US3773177A - Treatment process - Google Patents

Treatment process Download PDF

Info

Publication number
US3773177A
US3773177A US00119339A US3773177DA US3773177A US 3773177 A US3773177 A US 3773177A US 00119339 A US00119339 A US 00119339A US 3773177D A US3773177D A US 3773177DA US 3773177 A US3773177 A US 3773177A
Authority
US
United States
Prior art keywords
concentrate
filter
concentrates
resin
container
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 - Lifetime
Application number
US00119339A
Other languages
English (en)
Inventor
H Queiser
O Meichsner
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.)
Licentia Patent Verwaltungs GmbH
Original Assignee
Licentia Patent Verwaltungs GmbH
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
Priority claimed from DE19702035925 external-priority patent/DE2035925C/de
Application filed by Licentia Patent Verwaltungs GmbH filed Critical Licentia Patent Verwaltungs GmbH
Application granted granted Critical
Publication of US3773177A publication Critical patent/US3773177A/en
Anticipated expiration legal-status Critical
Expired - Lifetime legal-status Critical Current

Links

Images

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
    • G21F9/04Treating liquids
    • G21F9/06Processing
    • G21F9/12Processing by absorption; by adsorption; by ion-exchange
    • 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
    • G21F9/04Treating liquids
    • G21F9/06Processing
    • 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
    • G21F9/04Treating liquids
    • G21F9/20Disposal of liquid waste

Definitions

  • the second-listed part is used for sump waters, laboratory waste waters, and decontamination waters from the entire control region (about 20 percent to 30 percent of the total waste-water load).
  • a primary problem here is that waste waters from resin-bead ion exchange filters can not be dewatered with a usual filter-cake-producing filter, because the resin beads as a result of their shape do not remain lying on the filter cloth or septum especially once their moisture content has sunk below a certain level. Because of this problem, filter-cake-producing filters have been automatically dropped from consideration whenever a concentrate containing resin beads must be dewatered.
  • Container 1 carries concengl g ififg g granulartrate entering through pipeline 45 and resulting from almnim m sili cates condensate cleaning.
  • the concentrates in containers 1, 2, 4 and 5 have a salt content lower than that of the concentrate in container 6 and particles of a size smaller than the particle size of the resin-beads in container 3.
  • any remaining, unfiltered slurry remaining in filter 11 is circuited back to container 9 through pipeline 44 and dewatering and drying is then carried out in a two-phase process.
  • the excess water is blown out of the filter cake with a flow of 20 C air equal to a flow rate of 200 standard cubic meters per hour per square meter of filter area, where the conditions for the standard cubic meter are 0 C and 760 mm Hg.
  • the filter cake is dried with a flow of 120 C air equal to a flow rate of standard cubic meters per square meter of filter area per hour.
  • Hood 8 contains infrared radiators which heat the concentrate in a container 17 from above. Air flow within the hood is controlled so that it passes over the liquid surface of the concentrate and withdraws vapor as it is produced by the radiators. A thermally caused circulating of the liquid concentrate in a container 17 prevents premature crusting on the sides of the container. Maintenance of the air flow within the hood and over the surface of the concentrate makes the hood and container interior have a negative pressure, so that no vapors can escape through any leaks at the connection between hood and container.
  • the bulk density of the powdered residue left in container 17, lies between 0.8 and 1.5 t/m where t 1,000 kilograms and m meters.
  • This procedure for handling evaporation concentrates is presently being used in an installation at the AEG Nuclear Energy Experimentation Center Grosswelzheim.
  • the installation can process 10 to 20 liters of evaporation concentrate per hour.
  • Air flow through hood 18 comes in from conduit 30 and has been heated by heater 31. Exhaust air laden with vapor leaves through conduit 32. The exhaust air is passed through a combined cyclone/sand filter unit 20 to remove any solid or liquid particles and is then forwarded by airtight blower 21. The exhaust air then passes through dry air cooler 24, where any condensable components are removed, and thence to exhaust chimney 33. Condensate and rinse water from the cyclone/sand filter are returned to container 6.

Landscapes

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Environmental & Geological Engineering (AREA)
  • Vaporization, Distillation, Condensation, Sublimation, And Cold Traps (AREA)
  • Processing Of Solid Wastes (AREA)
  • Heat Treatment Of Water, Waste Water Or Sewage (AREA)
US00119339A 1970-07-20 1971-02-26 Treatment process Expired - Lifetime US3773177A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
DE19702035925 DE2035925C (de) 1970-07-20 Verfahren zur Behandlung radioaktiver Ruckstande

Publications (1)

Publication Number Publication Date
US3773177A true US3773177A (en) 1973-11-20

Family

ID=5777301

Family Applications (1)

Application Number Title Priority Date Filing Date
US00119339A Expired - Lifetime US3773177A (en) 1970-07-20 1971-02-26 Treatment process

Country Status (2)

Country Link
US (1) US3773177A (GUID-C5D7CC26-194C-43D0-91A1-9AE8C70A9BFF.html)
JP (1) JPS5011040B1 (GUID-C5D7CC26-194C-43D0-91A1-9AE8C70A9BFF.html)

Cited By (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3962078A (en) * 1974-12-13 1976-06-08 Hydromation Filter Company Method and apparatus for treating liquid contaminated with radioactive particulate solids
US4033868A (en) * 1970-07-20 1977-07-05 Licentia Patent-Verwaltungs-G.M.B.H. Method and apparatus for processing contaminated wash water
US4274962A (en) * 1975-04-11 1981-06-23 Kraftwerk Union Aktiengesellschaft Apparatus for treating radioactive concentrates
US5324485A (en) * 1992-08-12 1994-06-28 Martin Marietta Energy Systems, Inc. Microwave applicator for in-drum processing of radioactive waste slurry
US5424042A (en) * 1993-09-13 1995-06-13 Mason; J. Bradley Apparatus and method for processing wastes
US5695642A (en) * 1995-08-15 1997-12-09 Greenleigh; Stephen H. Method for purifying contaminated water
US6085911A (en) * 1997-08-07 2000-07-11 Greenleigh; Stephen H. Method and apparatus for extracting metallic contaminants from substrates
US20160225475A1 (en) * 2015-02-01 2016-08-04 Kurion, Inc. Ion specific media removal from vessel for vitrification

Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US2081398A (en) * 1936-03-14 1937-05-25 Standard Oil Co Method of operating a continuous filter system
US2624955A (en) * 1949-02-21 1953-01-13 Clinton S Robison Salt drying and cooling apparatus
US3360869A (en) * 1961-06-09 1968-01-02 Muller Hans Method of drying filter residue
US3482693A (en) * 1965-11-18 1969-12-09 Mueller Hans Method and arrangement for separating solid material from a viscous substance

Patent Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US2081398A (en) * 1936-03-14 1937-05-25 Standard Oil Co Method of operating a continuous filter system
US2624955A (en) * 1949-02-21 1953-01-13 Clinton S Robison Salt drying and cooling apparatus
US3360869A (en) * 1961-06-09 1968-01-02 Muller Hans Method of drying filter residue
US3482693A (en) * 1965-11-18 1969-12-09 Mueller Hans Method and arrangement for separating solid material from a viscous substance

Cited By (9)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4033868A (en) * 1970-07-20 1977-07-05 Licentia Patent-Verwaltungs-G.M.B.H. Method and apparatus for processing contaminated wash water
US3962078A (en) * 1974-12-13 1976-06-08 Hydromation Filter Company Method and apparatus for treating liquid contaminated with radioactive particulate solids
US4274962A (en) * 1975-04-11 1981-06-23 Kraftwerk Union Aktiengesellschaft Apparatus for treating radioactive concentrates
US5324485A (en) * 1992-08-12 1994-06-28 Martin Marietta Energy Systems, Inc. Microwave applicator for in-drum processing of radioactive waste slurry
US5424042A (en) * 1993-09-13 1995-06-13 Mason; J. Bradley Apparatus and method for processing wastes
US5695642A (en) * 1995-08-15 1997-12-09 Greenleigh; Stephen H. Method for purifying contaminated water
US6085911A (en) * 1997-08-07 2000-07-11 Greenleigh; Stephen H. Method and apparatus for extracting metallic contaminants from substrates
US20160225475A1 (en) * 2015-02-01 2016-08-04 Kurion, Inc. Ion specific media removal from vessel for vitrification
US10290384B2 (en) * 2015-02-01 2019-05-14 Kurion, Inc. Ion specific media removal from vessel for vitrification

Also Published As

Publication number Publication date
DE2035925A1 (de) 1972-01-27
DE2035925B2 (de) 1972-11-09
JPS5011040B1 (GUID-C5D7CC26-194C-43D0-91A1-9AE8C70A9BFF.html) 1975-04-26

Similar Documents

Publication Publication Date Title
US4033868A (en) Method and apparatus for processing contaminated wash water
US4274962A (en) Apparatus for treating radioactive concentrates
US3773177A (en) Treatment process
JPS60178399A (ja) 放射性物質で汚染された部分を除染するための方法及び装置
US4569787A (en) Process and apparatus for treating radioactive waste
US4314877A (en) Method and apparatus for drying radioactive waste water concentrates from evaporators
CN101798768A (zh) 废纸再生环保设备及方法
CN201154922Y (zh) 凝结水复合式高温除油除铁装置
US3348599A (en) Apparatus for dewatering and dehydrating slimes and the like
US4268409A (en) Process for treating radioactive wastes
CA1069302A (en) Method and device for sludge treatment
SU501682A3 (ru) Способ захоронени радиоактивных или токсичных веществ
CN110066095A (zh) 一种市政污泥低温干化处理系统
JP3866373B2 (ja) 放射性廃液のろ過濃縮方法
Queiser et al. Treatment process
CN112349444A (zh) 一种处理低放射性悬浊液的桶内微波干燥装置
US5132019A (en) Method of removing corrosion products in a water circulation system
CN213752002U (zh) 一种处理低放射性悬浊液的桶内微波干燥装置
DE3827897C2 (GUID-C5D7CC26-194C-43D0-91A1-9AE8C70A9BFF.html)
RU2173489C2 (ru) Способ и устройство для разделения среды на содержащую твердое вещество и на жидкую составляющую
CN206950899U (zh) 湿热尾气处理系统
US3287819A (en) Waste disposal system
JPS61189499A (ja) 放射性廃水の多段処理方法
KR102481183B1 (ko) 방사성 폐기물 파라핀 고화체의 재처리방법 및 이에 사용되는 파라핀 분리장치
DE3222677C2 (GUID-C5D7CC26-194C-43D0-91A1-9AE8C70A9BFF.html)