ES428275A1 - Un metodo para reducir en el refrigerante de un reactor ato-mico la concentracion de gas radiactivo. - Google Patents
Un metodo para reducir en el refrigerante de un reactor ato-mico la concentracion de gas radiactivo.Info
- Publication number
- ES428275A1 ES428275A1 ES428275A ES428275A ES428275A1 ES 428275 A1 ES428275 A1 ES 428275A1 ES 428275 A ES428275 A ES 428275A ES 428275 A ES428275 A ES 428275A ES 428275 A1 ES428275 A1 ES 428275A1
- Authority
- ES
- Spain
- Prior art keywords
- gas
- reactor
- stable
- radioactive
- concentration
- 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
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
-
- 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
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Medicines Containing Antibodies Or Antigens For Use As Internal Diagnostic Agents (AREA)
- Nuclear Medicine (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
- Treating Waste Gases (AREA)
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
US05/379,675 US3944466A (en) | 1973-07-16 | 1973-07-16 | Reducing concentration of gases in nuclear reactor |
Publications (1)
Publication Number | Publication Date |
---|---|
ES428275A1 true ES428275A1 (es) | 1977-07-01 |
Family
ID=23498208
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
ES428275A Expired ES428275A1 (es) | 1973-07-16 | 1974-07-15 | Un metodo para reducir en el refrigerante de un reactor ato-mico la concentracion de gas radiactivo. |
Country Status (11)
Country | Link |
---|---|
US (1) | US3944466A (en, 2012) |
JP (1) | JPS5343638B2 (en, 2012) |
BE (1) | BE817652A (en, 2012) |
CA (1) | CA1010162A (en, 2012) |
CH (1) | CH583957A5 (en, 2012) |
DE (1) | DE2429761A1 (en, 2012) |
ES (1) | ES428275A1 (en, 2012) |
FR (1) | FR2238217B1 (en, 2012) |
GB (1) | GB1449709A (en, 2012) |
IT (1) | IT1015693B (en, 2012) |
SE (1) | SE415307B (en, 2012) |
Families Citing this family (12)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE2608162C2 (de) * | 1976-02-27 | 1984-10-31 | Kraftwerk Union AG, 4330 Mülheim | Verfahren zum Behandeln von radioaktiven Gasen und Gassystem zur Durchführung des Verfahrens |
DE2748160C2 (de) * | 1977-10-27 | 1984-06-07 | Brown Boveri Reaktor GmbH, 6800 Mannheim | Einrichtung zur Begasung von Primärkühlmittel einer wassergekühlten Kernreaktoranlage |
DE2748159C2 (de) * | 1977-10-27 | 1984-06-20 | Brown Boveri Reaktor GmbH, 6800 Mannheim | Einrichtung zur Begasung vom Primärkühlmittel einer wassergekühlten Kernreaktoranlage |
DE2828153C3 (de) * | 1978-06-27 | 1984-07-26 | Kraftwerk Union AG, 4330 Mülheim | Kernreaktor mit einem flüssigen Kühlmittel |
DE2948297C2 (de) * | 1978-06-27 | 1985-01-17 | Kraftwerk Union AG, 4330 Mülheim | Kernreaktor mit einem flüssigen Kühlmittel |
FR2483115A1 (fr) * | 1980-05-23 | 1981-11-27 | Framatome Sa | Dispositif de recueil des liquides et des gaz de purge dans une installation renfermant des substances pouvant presenter une certaine radioactivite |
DE3105168C2 (de) * | 1981-02-13 | 1984-11-29 | Brown Boveri Reaktor GmbH, 6800 Mannheim | Anordnung zur Versorgung des Hauptkühlmittels einer wassergekühlten Kernreaktoranlage mit Wasserstoff |
JPS61135739U (en, 2012) * | 1985-02-14 | 1986-08-23 | ||
US5768329A (en) * | 1996-01-30 | 1998-06-16 | Northrop Grumman Corporation | Apparatus for accelerator production of tritium |
US6059270A (en) * | 1997-11-06 | 2000-05-09 | Kkb 02 Fluid Production Gmbh | Liquid enriched with a gas, a method of enriching a liquid with a gas, and an apparatus for enriching a liquid with a gas |
US5938821A (en) * | 1998-02-05 | 1999-08-17 | The United States Of America As Represented By The United States Department Of Energy | Drum bubbler tritium processing system |
US20160225470A1 (en) | 2015-02-03 | 2016-08-04 | Westinghouse Electric Company Llc | Apparatus for degassing a nuclear reactor coolant system |
Family Cites Families (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US3155469A (en) * | 1962-01-05 | 1964-11-03 | Linde Eismasch Ag | Process for removing trace admixtures from reactor coolant gas |
US3362883A (en) * | 1966-02-08 | 1968-01-09 | Westinghouse Electric Corp | Disposal system for contaminated hydrogen from a nuclear reactor |
-
1973
- 1973-07-16 US US05/379,675 patent/US3944466A/en not_active Expired - Lifetime
-
1974
- 1974-06-17 CA CA202,602A patent/CA1010162A/en not_active Expired
- 1974-06-21 DE DE2429761A patent/DE2429761A1/de active Pending
- 1974-07-05 IT IT24836/74A patent/IT1015693B/it active
- 1974-07-05 GB GB2984974A patent/GB1449709A/en not_active Expired
- 1974-07-15 JP JP8028874A patent/JPS5343638B2/ja not_active Expired
- 1974-07-15 ES ES428275A patent/ES428275A1/es not_active Expired
- 1974-07-15 BE BE146553A patent/BE817652A/xx not_active IP Right Cessation
- 1974-07-15 FR FR7424547A patent/FR2238217B1/fr not_active Expired
- 1974-07-16 CH CH977074A patent/CH583957A5/xx not_active IP Right Cessation
- 1974-07-16 SE SE7409299A patent/SE415307B/xx not_active IP Right Cessation
Also Published As
Publication number | Publication date |
---|---|
FR2238217B1 (en, 2012) | 1978-12-01 |
GB1449709A (en) | 1976-09-15 |
SE415307B (sv) | 1980-09-22 |
CH583957A5 (en, 2012) | 1977-01-14 |
FR2238217A1 (en, 2012) | 1975-02-14 |
CA1010162A (en) | 1977-05-10 |
US3944466A (en) | 1976-03-16 |
JPS5343638B2 (en, 2012) | 1978-11-21 |
JPS5037997A (en, 2012) | 1975-04-09 |
DE2429761A1 (de) | 1975-02-06 |
SE7409299L (en, 2012) | 1975-02-26 |
BE817652A (fr) | 1975-01-15 |
IT1015693B (it) | 1977-05-20 |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
ES428275A1 (es) | Un metodo para reducir en el refrigerante de un reactor ato-mico la concentracion de gas radiactivo. | |
ES439039A1 (es) | Un procedimiento de extraccion, de captura y de almacena- miento del yodo radiactivo contenido en los combustibles nu-cleares irradiados. | |
JPS5356497A (en) | Fuel storage rack for nuclear reactor | |
GB967067A (en, 2012) | ||
GB1436465A (en) | Methods of operating at least two nuclear reactors | |
ES435463A1 (es) | Perfeccionamientos introducidos en reactores nucleares. | |
DE2249429A1 (de) | Verfahren zur umwandlung von langlebigen spaltprodukten oder radionukliden mit langer halbwertszeit | |
GB1043713A (en) | Method of and apparatus for treating bituminous material or hydrocarbons underground with energy from nuclear fission | |
GB903489A (en) | Improvements in or relating to core elements for nuclear reactors | |
GB1454189A (en) | Method for preventing tritium contamination in a nuclear reactor | |
GB1193950A (en) | Kinetic Intense Neutron Generator Reactor | |
GB873594A (en) | Cluster arrangement of fuel elements in an atomic reactor | |
FR2128391A1 (en) | Nuclear fuel particles - with decreased swelling when irradiated by adding gadolinium caesium, yttrium tungsten and/or molybdenum oxid | |
GB1315875A (en) | Method and device for loading nuclear fuel cans | |
BELL et al. | Long-term hazard of radioactive wastes produced by the Enriched uranium, Pu-U-238, and U-233-Th fuel cycles(Long term hazard of high level and alpha radioactive wastes produced by enriched uranium, Pu-(U-238), and(U-233)-Th fuel cycles) | |
Perelygin et al. | The Half-life of a Spontaneously Fissioning Isomer | |
TAHERZADEH | Neutron radiation characteristics of plutonium dioxide fuel(Utilization of neutron radiation from PuO 2 decay to provide spacecraft electric power) | |
TAHERZADEH | Neutron radiation characteristics of plutonium dioxide fuel(Neutron emission rate from plutonium dioxide nuclear fuel) | |
Sivintsev | Was the Chazhma accident a Chernobyl of the Far East? | |
FURUTA et al. | Effect of alpha-ray irradiation on creep rupture properties of austenitic stainless steel(Helium ion irradiation effects on creep and rupture properties of austenitic stainless steel) | |
GB1303977A (en, 2012) | ||
DEFAYETTE et al. | Experiment design studies for fuel pin development(Method for simulating irradiation of fuel pin proposed for space power reactor in Plum Brook Reactor) | |
GB1019420A (en) | Organic moderated nuclear reactor and control method therefor | |
Robinson et al. | The Yields of the Chemical Elements in Thermal Neutron Fission of U-235 | |
GB858991A (en) | Improvements relating to nuclear fuel elements |