CS364685A2 - Method of radioactive waste solution concentration from atomic power stations - Google Patents

Method of radioactive waste solution concentration from atomic power stations

Info

Publication number
CS364685A2
CS364685A2 CS853646A CS364685A CS364685A2 CS 364685 A2 CS364685 A2 CS 364685A2 CS 853646 A CS853646 A CS 853646A CS 364685 A CS364685 A CS 364685A CS 364685 A2 CS364685 A2 CS 364685A2
Authority
CS
Czechoslovakia
Prior art keywords
solution concentration
radioactive waste
waste solution
power stations
atomic power
Prior art date
Application number
CS853646A
Other languages
Czech (cs)
Other versions
CS274452B2 (en
Inventor
Tamas Dr Drozda
Tibor Dr Balini
Mihaly Dr Kristof
Gyula Dr Mozes
Peter Tilky
Gyula Simon
Jozsef Viszlay
Original Assignee
Magyar Asvanyolaj Es Foeldgaz
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 Magyar Asvanyolaj Es Foeldgaz filed Critical Magyar Asvanyolaj Es Foeldgaz
Publication of CS364685A2 publication Critical patent/CS364685A2/en
Publication of CS274452B2 publication Critical patent/CS274452B2/en

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/04—Treating liquids
    • G21F9/06—Processing
    • G21F9/08—Processing by evaporation; by distillation

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Heat Treatment Of Water, Waste Water Or Sewage (AREA)
  • Separation Using Semi-Permeable Membranes (AREA)
CS364685A 1984-05-21 1985-05-21 Method of radioactive waste solution concentration from atomic power stations CS274452B2 (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
HU194784A HU193209B (en) 1984-05-21 1984-05-21 Method for increasing the concentratability of nuclear power station radioactive waste solutions

Publications (2)

Publication Number Publication Date
CS364685A2 true CS364685A2 (en) 1990-08-14
CS274452B2 CS274452B2 (en) 1991-04-11

Family

ID=10956961

Family Applications (1)

Application Number Title Priority Date Filing Date
CS364685A CS274452B2 (en) 1984-05-21 1985-05-21 Method of radioactive waste solution concentration from atomic power stations

Country Status (7)

Country Link
CS (1) CS274452B2 (en)
DD (1) DD237235A1 (en)
DE (1) DE3515587A1 (en)
FR (1) FR2564632A1 (en)
GB (1) GB2159320B (en)
HU (1) HU193209B (en)
PL (1) PL253510A1 (en)

Families Citing this family (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
HU200971B (en) * 1984-09-12 1990-09-28 Magyar Asvanyolaj Es Foeldgaz Combined separation process for reducing inactive salt content of waste solutions of atomic power stations
DE4216383A1 (en) * 1992-05-18 1993-11-25 Siemens Ag Process for cleaning a closed container
RU2553266C1 (en) * 2014-02-13 2015-06-10 Федеральное государственное унитарное предприятие "Горно-химический комбинат" Method for heterogenic catalytic decomposition of oxalate ions, complexing agents and surfactants in process mediums of radiochemical plants

Family Cites Families (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
BE859028A (en) * 1977-09-26 1978-03-28 Belgonucleaire Sa WATER DECONTAMINATION PROCESS
DE3029147A1 (en) * 1980-07-31 1982-02-25 Kraftwerk Union AG, 4330 Mülheim Treatment of radioactive residue of waste liquor contg. borate - by adjusting sodium boron molar ratio during concn. by evapn.
HU185105B (en) * 1982-06-10 1984-12-28 Magyar Asvanyolaj Es Foeldgaz Method for producing waste solution concentrates of atomic power station having high salt concantration

Also Published As

Publication number Publication date
HU193209B (en) 1987-08-28
CS274452B2 (en) 1991-04-11
GB8512064D0 (en) 1985-06-19
DD237235A1 (en) 1986-07-02
GB2159320B (en) 1988-04-20
FR2564632A1 (en) 1985-11-22
PL253510A1 (en) 1986-02-25
DE3515587A1 (en) 1985-11-28
GB2159320A (en) 1985-11-27

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