probably located in the porosity of the graphitic material (called “chlorite compounds (C102-) and chlorate (C103-)").
  • the acidic solution may comprise sulfuric acid (H 2 SO 4 ). Tests with this type of acid have given good results.
  • the acidic solution further comprises an oxygen supply element in the acidic solution, for example hydrogen peroxide (H 2 O 2 ) in a range of proportions typically comprised between 0.1% and 20%. % (a proportion of 5% yielding good results presented below).
  • H 2 O 2 hydrogen peroxide
  • the soaking in the acidic solution can be carried out in a time range of between 15 and 20 hours, for example about 18 hours.
  • the aforementioned thermal shock made for example by roasting, can be carried out in a temperature range between 800 and 1200 ° C (for example about 1000 ° C) for a period of between 15 and 30 minutes (for example about twenty minutes).
  • the present invention thus makes it possible to extract chlorine 36, of organic type, as demonstrated in the exemplary embodiments presented in detail below.
  • leaching of the radionuclides out of the irradiated graphite can be obtained by soaking in a highly acidic and oxidizing solution, followed by a thermal shock.
  • the present invention also aims at a facility for the treatment of carbonaceous radioactive waste, for the purpose of process according to one of the preceding claims, characterized in that it comprises: a tank for storing said waste in an acidic solution, and
  • Heating means shaped to apply a thermal shock to said waste after soaking in said acid solution.
  • FIG. 1 diagrammatically illustrates the main steps of the process within the meaning of the invention
  • Carbonaceous radioactive waste was crushed into powder form to constitute the different samples of the table above.
  • Each sample having a mass of 5 grams and observed particle sizes distributed typically between 2380 and 4000 microns after crushing, was: soaked for 18 hours in a solution of the aforementioned type (H 2 SO 4 and H 2 O 2 ),
  • o by rapid heating in a range of 5 to 60 minutes, for example for 20 minutes
  • o high temperature between 900 and 1200 ° C, for example at 1000 ° C.
  • FIG. 1 summarizes the main steps of the process within the meaning of the invention, comprising: for example, during a first step S1, the recovery of radioactive carbonaceous waste, for example in the form of graphite,
  • step S3 after identifying a sufficient soaking time (for example 18 hours) in step S3, applying a heat treatment, by roasting, at a temperature of the order of 1000 ° C, in step S4;
  • step S5 After identifying a sufficient duration of heat treatment (for example 20 minutes) in step S5,
  • chlorine 36 can be recovered in the acid solution and treated separately, and the carbonaceous waste can then be subjected to a vapor reforming treatment as described, for example, in the document cited above.
  • WO-2010/103210 step S6.
  • the installation for the implementation of this process may then comprise, with reference to FIG. 2, a tank CU and a conveyor C1 of GR waste products pouring into a highly acidic and oxygenated solution (H 2 SO 4 H 2 O 2 ) contained in the tank CU, which is surrounded (in the example shown) heating means MC to apply a heat shock type treatment.
  • the GR waste thus treated can then be recovered by the second conveyor C2 (after filtering, for example, the acid solution now containing chlorine-36) to be conveyed to a steam reforming installation.
  • Chlorine 36 can be recovered for example from the solution remaining under the tank CU, as presented as a purely illustrative example in Figure 2.
  • hydrogen peroxide is a good oxygen delivery element in a solution.
  • step a) the proportions of the oxygen supply element in the acid solution are susceptible to variations depending on the acids and elements employed.
  • the soaking time in step a) is capable of variations. The same goes for the temperature and the duration of the thermal shock.
  • step a) of soaking in the acid solution is preceded by a crushing of the carbonaceous waste to reduce it to powder.
  • this implementation is not essential and it can be alternatively provided to directly dipping solid graphite for example up to heart in an acid solution.

Landscapes

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Chemical & Material Sciences (AREA)
  • Environmental & Geological Engineering (AREA)
  • Electrochemistry (AREA)
  • General Chemical & Material Sciences (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Food Science & Technology (AREA)
  • Processing Of Solid Wastes (AREA)
  • Solid-Sorbent Or Filter-Aiding Compositions (AREA)
  • Manufacture And Refinement Of Metals (AREA)
  • Gasification And Melting Of Waste (AREA)
EP12816710.3A 2011-12-16 2012-12-11 Traitement de déchets radioactifs carbonés comportant du chlore. Withdrawn EP2791945A2 (fr)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
FR1161814A FR2984583A1 (fr) 2011-12-16 2011-12-16 Traitement de dechets radioactifs carbones comportant du chlore.
PCT/FR2012/052883 WO2013088059A2 (fr) 2011-12-16 2012-12-11 Traitement de déchets radioactifs carbonés comportant du chlore.

Publications (1)

Publication Number Publication Date
EP2791945A2 true EP2791945A2 (fr) 2014-10-22

Family

ID=47599056

Family Applications (1)

Application Number Title Priority Date Filing Date
EP12816710.3A Withdrawn EP2791945A2 (fr) 2011-12-16 2012-12-11 Traitement de déchets radioactifs carbonés comportant du chlore.

Country Status (9)

Country Link
US (1) US20140350320A1 (ko)
EP (1) EP2791945A2 (ko)
JP (1) JP2015505967A (ko)
KR (1) KR20140133500A (ko)
CN (1) CN104170019A (ko)
FR (1) FR2984583A1 (ko)
RU (1) RU2014129056A (ko)
WO (1) WO2013088059A2 (ko)
ZA (1) ZA201404590B (ko)

Families Citing this family (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
RU2624270C1 (ru) * 2016-02-24 2017-07-03 Акционерное общество "Радиевый институт имени В.Г. Хлопина" Способ переработки отходов реакторного графита
RU2726145C1 (ru) * 2019-04-25 2020-07-09 Валерий Вадимович Крымский Способ уменьшения радиоактивности отработавших графитовых блоков и установка для его осуществления
CN110715296B (zh) * 2019-09-28 2021-01-12 山西方洁路路通净化技术有限公司 负压无烟筒式焚烧系统
RU2765864C1 (ru) * 2020-10-09 2022-02-03 Акционерное Общество "Наука И Инновации" Способ переработки облученного в реакторе АЭС углерода и устройство для его реализации
CN113658736A (zh) * 2021-08-24 2021-11-16 浙江省辐射环境监测站 一种利用碳基纳滤膜去除溶液中放射性核素的方法

Family Cites Families (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE1958464A1 (de) * 1969-11-21 1971-06-03 Alkem Gmbh Verfahren zur nasschemischen Verbrennung von organischem Material
DE2916203A1 (de) * 1979-04-21 1980-11-06 K E W A Kernbrennstoff Wiedera Verfahren zur behandlung von brennbaren, festen, radioaktiven abfaellen
DE3375051D1 (en) * 1983-12-13 1988-02-04 Kernforschungsz Karlsruhe Process for the oxidative disposal of carbon particles contaminated by noxious material
FR2691524B1 (fr) * 1992-05-20 1997-12-12 Servithen Sarl Procede et installation pour la destruction sans contamination de l'environnement de pieces de graphite eventuellement radioactives.
UA57884C2 (uk) 1999-10-14 2003-07-15 Дейвід БРЕДБЕРІ Спосіб обробки радіоактивного графіту
JP2003014890A (ja) * 2001-06-28 2003-01-15 Toshiba Corp 放射化黒鉛の処分方法及びその装置
FR2943167B1 (fr) 2009-03-11 2011-03-25 Electricite De France Traitement de dechets radioactifs carbones.
DE102010026936A1 (de) * 2010-07-12 2012-01-12 Forschungszentrum Jülich GmbH Verfahren zur Teildekontamination radioaktiver Abfälle

Non-Patent Citations (1)

* Cited by examiner, † Cited by third party
Title
See references of WO2013088059A2 *

Also Published As

Publication number Publication date
RU2014129056A (ru) 2016-02-10
ZA201404590B (en) 2015-12-23
FR2984583A1 (fr) 2013-06-21
US20140350320A1 (en) 2014-11-27
KR20140133500A (ko) 2014-11-19
JP2015505967A (ja) 2015-02-26
CN104170019A (zh) 2014-11-26
WO2013088059A2 (fr) 2013-06-20
WO2013088059A3 (fr) 2013-10-24

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