GB1395431A - Method for removing radioactive iodine from a nuclear reactor sodium coolant - Google Patents

Method for removing radioactive iodine from a nuclear reactor sodium coolant

Info

Publication number
GB1395431A
GB1395431A GB2547673A GB2547673A GB1395431A GB 1395431 A GB1395431 A GB 1395431A GB 2547673 A GB2547673 A GB 2547673A GB 2547673 A GB2547673 A GB 2547673A GB 1395431 A GB1395431 A GB 1395431A
Authority
GB
United Kingdom
Prior art keywords
coolant
nuclear reactor
radioactive
sodium iodide
iodine
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
GB2547673A
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.)
CBS Corp
Original Assignee
Westinghouse Electric Corp
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 Westinghouse Electric Corp filed Critical Westinghouse Electric Corp
Publication of GB1395431A publication Critical patent/GB1395431A/en
Expired legal-status Critical Current

Links

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

Abstract

1395431 Nuclear reactor coolants WESTINGHOUSE ELECTRIC CORP 29 May 1973 [15 June 1972] 25476/73 Heading G6C In a process for removing radioactive I-131 and I-125 from a nuclear reactor sodium coolant by lowering the temperature of a part of the coolant to precipitate sodium iodide and returning the purified coolant to the main stream, non-radioactive iodine is added to the coolant before its temperature is lowered. As shown, a portion of the flow of liquid sodium coolant in line 1 is passed through pipe 11 into contact with non-radioactive sodium iodide at 12. When the whole of the coolant has become saturated with sodium iodide, the by-passed stream is diverted through cold trap 16 where sodium iodide including radioactive fission product iodine is deposited on wire mesh 17. The pipe 11 may be removed as a sample tube to determine the iodine concentration.
GB2547673A 1972-06-15 1973-05-29 Method for removing radioactive iodine from a nuclear reactor sodium coolant Expired GB1395431A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US26305472A 1972-06-15 1972-06-15

Publications (1)

Publication Number Publication Date
GB1395431A true GB1395431A (en) 1975-05-29

Family

ID=23000186

Family Applications (1)

Application Number Title Priority Date Filing Date
GB2547673A Expired GB1395431A (en) 1972-06-15 1973-05-29 Method for removing radioactive iodine from a nuclear reactor sodium coolant

Country Status (6)

Country Link
US (1) UST920001I4 (en)
JP (1) JPS4950398A (en)
DE (1) DE2329899A1 (en)
FR (1) FR2189820B1 (en)
GB (1) GB1395431A (en)
IT (1) IT993574B (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO1998012710A1 (en) * 1996-09-20 1998-03-26 Siemens Aktiengesellschaft Process and device for diminishing the risk of exposure to radioactive iodine during the revision of primary circuit components of a nuclear power station

Families Citing this family (6)

* 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
US4202730A (en) 1977-01-18 1980-05-13 The United States Of America As Represented By The Department Of Energy Radionuclide deposition control
US4088533A (en) 1977-01-18 1978-05-09 The United States Of America As Represented By The United States Department Of Energy Radionuclide trap
JPS57116296A (en) * 1981-01-13 1982-07-20 Tokyo Shibaura Electric Co Impurity removing device
JPS57117678U (en) * 1981-01-14 1982-07-21
USH262H (en) * 1983-11-25 1987-05-05 The United States Of America As Represented By The United States Department Of Energy Method of and apparatus for removing silicon from a high temperature sodium coolant

Family Cites Families (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB985400A (en) * 1960-12-30 1965-03-10 Atomic Energy Authority Uk Improvements in or relating to radioactive materials extraction processes
FR2184516B1 (en) * 1972-05-19 1978-09-01 Labo Electronique Physique

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO1998012710A1 (en) * 1996-09-20 1998-03-26 Siemens Aktiengesellschaft Process and device for diminishing the risk of exposure to radioactive iodine during the revision of primary circuit components of a nuclear power station

Also Published As

Publication number Publication date
FR2189820A1 (en) 1974-01-25
JPS4950398A (en) 1974-05-16
IT993574B (en) 1975-09-30
DE2329899A1 (en) 1974-01-03
UST920001I4 (en) 1974-03-05
FR2189820B1 (en) 1976-04-30

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Legal Events

Date Code Title Description
PS Patent sealed [section 19, patents act 1949]
PCNP Patent ceased through non-payment of renewal fee