FR1477058A - Process for treating water used for adjusting a nuclear reactor to recover boric acid - Google Patents

Process for treating water used for adjusting a nuclear reactor to recover boric acid

Info

Publication number
FR1477058A
FR1477058A FR58537A FR58537A FR1477058A FR 1477058 A FR1477058 A FR 1477058A FR 58537 A FR58537 A FR 58537A FR 58537 A FR58537 A FR 58537A FR 1477058 A FR1477058 A FR 1477058A
Authority
FR
France
Prior art keywords
adjusting
boric acid
nuclear reactor
water used
treating water
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
Application number
FR58537A
Other languages
French (fr)
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.)
UK Atomic Energy Authority
Original Assignee
UK Atomic Energy Authority
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 GB19550/65A external-priority patent/GB1080794A/en
Application filed by UK Atomic Energy Authority filed Critical UK Atomic Energy Authority
Priority to FR58537A priority Critical patent/FR1477058A/en
Application granted granted Critical
Publication of FR1477058A publication Critical patent/FR1477058A/en
Expired legal-status Critical Current

Links

Classifications

    • B—PERFORMING OPERATIONS; TRANSPORTING
    • B01—PHYSICAL OR CHEMICAL PROCESSES OR APPARATUS IN GENERAL
    • B01D—SEPARATION
    • B01D61/00—Processes of separation using semi-permeable membranes, e.g. dialysis, osmosis or ultrafiltration; Apparatus, accessories or auxiliary operations specially adapted therefor
    • B01D61/42—Electrodialysis; Electro-osmosis ; Electro-ultrafiltration; Membrane capacitive deionization
    • B01D61/44—Ion-selective electrodialysis
    • B—PERFORMING OPERATIONS; TRANSPORTING
    • B01—PHYSICAL OR CHEMICAL PROCESSES OR APPARATUS IN GENERAL
    • B01J—CHEMICAL OR PHYSICAL PROCESSES, e.g. CATALYSIS OR COLLOID CHEMISTRY; THEIR RELEVANT APPARATUS
    • B01J41/00—Anion exchange; Use of material as anion exchangers; Treatment of material for improving the anion exchange properties
    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01B—NON-METALLIC ELEMENTS; COMPOUNDS THEREOF; METALLOIDS OR COMPOUNDS THEREOF NOT COVERED BY SUBCLASS C01C
    • C01B35/00—Boron; Compounds thereof
    • C01B35/08—Compounds containing boron and nitrogen, phosphorus, oxygen, sulfur, selenium or tellurium
    • C01B35/10—Compounds containing boron and oxygen
    • C01B35/1045—Oxyacids
    • C01B35/1054—Orthoboric acid
    • C01B35/109—Purification; Separation; Concentration
    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01B—NON-METALLIC ELEMENTS; COMPOUNDS THEREOF; METALLOIDS OR COMPOUNDS THEREOF NOT COVERED BY SUBCLASS C01C
    • C01B5/00—Water
    • C01B5/02—Heavy water; Preparation by chemical reaction of hydrogen isotopes or their compounds, e.g. 4ND3 + 7O2 ---> 4NO2 + 6D2O, 2D2 + O2 ---> 2D2O
    • 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
    • G21C19/28—Arrangements for introducing fluent material into the reactor core; Arrangements for removing fluent material from the reactor core
    • G21C19/30—Arrangements for introducing fluent material into the reactor core; Arrangements for removing fluent material from the reactor core with continuous purification of circulating fluent material, e.g. by extraction of fission products deterioration or corrosion products, impurities, e.g. by cold traps
    • G21C19/307—Arrangements for introducing fluent material into the reactor core; Arrangements for removing fluent material from the reactor core with continuous purification of circulating fluent material, e.g. by extraction of fission products deterioration or corrosion products, impurities, e.g. by cold traps specially adapted for liquids
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C7/00—Control of nuclear reaction
    • G21C7/06—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
    • G21C7/22—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of a fluid or fluent neutron-absorbing material, e.g. by adding neutron-absorbing material to the coolant
    • B—PERFORMING OPERATIONS; TRANSPORTING
    • B01—PHYSICAL OR CHEMICAL PROCESSES OR APPARATUS IN GENERAL
    • B01D—SEPARATION
    • B01D2311/00—Details relating to membrane separation process operations and control
    • B01D2311/26—Further operations combined with membrane separation processes
    • B01D2311/2623—Ion-Exchange
    • 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

Landscapes

  • Chemical & Material Sciences (AREA)
  • Engineering & Computer Science (AREA)
  • Organic Chemistry (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Physics & Mathematics (AREA)
  • Water Supply & Treatment (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Inorganic Chemistry (AREA)
  • Health & Medical Sciences (AREA)
  • Urology & Nephrology (AREA)
FR58537A 1965-05-10 1966-04-21 Process for treating water used for adjusting a nuclear reactor to recover boric acid Expired FR1477058A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
FR58537A FR1477058A (en) 1965-05-10 1966-04-21 Process for treating water used for adjusting a nuclear reactor to recover boric acid

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
GB19550/65A GB1080794A (en) 1965-05-10 1965-05-10 Improvements in or relating to nuclear reactor installations
FR58537A FR1477058A (en) 1965-05-10 1966-04-21 Process for treating water used for adjusting a nuclear reactor to recover boric acid

Publications (1)

Publication Number Publication Date
FR1477058A true FR1477058A (en) 1967-04-14

Family

ID=26170126

Family Applications (1)

Application Number Title Priority Date Filing Date
FR58537A Expired FR1477058A (en) 1965-05-10 1966-04-21 Process for treating water used for adjusting a nuclear reactor to recover boric acid

Country Status (1)

Country Link
FR (1) FR1477058A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2444997A1 (en) * 1978-12-22 1980-07-18 Babcock Brown Boveri Reaktor Boron removal from nuclear reactor coolant - by passing side stream through reverse osmosis unit
FR2520545A1 (en) * 1982-01-27 1983-07-29 Framatome Sa METHOD AND DEVICE FOR MODIFYING THE CONCENTRATION OF THE SOLUBLE POISON CONTAINED IN THE REFRIGERANT FLUID OF THE PRIMARY CIRCUIT OF A NUCLEAR REACTOR

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2444997A1 (en) * 1978-12-22 1980-07-18 Babcock Brown Boveri Reaktor Boron removal from nuclear reactor coolant - by passing side stream through reverse osmosis unit
FR2520545A1 (en) * 1982-01-27 1983-07-29 Framatome Sa METHOD AND DEVICE FOR MODIFYING THE CONCENTRATION OF THE SOLUBLE POISON CONTAINED IN THE REFRIGERANT FLUID OF THE PRIMARY CIRCUIT OF A NUCLEAR REACTOR
EP0085611A1 (en) * 1982-01-27 1983-08-10 Framatome Method and device for modifying the concentration of a soluble poison in the coolant of the primary system of a nuclear reactor

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