UST921014I4 - Colburn mbthod for removing fission products from a nuclear reactor coolant - Google Patents

Colburn mbthod for removing fission products from a nuclear reactor coolant Download PDF

Info

Publication number
UST921014I4
UST921014I4 US921014DH UST921014I4 US T921014 I4 UST921014 I4 US T921014I4 US 921014D H US921014D H US 921014DH US T921014 I4 UST921014 I4 US T921014I4
Authority
US
United States
Prior art keywords
reactor coolant
mbthod
colburn
nuclear reactor
fission products
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.)
Pending
Application number
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 filed Critical
Application granted granted Critical
Publication of UST921014I4 publication Critical patent/UST921014I4/en
Pending legal-status Critical Current

Links

Images

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
    • G21C19/28—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
    • G21C19/31—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 for molten metals
    • 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

Definitions

  • PUBLISHED APRIL 16, 1974 coouNo svsym ems A method for removing cesium 137, iodine 131 and tritium from a liquid sodium reactor coolant. Hydrogen is introduced into the liquid sodium causing sodium hydride to precipitate in a cold trap. The cesium iodine and tritium isotopes are removed from the liquid sodium by coprecipitating as impurities in the sodium hydride.

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)
  • Treating Waste Gases (AREA)

Abstract

A METHOD FOR REMOVING CESIUM 137, IODINE 131 AND TRITIUM FROM A LIQUID SODIUM REACTOR COOLANT. HYDROGEN IS INTRODUCED INTO THE LIQUID SODIUM CAUSING SODIUM HYDRIDE TO PRECIPITATE IN A COLD TRAP. THE CESIUM IODINE AND TRITIUM ISOTOPES ARE REMOVED FROM THE LIQUID SODIUM BY COPRECIPITATING AS IMPURITIES IN THE SODIUMM HYDRIDE.

Description

DEFENSIVE PULICATION UNITED STATES PATENT OFFICE Published at the request of the applicant or owner in accordance with the Notice of Dec. 16, 1969, 869 0.G. 687. The abstracts of Defensive Publication applications are identified by distinctly numbered series and are arranged chronologically. The heading of each abstract indicates the number of pages of specification, including claims and sheets of drawings contained in the application as originally filed. The files of these applications are available to the public for inspection and reproduction may be purchased for 30 cents a sheet.
Defensive Publication applications have not been examined as to the merits of alleged invention. The Patent Oflice makes no assertion as to the novelty of the disclosed subject matter.
PUBLISHED APRIL 16, 1974 coouNo svsym ems A method for removing cesium 137, iodine 131 and tritium from a liquid sodium reactor coolant. Hydrogen is introduced into the liquid sodium causing sodium hydride to precipitate in a cold trap. The cesium iodine and tritium isotopes are removed from the liquid sodium by coprecipitating as impurities in the sodium hydride.
April 16, 1974 A NUCLEAR REACTOR COOLANT Filed June @551 1 M9365 I 53356 RE 562,206 Em 38 Em \m \v 360 360 2596 f @2308 ozjooo
US921014D 1972-06-09 1972-06-09 Colburn mbthod for removing fission products from a nuclear reactor coolant Pending UST921014I4 (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US26147672A 1972-06-09 1972-06-09

Publications (1)

Publication Number Publication Date
UST921014I4 true UST921014I4 (en) 1974-04-16

Family

ID=22993472

Family Applications (2)

Application Number Title Priority Date Filing Date
US921014D Pending UST921014I4 (en) 1972-06-09 1972-06-09 Colburn mbthod for removing fission products from a nuclear reactor coolant
US05/493,368 Expired - Lifetime US4075060A (en) 1972-06-09 1974-07-31 Method for removing fission products from a nuclear reactor coolant

Family Applications After (1)

Application Number Title Priority Date Filing Date
US05/493,368 Expired - Lifetime US4075060A (en) 1972-06-09 1974-07-31 Method for removing fission products from a nuclear reactor coolant

Country Status (6)

Country Link
US (2) UST921014I4 (en)
JP (1) JPS5232436B2 (en)
DE (1) DE2328660A1 (en)
FR (1) FR2188252B1 (en)
GB (1) GB1393355A (en)
IT (1) IT993570B (en)

Families Citing this family (11)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CA1071415A (en) * 1975-09-18 1980-02-12 The Government Of The United States As Represented By The United States Department Of Energy Method for the recovery of halogens from sodium
JPS5450800A (en) * 1977-09-30 1979-04-20 Toshiba Corp Removing device of radioactive substance
DE2746159A1 (en) * 1977-10-14 1979-04-19 Interatom NUCLEAR ENERGY SYSTEM WITH EQUIPMENT FOR COOLANT CLEANING
JPS5480216A (en) * 1977-12-09 1979-06-26 Hitachi Ltd Operation method for liquid metal cooled reactor
DE2828153C3 (en) * 1978-06-27 1984-07-26 Kraftwerk Union AG, 4330 Mülheim Nuclear reactor with a liquid coolant
DE3017585C2 (en) * 1980-05-08 1984-05-30 Brown Boveri Reaktor GmbH, 6800 Mannheim Process and arrangement for lowering the pressure in the containment of a nuclear reactor plant
JPS5845600A (en) * 1981-09-11 1983-03-16 動力炉・核燃料開発事業団 Method of removing hydrogen from fast breeder secondary system
US4587083A (en) * 1983-08-10 1986-05-06 The United States Of America As Represented By The United States Department Of Energy Method for removing cesium from a nuclear reactor coolant
US6272226B1 (en) 1997-04-02 2001-08-07 Scientific-Atlanta, Inc. Apparatus and method for masking audio signals in a signal distribution system
FR2859042B1 (en) * 2003-08-19 2005-11-18 Framatome Anp PROCESS AND PLANT FOR PROCESSING ALKALINE METALS CHARGED WITH TRITIUM OR COMPONENTS SUBJECTED BY ALKALINE METALS CHARGED WITH TRITIUM
RU2614048C1 (en) * 2016-03-18 2017-03-22 Российская Федерация, от имени которой выступает Государственная корпорация по атомной энергии "Росатом" Nuclear power plant with heat carrier cleaning system

Family Cites Families (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US2745552A (en) * 1953-09-02 1956-05-15 Warren H Bruggeman Filter with fractional crystallization means
GB1285088A (en) * 1969-12-18 1972-08-09 Atomic Energy Authority Uk Cold traps for liquid metal

Also Published As

Publication number Publication date
GB1393355A (en) 1975-05-07
US4075060A (en) 1978-02-21
FR2188252A1 (en) 1974-01-18
FR2188252B1 (en) 1976-05-07
JPS4962898A (en) 1974-06-18
JPS5232436B2 (en) 1977-08-22
DE2328660A1 (en) 1974-01-10
IT993570B (en) 1975-09-30

Similar Documents

Publication Publication Date Title
UST921014I4 (en) Colburn mbthod for removing fission products from a nuclear reactor coolant
UST921019I4 (en) Core for a nuclear reactor
UST921016I4 (en) Removal op radioactive contamination prom a nuclear reactor coolant
Coppinger et al. Heat Problems in the Disposal of High Level Radioactive Wastes
US2833618A (en) Separating uranium containing solids suspended in a liquid
UST937001I4 (en) Comtois etal thermal nuclear reactor
UST901028I4 (en) Shield plug access enclosure for a nuclear reactor
Merten et al. The preparation and properties of zirconium-uranium-hydrogen alloys
Franks et al. Polygonization in copper
Mauer et al. Solubility effects on the corrosion of nuclear defense waste glasses
Chapman Measurement of an Effective Neutron Removal Cross Section of Lithium at the Lid Tank Shielding Facility
UST892007I4 (en) Defensive publication
UST901027I4 (en) Nuclear reactor having thermally compensated support structure for a fuel assembly
UST883001I4 (en) Core structures for nuclear reactors
Billington Relaxing reliance on empirical data
GB966366A (en) Improvements in or relating to fuel elements for nuclear reactors
Holm Nuclear reactor theory: JJ Syrett,(Nuclear Engineering Monographs II)(viii–80 p., 12s 6d.)
Amelinckx Radiation-induced precipitation sites in potassium chloride
Brittan et al. Technical Review of ZPR-I Accidental Transient-The Power Excursion, Exposers, and Clinical Data
Kuz'menko et al. Dependence of proton pairing energy for Dy, Gd, Sm isotope nuclei on neutron number
Tsen SOME THERMODYNAMIC PROBLEMS INVOLVED IN THE REDUCTION OF RARE METAL OXIDES
Tabuchi et al. STUDY OF EPIDEMIOLOGICAL FACTORS AFFECTING THE FREQUENCY OF OCCURRENCE OF CONGENITAL ANOMALIES
Runnals Method of making alloys of beryllium with plutonium and the like
Steinegger A PROCESS FOR PREPARING BORON-PARAFFIN SHIELDING BLOCKS
Henry et al. Neptunium behavior in solvent extraction of uranium at Savannah River Plant