[go: up one dir, main page]

Taube et al., 1980 - Google Patents

Reactor with very low fission product inventory

Taube et al., 1980

View PDF
Document ID
14296317823224634932
Author
Taube M
Heer W
et al.
Publication year

External Links

Snippet

A fast converter with one zone and an internal breeding ratio of 1.00, with liquid fuel in the form of molten plutonium--uranium-and sodium chloride, with a thermal power of 3 GW (th) allows continuous extraction of the volatile fission products (Br, I, Kr, Xe, Te) by means of …
Continue reading at inis.iaea.org (PDF) (other versions)

Classifications

    • 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 GASES [GHG] EMISSION, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors
    • Y02E30/40—Other aspects relating to nuclear fission
    • 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 GASES [GHG] EMISSION, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors
    • Y02E30/38—Fuel
    • 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
    • G21C19/42—Reprocessing of irradiated fuel
    • 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
    • G21F9/16—Processing by fixation in stable solid media
    • G21F9/167—Processing by fixation in stable solid media in polymeric matrix, e.g. resins, tars
    • 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
    • G21F9/28—Treating solids

Similar Documents

Publication Publication Date Title
CN105027224B (en) A Practical Molten Salt Fission Reactor
Zrodnikov et al. Innovative nuclear technology based on modular multi-purpose lead–bismuth cooled fast reactors
Ergen et al. The aircraft reactor experiment—physics
Greaves et al. The case for the thorium molten salt reactor
Krepel et al. TerraPower fast chloride reactor
Taube The transmutation of strontium-90 and cesium-137 in a high-flux fast reactor with a thermalized central region
Orlov et al. The closed on-site fuel cycle of the BREST reactors
Taube et al. Reactor with very low fission product inventory
Ignat’ev et al. Accident resistance of molten-salt nuclear reactor
US20240249851A1 (en) Molten salt reactor and passive fuel injection method therefor
Bowman Basis and objectives of the Los Alamos Accelerator‐Driven Transmutation technology project
Zrodnikov et al. SVBR-75/100 multipurpose modular low-power fast reactor with lead–bismuth coolant
Taube et al. Molten chlorides fast breeder reactor problems and possibilities
Holcomb Development Principles for Thermal-Spectrum Molten-Salt Breeder Reactors
Creasman Methodology for source term analysis of a molten salt reactor
Santora Assessment of core minimization options for breed-and-burn molten chloride fast reactors
Furukawa et al. Thorium cycle implementation through plutonium incineration by thorium molten-salt nuclear energy synergetics
Venneri et al. The Los Alamos accelerator driven transmutation of nuclear waste (ATW) concept development of the ATW target/blanket system
Orlov et al. Mononitride fuel and large scale nuclear power industry
Brey et al. The Fort St. Vrain high temperature gas-cooled reactor: XIII. Radiological and shielding performance of Fort St. Vrain
Yoo et al. Source Term Estimation in Station Blackout Accident of PHWR Plant for Emergency Response Planning
Hummel et al. Results of a phenomena identification and ranking table (PIRT) exercise for a severe accident in molten-salt small modular reactors
Parker et al. Impact of secondary effects on the reduction of fission product source terms in Class IX reactor accidents
Alekseev et al. Concept of the demonstration molten salt unit for the transuranium elements transmutation
Chuvillo et al. ITEP concept of the use of electro-nuclear facilities in the atomic power industry